KINDAI UNIVERSITY


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SANO Tadafumi

Profile

FacultyAtomic Energy Research Institute
PositionAssociate Professor
DegreePh.D. in Engineering
Commentator Guidehttps://www.kindai.ac.jp/meikan/2405-sano-tadafumi.html
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Last Updated :2020/09/02

Research Activities

Research Areas

  • Energy, Nuclear engineering

Published Papers

  • Improving nuclear data accuracy of 241Am and 237Np capture cross sections, Gašper Žerovnik, Peter Schillebeeckx, Danie l Cano-Ott, Marian Jandel, Jun-ichi Hori, Atsushi Kimura, Matthias Rossbach, Alain Letourneau, Gilles Noguere, Pierre Leconte, Tadafumi Sano, Mark A Kellett, Osamu Iwamoto, Anatoly V Ignatyuk, Oscar Cabellos, Christoph Genreith, Hideo Harada, EDP Sciences, EDP Sciences, 146, 11035, Oct. 2017 , Refereed
  • Research and development for accuracy improvement of neutron nuclear data on minor actinides, H. Harada, O. Iwamoto, N. Iwamoto, A. Kimura, K. Terada, T. Nakao, S. Nakamura, K. Mizuyama, M. Igashira, T. Katabuchi, T. Sano, Y. Shibahara, Y. Takahashi, K. Takamiya, C. H. Pyeon, S. Fukutani, T. Fujii, J. Hori, H. Yashima, EPJ Web of Conferences, EPJ Web of Conferences, 146, 11001, Oct. 2017 , Refereed
  • Non-destructive assay of nuclear materials using a self-indication method, J. Hori, T. Sano, Y. Takahashi, J. Lee, H. Unesaki, K. Nakajima, EPJ Web of Conferences, EPJ Web of Conferences, 146, 09042, Oct. 2017 , Refereed
  • Influence of the neutron transport tube on neutron resonance densitometry, F. Kitatani, H. Tsuchiya, J. Takamine, J. Hori, T. Sano, EPJ Web of Conferences, EPJ Web of Conferences, 146, 09032, Oct. 2017 , Refereed
  • Analysis of energy resolution in the KURRI-LINAC pulsed neutron facility, T. Sano, J. Hori, Y. Takahashi, H. Yashima, J. Lee, H. Harada, EPJ Web of Conferences, EPJ Web of Conferences, 146, 03031, Oct. 2017 , Refereed
  • High precision analysis of isotopic composition for samples used for nuclear cross-section measurements, Y. Shibahara, J. Hori, K. Takamiya, T. Fujii, S. Fukutani, T. Sano, H. Harada, EPJ Web of Conferences, EPJ Web of Conferences, 146, 03028, Oct. 2017 , Refereed
  • Evaluation of Sample-dependent Background at the KURRI-LINAC using a Time-of-Flight Method, J. Lee, J. Hori, T. Sano, K. Nakajima, Proceeding of Reactor Physics Asia 2017, Proceeding of Reactor Physics Asia 2017, 74 - 78, Aug. 2017 , Refereed
  • Pulsed Neutron Imaging for Non-destructive Testing using Simulated Nuclear Fuel Samples, D. Ito, T. Sano, J. Hori, Y. Takahashi, H. Hasemi, T. Kamiyama, K. Nakajima, Physics Procedia, Physics Procedia, 88, 89 - 94, Aug. 2017 , Refereed
  • Measurement of Doppler Effect for Metallic Fuel Alloy, T. Sano, J. Hori, H. Unesaki, Y. Takahashi, A. Hara, K. Nakajima, Energy Procedia, Energy Procedia, 131C, 292 - 298, 2017 , Refereed
  • Development of In-reactor Observation System Using Cherenkov Light (VI), T. Takeuchi, K. Yamamoto, N. Otsuka, H. Shibata, A. Shibata, N. Takemoto, K. Tsuchiya, T. Sano, H. Unesaki, Y. Fujihara, Y. Takahashi, K. Nakajima, KURRI Prog. Rep., KURRI Prog. Rep., May 2015
  • EVALUATION OF NEUTRON SPECTRUM AT IN-CORE IRRADIATION EQUIPMENTS IN KUR WITH LOW ENRICHED URANIUM FUEL, SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, NAKAJIMA KEN, Proceeding of PHYSOR2014, Proceeding of PHYSOR2014, (2014-003), 1126220 (WEB ONLY), Mar. 2015 , Refereed
  • POWER SPECTRAL ANALYSIS FOR A SUBCRITICAL REACTOR SYSTEM DRIVEN BY A PULSED SPALLATION NEUTRON SOURCE, SAKON ATSUSHI, HOHARA SIN-YA, SUGIYAMA WATARU, HASHIMOTO KENGO, PYEON CHEOL HO, SANO TADAFUMI, YAGI TAKAHIRO, Proceeding of PHYSOR2014, Proceeding of PHYSOR2014, (2014-003), 1102582 (WEB ONLY), Mar. 2015 , Refereed
  • ANALYSIS OF INTEGRAL EXPERIMENT FOR THORIUM FUEL CYCLE AT KYOTO UNIVERSITY CRITICAL ASSEMBLY, TAKAHASHI YOSHIYUKI, SANO TADAFUMI, HORI JUN-ICHI, UNESAKI HIRONOBU, NAKAJIMA KEN, Proceeding of PHYSOR2014, Proceeding of PHYSOR2014, (2014-003), 1127688 (WEB ONLY), Mar. 2015 , Refereed
  • Neutron Capture Cross Section Measurements on 232Th with a Total Absorption BGO Spectrometer at KURRI-LINAC, HORI JUN-ICHI, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, UNESAKI HIRONOBU, NAKAJIMA KEN, Proceeding of PHYSOR2014, Proceeding of PHYSOR2014, (2014-002), 121-126 (WEB ONLY), Feb. 2015 , Refereed
  • Analysis of Integral Experiment for Th-232 (n,.GAMMA.) Reaction Cross Section at KUCA, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, HORI JUN-ICHI, UNESAKI HIRONOBU, NAKAJIMA KEN, 日本原子力研究開発機構JAEA-Conf(Web), 日本原子力研究開発機構JAEA-Conf(Web), (2014-002), 167-173 (WEB ONLY), Feb. 2015
  • Establishment of Irradiation Procedure for 99Mo/99mTc Production by (n, ) Method After JMTR Re-start, T. ISHIDA, T. SHIINA, A. OHTA, A. KIMURA, K. NISHIKATA, A. SHIBATA, M. TANASE, M. KOBAYASHI, T. SANO, K TSUCHIYA, 2015
  • Neutron Irradiation Effect of High-density MoO3 pellets for Mo-99 Production (2), K. Nishikata, T. Ishida, M. Yonekawa, Y. Kato, M. Kurosawa, A. Kimura, K. Tsuchiya, T. Sano, Y. Fujihara, J. Zhang, KURRI Prog. Rep., KURRI Prog. Rep., 2015
  • AIMACプロジェクトにおけるMA核データの積分実験, SANO TADAFUMI, HORI JUN'ICHI, YAGI TAKAHIRO, TAKAHASHI YOSHIYUKI, YASHIMA HIROSHI, PYEON CHEOL HO, TAKAMIYA KOICHI, HARADA HIDEO, KURRI KR (CD) (CD-ROM), KURRI KR (CD) (CD-ROM), (50), ROMBUNNO.10, 2015
  • 中性子共鳴濃度分析法における中性子輸送系の開発, KITATANI FUMITO, KOIZUMI MITSUO, TSUCHIYA HARUFUMI, TAKAMINE JUN, KURETA MASATOSHI, HARADA HIDEO, SEYA MICHIO, HORI JUN'ICHI, SANO TADAFUMI, KURRI KR, KURRI KR, (200), 41, Jan. 2015
  • Application of Cherenkov Light Observation to Reactor Measurements (1) - Estimation of Reactor Power from Cherenkov Light Intensity -, YAMAMOTO KEIICHI, TAKEUCHI TOMOAKI, SANO TADAFUMI, HONMA RYOHEI, KIMURA NOBUAKI, OTSUKA NORIAKI, KOSUGE FUMIAKI, NAKAJIMA KEN, TSUCHIYA KUNIHIKO, 日本原子力研究開発機構JAEA-Technology(Web), 日本原子力研究開発機構JAEA-Technology(Web), (2014-028), WEB ONLY, Jan. 2015
  • Determination of prompt-neutron decay constant from phase shift between beam current and neutron detection signals for an accelerator-driven system in the Kyoto University Critical Assembly, SAKON ATSUSHI, HASHIMOTO KENGO, SUGIYAMA WATARU, HOHARA SIN-YA, PYEON CHEOL HO, SANO TADAFUMI, YAGI TAKAHIRO, OHSAWA TAKAAKI, J Nucl Sci Technol, J Nucl Sci Technol, 52(1-2), 203 - 212, Jan. 2015 , Refereed
  • Survey on Effect of Crystal Texture of Beryllium on Total Cross-Section to Improve Neutronic Evaluation in JMTR, N.Takemoto, T.Imaizumi, N.Kimura, K.Tsuchiya, J.Hori, T.Sano, K.Nakajima, Proceeding of PHYSOR2014, Proceeding of PHYSOR2014, 2014 , Refereed
  • Estimation of Reaction Rate in Subcritical System by Gamma Ray Spectrum Measurement, NAUCHI YASUSHI, OHTA HIROKAZU, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, YAGI TAKAHIRO, KAMEYAMA TAKANORI, 日本原子力研究開発機構JAEA-Conf(Web), 日本原子力研究開発機構JAEA-Conf(Web), (2013-002), 33 (WEB ONLY), Oct. 2013
  • Development of In-reactor Observation System Using Cherenkov Light (V), N. Ohtsuka, T. Takeuchi, K. Yamamoto, A. Shibata, N. Kimura, N. Takemoto, M. Tanimoto, K. Tsuchiya, T. Sano, H. Unesaki, Y. Fujihara, Y. Takahashi, K. Nakajima, KURRI Prog. Rep., KURRI Prog. Rep., May 2013
  • KURの微調整棒に対する粗調整棒の制御棒干渉効果の測定, SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, NAKAMORI AKIRA, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN, KURRI KR, KURRI KR, (176), 51 - 56, Jan. 2013
  • B2実験孔照射装置の特性評価, TAKAMIYA KOICHI, YOSHIDA YUYA, TANAKA HIROKI, SANO TADAFUMI, YOSHINO HIROFUMI, OKUMURA RYO, IINUMA YUTO, KURRI KR, KURRI KR, (176), 124 - 126, Jan. 2013
  • KUR反応度測定システムの開発とその適用, NAKAMORI AKIRA, SANO TADAFUMI, ZHANG JIAN, FUJIHARA YASUYUKI, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN, KURRI KR, KURRI KR, (176), 78 - 83, Jan. 2013
  • Sensitivity Analysis for Kyoto University Research Reactor Using JENDL-4.0, SANO TADAFUMI, NAKAJIMA KEN, UNESAKI HIRONOBU, 日本原子力研究開発機構JAEA-Conf(Web), 日本原子力研究開発機構JAEA-Conf(Web), (2012-001), 35 (WEB ONLY), Jul. 2012
  • 使用済燃料キャスク内の収納体数増加手法の検討(3)―燃料集合体からの漏洩中性子数の定量測定―, NAUCHI YASUSHI, KAMEYAMA TAKANORI, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, YAGI TAKAHIRO, 電力中央研究所原子力技術研究所研究報告, 電力中央研究所原子力技術研究所研究報告, (L11004), 27P, Jun. 2012
  • KUR反応度測定システムについて, NAKAMORI TERU, HASEGAWA KEI, TSUCHIYAMA TATSUO, YAMAMOTO TOSHIHIRO, OKUMURA RYO, SANO TADAFUMI, UTNL-R(東京大学大学院工学系研究科原子力専攻), UTNL-R(東京大学大学院工学系研究科原子力専攻), (0480), 4.1-4.8, 2012
  • KUR炉心内照射領域における中性子束測定, FUJIWARA YASUYUKI, SANO TADAFUMI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 46th, 73 - 78, Jan. 2012
  • DEVELOPMENT OF INSTRUMENTS FOR IMPROVED SAFETY MEASURE FOR LWRs, T. Takeuchi, A. Shibata, H. Nagata, K. Miura, T. Sano, N. Kimura, N. Ohtsuka, T. Saito, J. Nakamura, K. Tsuchiya, 5th International Symposium on Material Testing Reactors (ISMTR-6), 5th International Symposium on Material Testing Reactors (ISMTR-6), 2012 , Refereed
  • Feynman-alpha Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14 MeV Neutron Source, Hiroshi Taninaka, Atsuko Miyoshi, Kengo Hashimoto, Cheol Ho Pyeon, Tadafumi Sano, Tsuyoshi Misawa, Wataru Sugiyama, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48(9), 1272 - 1280, Sep. 2011 , Refereed
    Summary:In a series of Feynman-alpha correlation measurements for a thermal Accelerator-Driven System (ADS) with 14 MeV neutrons at the Kyoto University Critical Assembly (KUCA), an unstable accelerator condition such as a drift of beam current has been frequently observed. Neutron source instability caused by such unavoidable beam-current instability resulted in a divergent variance-to-mean ratio and, consequently, the correlation analysis failed. Nevertheless, we attempted to apply a difference-filtering technique to the correlation analysis to reduce the influence of the above instability. The present attempt resulted in consistent prompt-neutron decay constants with those obtained in a previous pulsed neutron experiment. The application of the filtering is expected to enhance the robustness of Feynman-alpha analysis against various instabilities of accelerator operation in actual ADS.
  • 京都大学研究用原子炉低濃縮ウラン燃料炉心について, SANO TADAFUMI, KURRI KR, KURRI KR, (158), 14 - 32, Feb. 2011
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(3)中性子束分布及び出力校正, ZHANG JIAN, SANO TADAFUMI, FUJIHARA YASUYUKI, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, NAKAJIMA KEN, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 45th, 88 - 93, Jan. 2011
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(2)各種反応度測定, SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 45th, 82 - 87, Jan. 2011
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(1)臨界近接及び制御棒校正, FUJIHARA YASUYUKI, SANO TADAFUMI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, TSUCHIYAMA TATSUO, HASEGAWA KIYOSHI, NAKAMORI AKIRA, MISAWA TSUYOSHI, UNESAKI HIRONOBU, NAKAJIMA KEN, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 45th, 77 - 81, Jan. 2011
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験, CHO KEN, SANO TADAFUMI, FUJIWARA YASUYUKI, TAKAHASHI YOSHIYUKI, TSUCHIYAMA TATSUO, NAKAMORI TERU, HASEGAWA KEI, ONO KAZUOMI, MARUYAMA NAOYA, MISAWA TSUYOSHI, UNESAKI HIRONOBU, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN, UTNL-R(東京大学大学院工学系研究科原子力専攻), UTNL-R(東京大学大学院工学系研究科原子力専攻), (0477), 3.1-3.9, 2011
  • DEVELOPMENT OF A SURVEILLANCE SYSTEM WITH MOTION DETECTION AND SELF-LOCATION CAPABILITY, M. Tanigaki, T. Sano, Y. Hirai, M. Miyabe, S. Fukutani, H. Kawabe, Y. Kobayashi, Y. Kuriyama, N. Sato, K. Takamiya, Y. Morimoto, ICALEPCS 2011, ICALEPCS 2011, 0 - 0, 2011
  • Full Core Conversion of the Kyoto University Research Reactor (KUR) from HEU to LEU, H. Unesaki, T. Sano, T. Misawa, K. Nakajima, 32nd International Meeting on Reduced Enrichment for Research and Test Reactors, 32nd International Meeting on Reduced Enrichment for Research and Test Reactors, Oct. 2010
  • NUCLEAR DSIGN OF KYOTO UNIVERSITY RESEARCH REACTOR (KUR) WITH LEU CORE, Tadafumi Sano, Hironobu Unesaki, Ken Nakajima, 32nd nternational Meeting on Reduced Enrichment for Research and Test Reactors, 32nd nternational Meeting on Reduced Enrichment for Research and Test Reactors, Oct. 2010
  • SRACを用いたKUR低濃縮燃料炉心の臨界近接手順の検討, FUJIHARA YASUYUKI, SANO TADAFUMI, ZHANG JIAN, NAKAJIMA KEN, UNESAKI HIRONOBU, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 44th, 94 - 99, Jan. 2010
  • SRACを用いたKUR低濃縮燃料炉心の温度係数の評価, ZHANG JIAN, SANO TADAFUMI, FUJIHARA YASUYUKI, NAKAJIMA KEN, UNESAKI HIRONOBU, 京都大学原子炉実験所学術講演会報文集, 京都大学原子炉実験所学術講演会報文集, 44th, 88 - 93, Jan. 2010
  • Preliminary Experimental Results on Measurement of Erbia Content in Uranium Fuel Using PGAA, TKAMATSU TERUHISA, SUGIMURA NAOKI, SANO TADAFUMI, Trans Am Nucl Soc, Trans Am Nucl Soc, 103, 222 - 223, 2010 , Refereed
  • Determination of Lambda-Mode Eigenvalue Separation of a Thermal Accelerator-Driven System from Pulsed Neutron Experiment, TANINAKA HIROSHI, HASHIMOTO KENGO, PYEON CHEOL HO, SANO TADAFUMI, MISAWA TSUYOSHI, OHSAWA TAKAAKI, J Nucl Sci Technol, J Nucl Sci Technol, 47(4), 376-383 (J-STAGE) - 383, 2010 , Refereed
  • A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel, Tadafumi Sano, Toshikazu Takeda, Masatoshi Yamasaki, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46(3), 226 - 231, Mar. 2009 , Refereed
    Summary:A new uncertainty reduction method is proposed to evaluate the prediction accuracy of neutronics characteristics by combining the generalized bias factor method and the cross section adjustment method. The present method is applied to a fuel fabrication process with erbia-bearing fuel. The cross section uncertainty of erbium is improved by means of cross section adjustment using experimental data of the erbia worths. For a blending machine (H/U = 0) used in the fuel fabrication process, the uncertainty reduction, which shows the rate of reduction of uncertainty, of the k(eff) is 0.604 for the present method and 0.555 for the conventional bias factor method. Thus, the prediction uncertainties are reduced by the present method compared with by the bias factor method.
  • Progress of Criticality Experiments and Nuclear Design Studies on Erbia-Bearing Super High Burnup Fuel, Masatoshi Yamasaki, Takeshi Kuroishi, Toshikazu Takeda, Akio Yamamoto, Hironobu Unesaki, Masaaki Mori, Tadafumi Sano, Int. Congress on Advances in Nuclear Power Plants (ICAPP2009), Int. Congress on Advances in Nuclear Power Plants (ICAPP2009), 0 - 0, 2009 , Refereed
  • Improvement of Prediction Accuracy for Fuel Fabrication System with Erbia Bearing Fuel, T. Takeda, T. Sano, T. Kuroishi, M. Yamasaki, H. Unesaki, Proc. ICAPP’08、 Anaheim, Proc. ICAPP’08、 Anaheim, 8028 - 0, 2008 , Refereed
  • Calculation of Doppler reactivity worth in transient with space dependence of self-shielding in fuel pellet, Tadafumi Sano, Toshikazu Takeda, Hideaki Ikeda, Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, 41(7), 797 - 801, Jul. 30 1999 , Refereed
  • Resonance Analysis for Neutron Capture Cross Sections of Th-232, Jaehong Lee, Jun-Ichi Hori, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki, Ken Nakajima, Energy Procedia, Energy Procedia, 131, 306 - 311, 2017 , Refereed
    Summary:In recent years, a great interest has been taken in the thorium fuel cycle. The neutron capture reaction for 232Th is very important to evaluate the 233U production in the thorium fuel cycle. In the present study, we have carried out the resonance analysis of neutron capture cross sections of 232Th obtained by using the Kyoto University Research Reactor Institute - Linear Accelerator (KURRI-LINAC). We performed the resonance analysis using the code SAMMY for the 10 resolved resonances in the energy range from 20 to 210 eV. The obtained parameters for the 69.2-, 113.1-, 120.9- and 170.4-eV resonances are in disagreement with the evaluated values, whereas the parameters for other six resonances were in general agreement. In order to verify the validity for the resonance analysis, we also investigated the neutron self-shielding and multiple-scattering effects on the neutron capture cross sections obtained for 232Th samples with three different thicknesses. The correction factors were estimated by the Monte Carlo simulation using the evaluated cross sections in JENDL-4.0 and the cross section data revised by the present resonance analysis. The comparison between the capture cross sections corrected with the JENDL-4.0 is consistent with the resonance analysis results. Moreover, it was confirmed that the revised cross section data enable the correction factors to reproduce the experimental results for the 69.2- and 120.9-eV resonances. In the case of 170.4-eV resonance, the disagreement between the experimental results was not improved in this study. Therefore, further study is necessary to improve the resonance data.
  • Neutron capture cross section measurements of Eu-151,Eu-153 using a pair of C6D6 detectors, Jaehong Lee, Jun-ichi Hori, Ken Nakajima, Tadafumi Sano, Samyol Lee, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 54(10), 1046 - 1057, 2017 , Refereed
    Summary:We have measured the neutron capture cross sections of Eu-151 and Eu-153 by the time-of-flight (TOF) method in the range from 0.005eV to keV region using the Kyoto University Research Reactor Institute - Linear Accelerator (KURRI-LINAC). We employed a pair of C6D6 liquid scintillators for the prompt capture -ray measurement. The pulse-height weighting technique was employed to obtain the capture yields from the -ray spectra of Eu-151,Eu-153. The obtained thermal cross sections at 0.0253eV are 9051 683 b for Eu-151 and 364 +/- 44 b for Eu-153, respectively. The resonance integrals have been derived as 3490 +/- 162 b for Eu-151 and 1538 +/- 106 b for Eu-153.The obtained capture cross sections were compared with the previously reported experimental data and the evaluated data. The evaluated data in JENDL-4.0 and JEFF-3.2 show good agreement with the present experiment results of Eu-151, however, the evaluated data in ENDF/B-VII.1 are larger than the present experiment results of Eu-151 about 10% to 20% in the energy region from 0.03 to 0.2eV. For the neutron capture cross sections of Eu-153, the evaluated data in ENDF/B-VII.1 and Widder's data are in good agreement with the present results in the energy region below 0.35 eV.
  • Systematic effects on cross-section data derived from reaction rates at a cold neutron beam, Gasper Zerovnik, Bjoern Becker, Tamas Belgya, Christoph Genreith, Hideo Harada, Stefan Kopecky, Vladimir Radulovic, Tadafumi Sano, Peter Schillebeeckx, Andrej Trkov, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 799, 29 - 36, Nov. 2015 , Refereed
    Summary:The methodology to derive cross-section data from measurements in a cold neutron beam was studied. Mostly, capture cross-sections at thermal energy are derived relative to a standard cross-section, e.g. the cross-section of the H-1(n,gamma), N-14(n,gamma), or Au-197(n,gamma) reaction, and proportionality between the standard and the measured cross-section, evaluated at different energies in the sub-thermal region, is often assumed. Due to this assumption the derived capture cross-section at thermal energy can be biased by more than 10%. Evidently the bias depends on how much the energy dependence of the cross-section deviates from a direct proportionality with the inverse of the neutron speed. The effect is reduced in case the cross-section is not derived at thermal energy but at an energy close to the average energy of the cold neutron beam. Nevertheless, it is demonstrated that the bias can only be avoided in case the energy dependence of the cross-section is known and proper correction factors are applied. In some cases the results are also biased when the attenuation of the neutron beam within the sample is neglected in the analysis. Some of the cross-section data reported in the literature suffer from such bias effects. Hence, the results have to be corrected using the correction factors presented in this paper. (C) 2015 The Authors. Published by Elsevier B.V.
  • Concept of capture credit based on neutron-induced gamma ray spectroscopy, Yasushi Nauchi, Hirokazu Ohta, Hironobu Unesaki, Tadafumi Sano, Takahiro Yagi, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 52(7-8), 1074 - 1083, Aug. 2015 , Refereed
    Summary:Capture credit (CapC) based on neutron-induced gamma ray spectroscopy (NIGS) is proposed to confirm the subcriticality of fuel debris in which nuclear fuel and structural materials are co-melted or mixed. By NIGS, rates of some capture reactions can be measured in relation to fission reactions. By the ratio, we can credit the negative reactivity inserted by the capture reactions. The theory of CapC is described. In order to demonstrate the benefit to take CapC for storage of the fuel debris, numerical simulations are performed for a hypothetical array of canisters in which the fuel debris is stored. A procedure of CapC based on NIGS is also proposed, which consists of several technologies: (1) NIGS, (2) simulations of a response and an efficiency of the ray detection, and (3) unfolding of the ray pulse height spectrum to obtain reaction rates. Experimental studies of NIGS have been launched in Kyoto university critical assembly facility. NIGS is firstly studied for simulated fuel debris of a few kinds of mixture of stainless steel and uranium in subcritical systems. The measured ray pulse height spectra and preliminary analyses indicate that CapC based on NIGS is worth to be investigated further for the efficient storage of fuel debris.
  • Perspectives of research and development of accelerator-driven system in Kyoto University Research Reactor Institute, Cheol Ho Pyeon, Takahiro Yagi, Yoshiyuki Takahashi, Tadafumi Sano, Daisuke Ito, Yasushi Saito, Ken Nakajima, PROGRESS IN NUCLEAR ENERGY, PROGRESS IN NUCLEAR ENERGY, 82, 22 - 27, Jul. 2015 , Refereed
    Summary:The experimental studies on the accelerator-driven system (ADS) are being conducted for the basic research of nuclear transmutation analyses with the combined use of the core at the Kyoto University Critical Assembly (KUCA) and the fixed-field alternating gradient (FFAG; 100 MeV protons) accelerator, in the Kyoto University Research Reactor Institute. The ADS experiments with 100 MeV protons were carried out to investigate the neutronic characteristics of ADS, and the static and kinetic parameters were accurately analyzed through both the measurements and the Monte Carlo simulations of reactor physics parameters. An upcoming ADS at KUCA could be composed of highly-enriched uranium fueled and Pb-Bi zoned core, and the conversion analyses (Np-237 and Am-241) of nuclear transmutation could be conducted in ADS (hard spectrum core) at KUCA. Also, thermal hydraulics of liquid Pb-Bi are expected to be examined with the use of Pb-Bi test loop and test facilities for the investigation of Pb-Bi liquid characteristics from the viewpoints of single-phase heat transfer and two-phase flow. (C) 2014 Elsevier Ltd. All rights reserved.
  • Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode, Jian Zhang, Xiuzhong Shen, Yasuyuki Fujihara, Tadafumi Sano, Toshihiro Yamamoto, Ken Nakajima, Annals of Nuclear Energy, Annals of Nuclear Energy, 76, 410 - 420, Feb. 2015 , Refereed
    Summary:© 2014 Elsevier Ltd. All rights reserved. In this study, the natural circulation cooling capacity of Kyoto University Research Reactor (KUR) is experimentally investigated by measuring the inlet and outlet temperatures of the core under natural circulation operation at various thermal powers ranging from 10 kW to 100 kW and the shutdown state. In view of the uneven power distribution and the resultant inconsistent coolant outlet temperature in the core, eight measuring points located separately in the outlet of the fuel elements were chosen to investigate the distribution of the outlet temperature of the core. The natural circulation cooling capacity represented by the average natural circulation flow velocity in the core is calculated from the temperature difference between the outlet and inlet temperature of the core. The measured outlet temperature of the fuel elements shows a cross-sectional distribution agreeing with the distribution of the thermal output of the fuel elements in the core. Since the measured outlet temperatures decrease quickly in the flow direction in a small local region above the outlet of the core, the mixing of the hot water out of the core with the cold water around the core outlet is found to happen in the small region not more than 5 cm far from the core outlet. The natural circulation flow velocity in the core increases non-linearly with the thermal power. The safety of KUR has been analysed by conservatively estimating the highest coolant temperature, the highest fuel cladding temperature, the highest fuel meat temperature and the minimum DNBR under all of the normal operations with natural circulation cooling mode. The natural circulation operation at the thermal power of 100 kW is the most serious operating condition. The average natural circulation flow velocity at the thermal power of 100 kW is 3.13 cm/s. All of these estimated parameters under normal natural circulation operation meet the safety criterion of research reactor.
  • Accuracy Improvement of Neutron Nuclear Data on Minor Actinides, Hideo Harada, Osamu Iwamoto, Nobuyuki Iwamoto, Atsushi Kimura, Kazushi Terada, Taro Nakao, Shoji Nakamura, Kazuhito Mizuyama, Masayuki Igashira, Tatsuya Katabuchi, Tadafumi Sano, Yoshiyuki Takahashi, Koichi Takamiya, Cheol Ho Pyeon, Satoshi Fukutani, Toshiyuki Fujii, Jun-ichi Hori, Takahiro Yagi, Hiroshi Yashima, CGS15 - CAPTURE GAMMA-RAY SPECTROSCOPY AND RELATED TOPICS, CGS15 - CAPTURE GAMMA-RAY SPECTROSCOPY AND RELATED TOPICS, 93, 2015 , Refereed
    Summary:Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program" in Japan at October 2013. The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the team aims at improving the accuracy of the data. The background and research plan of the AIMAC project are presented.
  • Neutron Capture Cross Section Measurement on Zr-91 at J-PARC/MLF/ANNRI, Jun-ichi Hori, Hiroshi Yashima, Shoji Nakamura, Kazuyoshi Furutaka, Kaoru Y. Hara, Hideo Harada, Kentaro Hirose, Masayuki Igashira, Tatsuya Katabuchi, Atsushi Kimura, Koichi Kino, Fumito Kitatani, Yoshiaki Kiyanagi, Mitsuo Koizumi, Motoharu Mizumoto, Tadafumi Sano, Yoshiyuki Takahashi, Yosuke Toh, CGS15 - CAPTURE GAMMA-RAY SPECTROSCOPY AND RELATED TOPICS, CGS15 - CAPTURE GAMMA-RAY SPECTROSCOPY AND RELATED TOPICS, 93, 2015 , Refereed
    Summary:The neutron capture cross section measurement on Zr-91 was performed at neutron TOF beam line ANNRI installed at J-PARC/MLF. Prompt capture gamma rays from the sample were detected with an array of large Ge detectors at a distance of 21.5 m from the spallation neutron source by the time-of-fligh (TOF) method. The neutron capture gamma-ray pulse-height spectra from the 182-eV p-wave resonance and the 292-eV s-wave resonance were obtained by gating on the TOF regions, respectively. Though the decay patterns of primary transitions from the capture state were quite different between resonances, the prominent characteristics common to both resonances was the very strong ground-state transition from the 935-keV state. Therefore, a ground-state transition method was applied to obtain the capture yield, so that the background components due to impurities were successfully eliminated. The preliminary result of the neutron capture cross section for Zr-91 up to 5 keV is presented.
  • Development of nondestructive assay to fuel debris of fukushima daiichi NPP (1): Experimental validation for the application of a self-indication method, Jun-Ichi Hori, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki, Ken Nakajima, Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 21 - 29, Jan. 01 2015 , Refereed
    Summary:We have proposed a new concept of the “self-indication method” combined with neutron resonance densitometry (NRD) for nondestructive assaying of the distribution of nuclear materials in the fuel debris of Fukushima Daiichi NPP. To verify the method, we performed experiments using a 46 MeV electron linear accelerator at the Kyoto University Research Reactor Institute. First, we measured the area densities of gold foil 10, 20, 30, 40, and 50 μm thick by area analysis at the 4.9 eV resonance region. It was confirmed that the area densities of the target nuclide can be determined by conventional NRD and the self-indication method within 3 % accuracy, respectively. As the next step, we added a silver foil of 50 μm thickness to a gold foil of 10 μm thickness and measured the area density of the gold foil. It was shown that the contribution from the other nuclide (silver foil) can be remarkably suppressed by applying the self-indication method. Finally, we have demonstrated a nondestructive assay of nuclear material using a mixture composed of a natural uranium foil, sealed minor actinide samples of 237Np and 243Am. The results indicated that the self-indication method is useful for assaying a mixture of materials with high activity such as fuel debris.
  • Development of nondestructive assay of fuel debris of fukushima daiichi NPP (2): Numerical validation for the application of a self-indication method, Tadafumi Sano, Jun-Ichi Hori, Yoshiyuki Takahashi, Hironobu Unesaki, Ken Nakajima, Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 31 - 37, Jan. 01 2015 , Refereed
    Summary:To perform decommissioning of the Fukushima Daiichi NPP safely, it is very important to measure the components of the fuel debris. Therefore, a new nondestructive assay to identify and quantify the target nuclide in fuel debris using a pulsed-neutron source is under development in Kyoto University Research Reactor Institute. We use the self-indication method for the nondestructive assay. This method is a neutron transmission method. The neutron transmission method is focused on resonance reactions (i.e., capture, fission) at the target nuclide. In the self-indication method, the transmitted neutrons from the sample are injected into an indicator. The indicator consists of a high-purity target nuclide. The transmitted neutrons are obtained by the time-of-flight (TOF) technique via resonance reactions in the indicator. The self-indication method has a high signal-to-noise (S/N) ratio compared to the conventional method. In this study, numerical validation for the self-indication method to identify and quantify nuclides in a BWR-MOX pellet is described. The burn-up of the MOX pellet is 0 GWd/t, 10 GWd/t, 20 GWd/t, 30 GWd/t, 40 GWd/t, and 50 GWd/t. The 12-m measurement line in KUR-LINAC is simulated as a calculational geometry. Numerical calculations are carried out by continuous-energy Monte-Carlo code MVP2 with JENDL-4.0 as the nuclear data library. The burn-up calculations of the BWR-MOX pellet are performed by the deterministic neutronics code SARC 2006 with JENDL-4.0. Numerical validation for application of the self-indication method is carried out. From the results, it is noted that the self-indication method has a good S/N ratio compared to the neutron transmission method for quantifying the amount of target nuclides in the fuel debris.
  • Measurement of large negative reactivity of an accelerator-driven system in the Kyoto University Critical Assembly, Atsushi Sakon, Kengo Hashimoto, Muhamad Aiman Bin Maarof, Masahiro Kawasaki, Wataru Sugiyama, Cheol Ho Pyeon, Tadafumi Sano, Takahiro Yagi, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 51(1), 116 - 126, Jan. 2014 , Refereed
    Summary:Large negative reactivity of a subcritical system driven by a pulsed 14 MeV neutron source has been measured in the Kyoto University Critical Assembly. The subcriticality of the accelerator-driven system (ADS) ranged in effective multiplication factor roughly from 0.98 to 0.92, which corresponded to an operational range of an actual ADS proposed by Japan Atomic Energy Agency. As the measurement technique, pulsed neutron method, power spectral analysis for pulsed neutron source, accelerator-beam trip method were employed. From neutron count decay data obtained by the pulsed neutron experiment, not only the prompt-neutron decay constant of fundamental mode but also a higher spatial mode could be derived. The subcriticality was also determined from the fundamental decay constant. The measured cross-power spectral density consisted of a familiar correlated reactor-noise component and many uncorrelated delta-function-like peaks at the integral multiple of pulse repetition frequency. The fundamental prompt-neutron decay constant, i.e., the subcriticality determined from the latter uncorrelated peaks was consistent with that obtained by the above pulsed neutron experiment. However, the magnitude of the former correlated component was reduced with an increase in the subcriticality and eventually this component became almost white at deeply subcritical state ranging in the multiplication factor under 0.95. Consequently, the determination of the decay constant from the correlated component was impossible under such a subcritical state. As data analysis method for the beam trip experiment, both the conventional integral count method and the least-squares inverse kinetics method (LSIKM) were employed. The LSIKM analysis led to the consistent subcriticality with that obtained by the pulsed neutron experiment, while the integral count method significantly underestimated the subcriticality. This underestimation originated from a residual background count, which was maintained after the beam trip. The LSIKM was mostly not influenced by such a slight count rate.
  • Positron beam facility at Kyoto University Research Reactor, Q. Xu, K. Sato, T. Yoshiie, T. Sano, H. Kawabe, Y. Nagai, K. Nagumo, K. Inoue, T. Toyama, N. Oshima, A. Kinomura, Y. Shirai, 13TH INTERNATIONAL WORKSHOP ON SLOW POSITRON BEAM TECHNIQUES AND APPLICATIONS (SLOPOS13), 13TH INTERNATIONAL WORKSHOP ON SLOW POSITRON BEAM TECHNIQUES AND APPLICATIONS (SLOPOS13), 505, 2014 , Refereed
    Summary:A positron beam facility is presently under construction at the Kyoto University Research Reactor (KUR), which is a light-water moderated tank-type reactor operated at a rated thermal power of 5 MW. A cadmium (Cd) - tungsten (W) source similar to that used in NEPOMUC was chosen in the KUR because Cd is very efficient at producing gamma-rays when exposed to thermal neutron flux, and W is a widely used in converter and moderator materials. High-energy positrons are moderated by a W moderator with a mesh structure. Electrical lenses and a solenoid magnetic field are used to extract the moderated positrons and guide them to a platform outside of the reactor, respectively. Since Japan is an earthquake-prone country, a special attention is paid for the design of the in-pile positron source so as not to damage the reactor in the severe earthquake.
  • Power spectral analysis for a thermal subcritical reactor system driven by a pulsed 14 MeV neutron source, Atsushi Sakon, Kengo Hashimoto, Wataru Sugiyama, Hiroshi Taninaka, Cheol Ho Pyeon, Tadafumi Sano, Tsuyoshi Misawa, Hironobu Unesaki, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 50(5), 481 - 492, May 2013 , Refereed
    Summary:A series of power spectral analyses for a thermal subcritical reactor system driven by a pulsed 14 MeV neutron source was carried out at Kyoto University Critical Assembly (KUCA), to determine the prompt-neutron decay constant of the accelerator-driven system (ADS). The cross-power spectral density between time-sequence signal data of two neutron detectors was composed of a familiar continuous reactor noise component and many delta-function-like peaks at the integral multiple of pulse repetition frequency. The prompt-neutron decay constant inferred from the reactor noise component of the cross-power spectral density was consistent with that obtained by a pulsed neutron experiment. However, the reactor noise component of the auto-power spectral density of each detector was hidden by a white chamber noise in the higher-frequency range and this feature resulted in a considerable underestimation of the decay constant. For several runs with a low pulse-repetition frequency, furthermore, we attempted to infer the decay constant from point data of the delta-function-like peaks. The analysis for a run under a slightly subcritical state resulted in the consistent decay constant; however, those for other runs under significantly subcritical states underestimated the decay constant. Considering the contribution of a spatially higher mode to the point data, the above underestimation was solved to obtain the consistent decay constant. While the Feynman- formula for a pulsed neutron source is too complicated to be fitted directly to variance-to-mean ratio data, the present analysis on frequency domain is much simpler and the conventional formula based on the first-order reactor transfer function is available for fitting to power spectral density data.
  • Feynman-alpha Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14 MeV Neutron Source, Hiroshi Taninaka, Atsuko Miyoshi, Kengo Hashimoto, Cheol Ho Pyeon, Tadafumi Sano, Tsuyoshi Misawa, Wataru Sugiyama, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48(9), 1272 - 1280, Sep. 2011 , Refereed
    Summary:In a series of Feynman-alpha correlation measurements for a thermal Accelerator-Driven System (ADS) with 14 MeV neutrons at the Kyoto University Critical Assembly (KUCA), an unstable accelerator condition such as a drift of beam current has been frequently observed. Neutron source instability caused by such unavoidable beam-current instability resulted in a divergent variance-to-mean ratio and, consequently, the correlation analysis failed. Nevertheless, we attempted to apply a difference-filtering technique to the correlation analysis to reduce the influence of the above instability. The present attempt resulted in consistent prompt-neutron decay constants with those obtained in a previous pulsed neutron experiment. The application of the filtering is expected to enhance the robustness of Feynman-alpha analysis against various instabilities of accelerator operation in actual ADS.
  • Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment, Hiroshi Taninaka, Kengo Hashimoto, Cheol Ho Pyeon, Tadafumi Sano, Tsuyoshi Misawa, Hironobu Unesaki, Wataru Sugiyama, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48(6), 873 - 879, Jun. 2011 , Refereed
    Summary:An experimental technique based on an accelerator-beam trip or restart operation is proposed to determine the subcritical reactivity of an accelerator-driven system (ADS). Applying the least-squares inverse kinetics method to the data analysis, the subcriticality can be inferred from time-sequence neutron count data after these operations. A series of beam trip and restart experiments with 14 MeV neutrons were carried out in a thermal ADS of Kyoto University Critical Assembly (KUCA), to demonstrate the applicability of the proposed technique. The subcriticalities evaluated using neutron counters far from the DT target were consistent with those obtained in a previous pulsed neutron experiment. However, a counter placed close to the target significantly overestimated the subcriticality. The present technique is expected to be available for subcriritcality measurement at startup and shutdown of various ADSs.
  • Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment, Hiroshi Taninaka, Kengo Hashimoto, Cheol Ho Pyeon, Tadafumi Sano, Tsuyoshi Misawa, Hironobu Unesaki, Wataru Sugiyama, Takaaki Ohsawa, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48(6), 873 - 879, Jun. 2011 , Refereed
    Summary:An experimental technique based on an accelerator-beam trip or restart operation is proposed to determine the subcritical reactivity of an accelerator-driven system (ADS). Applying the least-squares inverse kinetics method to the data analysis, the subcriticality can be inferred from time-sequence neutron count data after these operations. A series of beam trip and restart experiments with 14 MeV neutrons were carried out in a thermal ADS of Kyoto University Critical Assembly (KUCA), to demonstrate the applicability of the proposed technique. The subcriticalities evaluated using neutron counters far from the DT target were consistent with those obtained in a previous pulsed neutron experiment. However, a counter placed close to the target significantly overestimated the subcriticality. The present technique is expected to be available for subcriritcality measurement at startup and shutdown of various ADSs.
  • Reactor physics experiment for advanced nuclear reactor system at Kyoto University Critical Assembly (KUCA), Hironobu UNESAKI, Tsuyoshi MISAWA, Cheol-Ho PYEON, Tadafumi SANO, Jae-Yong LIM, International Journal of Nuclear Safety and Simulation, International Journal of Nuclear Safety and Simulation, Vol.1、No.3, 228 - 235, 2010 , Refereed
  • A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel, Tadafumi Sano, Toshikazu Takeda, Masatoshi Yamasaki, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46(3), 226 - 231, Mar. 2009 , Refereed
    Summary:A new uncertainty reduction method is proposed to evaluate the prediction accuracy of neutronics characteristics by combining the generalized bias factor method and the cross section adjustment method. The present method is applied to a fuel fabrication process with erbia-bearing fuel. The cross section uncertainty of erbium is improved by means of cross section adjustment using experimental data of the erbia worths. For a blending machine (H/U = 0) used in the fuel fabrication process, the uncertainty reduction, which shows the rate of reduction of uncertainty, of the k(eff) is 0.604 for the present method and 0.555 for the conventional bias factor method. Thus, the prediction uncertainties are reduced by the present method compared with by the bias factor method.
  • Critical experiments in Kyoto University Critical Assembly for development of >5wt% enrichment erbia bearing super high burnup fuel, T. Endo, M. Yamasaki, T. Kuroishi, H. Unesaki, T. Sano, A. Yamamoto, American Nuclear Society - Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance 2009, American Nuclear Society - Nuclear Criticality Safety Division Topical Meeting on Realism, Robustness and the Nuclear Renaissance 2009, 536 - 545, 2009 , Refereed
  • The outline of development project on Erbia bearing super-high-burnup fuel, M. Yamasaki, T. Kuroishi, T. Takeda, A. Yamamoto, H. Unesaki, T. Sano, M. Mori, American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV, American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV, 1, 87 - 97, 2009 , Refereed
  • Evaluation of prediction error reduction for breeding ratio by bias factor method with use of experimental result on basic reaction rate ratio, Takanori Kitada, Nobuhito Nonaka, Tadafumi Sano, Toshikazu Takeda, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 45(3), 211 - 216, Mar. 2008 , Refereed
    Summary:The evaluation technique of prediction error reduction by the bias factor method is extended to the cases where the neutronic property of a target core is related to the properties in critical experiments. This extended procedure can utilize several experimental results, although the conventional procedure utilizes only one experimental result. Calculations were performed where the measured property is the reaction rate ratio of U-238 capture to Pu-239 fission (C28/F49) in FCA XXII-1 cores and the target core property is C28/F49 or breeding ratio in a breeding light water reactor (BLWR). The prediction error of the breeding ratio in BLWR is reduced from 0.57 to 0.43%, whereas the error of C28/F49 is reduced from 0.72 to 0.19%.
  • Evaluation of prediction error reduction for breeding ratio by bias factor method with use of experimental result on basic reaction rate ratio, Takanori Kitada, Nobuhito Nonaka, Tadafumi Sano, Toshikazu Takeda, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 45(3), 211 - 216, Mar. 2008 , Refereed
    Summary:The evaluation technique of prediction error reduction by the bias factor method is extended to the cases where the neutronic property of a target core is related to the properties in critical experiments. This extended procedure can utilize several experimental results, although the conventional procedure utilizes only one experimental result. Calculations were performed where the measured property is the reaction rate ratio of U-238 capture to Pu-239 fission (C28/F49) in FCA XXII-1 cores and the target core property is C28/F49 or breeding ratio in a breeding light water reactor (BLWR). The prediction error of the breeding ratio in BLWR is reduced from 0.57 to 0.43%, whereas the error of C28/F49 is reduced from 0.72 to 0.19%.
  • Generalized bias factor method for accurate prediction of neutronics characteristics, Tadafumi Sano, Toshikazu Takeda, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43(12), 1465 - 1470, Dec. 2006 , Refereed
    Summary:A generalized bias factor method is proposed to improve the prediction accuracy of neutronics characteristics of a target core. The generalized bias factor method uses conventional bias factors calculated for several critical assemblies. The weighting factors for individual bias factors are determined to minimize the variance of neutronic characteristics of the target core. Numerical calculations are performed to investigate the uncertainty reductions of neutronics characteristics for a tight-lattice core. Though the uncertainty is not remarkably reduced for k(eff), that for the reaction rate ratio of U-238 capture/Pu-239 fission is remarkably reduced: For example, the uncertainty reduction of the reaction rate ratio in the upper core is 0.871 for the present method, and 0.657 for the conventional bias factor method.
  • Generalized bias factor method for accurate prediction of neutronics characteristics, Tadafumi Sano, Toshikazu Takeda, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43(12), 1465 - 1470, Dec. 2006 , Refereed
    Summary:A generalized bias factor method is proposed to improve the prediction accuracy of neutronics characteristics of a target core. The generalized bias factor method uses conventional bias factors calculated for several critical assemblies. The weighting factors for individual bias factors are determined to minimize the variance of neutronic characteristics of the target core. Numerical calculations are performed to investigate the uncertainty reductions of neutronics characteristics for a tight-lattice core. Though the uncertainty is not remarkably reduced for k(eff), that for the reaction rate ratio of U-238 capture/Pu-239 fission is remarkably reduced: For example, the uncertainty reduction of the reaction rate ratio in the upper core is 0.871 for the present method, and 0.657 for the conventional bias factor method.
  • Rapid estimation of core-power ratio in coupled-core system by rod drop method, K Hashimoto, T Sano, H Unesaki, T Kitada, J Yamamoto, T Horiguchi, T Takeda, O Aizawa, S Shiroya, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 37(7), 565 - 571, Jul. 2000 , Refereed
    Summary:To determine rapidly the core-power ratio in a coupled-core system, a method is proposed on the basis of the control rod drop experiment. A formula of an asymmetrical two-point version was derived to deduce the core-power ratio and subcriticalities of the individual cores. It requires only a familiar measurement technique and tools for the conventional rod drop experiment to apply this formula for the purpose of obtaining these quantities. The present method was applied to the rod drop data measured in coupled-core systems, where the core-power ratio sensitively depended on the rod patterns. The validity of the proposed method was experimentally demonstrated through the comparison between the measured core-power ratios obtained by the present method and that derived from the flux distribution measurement.
  • Rapid estimation of core-power ratio in coupled-core system by rod drop method, K Hashimoto, T Sano, H Unesaki, T Kitada, J Yamamoto, T Horiguchi, T Takeda, O Aizawa, S Shiroya, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 37(7), 565 - 571, Jul. 2000 , Refereed
    Summary:To determine rapidly the core-power ratio in a coupled-core system, a method is proposed on the basis of the control rod drop experiment. A formula of an asymmetrical two-point version was derived to deduce the core-power ratio and subcriticalities of the individual cores. It requires only a familiar measurement technique and tools for the conventional rod drop experiment to apply this formula for the purpose of obtaining these quantities. The present method was applied to the rod drop data measured in coupled-core systems, where the core-power ratio sensitively depended on the rod patterns. The validity of the proposed method was experimentally demonstrated through the comparison between the measured core-power ratios obtained by the present method and that derived from the flux distribution measurement.
  • Measurement of Subcriticality of Accelerator Driven Subcritical Core by the Pulsed Neutron Method, T. Takeda, T. Yamamoto, T. Kitada, T. Okada, T. Sano, O. Aizawa, S. Shiroya, T. Misawa, H. Unesaki, K. Kobayashi, C. Ichihara, KURRI Prog. Rep. 2000, KURRI Prog. Rep. 2000, 57, 0 - 0, 2000
  • Basic Experiments on Reactor-Power Oscillation (V) -Coupling-Coefficient Measurements for C35G/20H2O/System-, K. Hashimoto, T. Takeda, O. Aizawa, T. Horiguchi, J. Yamamoto, T. Kitada, T. Yamamoto, T. Sano, S. Shiroya, H. Unesaki, M. Hayashi, KURRI Prog. Rep., KURRI Prog. Rep., 1999, 49 - 0, 2000
  • A simple analytical method for evaluation of limit-cycle oscillation amplitude in boiling water reactors, K Hashimoto, T Sano, A Hotta, T Takeda, ANNALS OF NUCLEAR ENERGY, ANNALS OF NUCLEAR ENERGY, 25(17), 1455 - 1464, Nov. 1998 , Refereed
    Summary:An analytical method to obtain the amplitude of limit-cycle in-phase oscillation in boiling water reactors is proposed, which is applicable to small-amplitude limit cycles actually observed in various stability tests. The expression of a zero-power transfer function including the limit-cycle amplitude can be derived by considering higher-order nonlinear interaction between neutron density and feedback reactivity. In a limit-cycle oscillation, the gain- and phase-margin of the open-loop transfer function, which is defined by the product of the zero-power and a feedback transfer function, must be zero. From this requirement the oscillation amplitude and resonance frequency can be determined. A numerical example indicates that the fifth-order nonlinear approximation is adequate for the evaluation of the amplitude and that the resonance frequency is only slightly dependent on the amplitude. Assuming the independence of the resonance frequency from the amplitude, a simple formula can also be derived. When a resonance frequency is obtained by linear stability analysis, the oscillation amplitude can be readily determined from the formula expressed as a function of the amplitude by a polynomial. (C) 1998 Elsevier Science Ltd. All rights reserved.

Misc

  • 原子炉燃料の健全性評価のための非破壊分析技術の開発(8)中性子源開発 II, 高橋佳之, 堀順一, 佐野忠史, 伊藤大介, 中島健, 宇根崎博信, 鬼柳善明, 日本原子力学会秋の大会予稿集(CD-ROM), 2017, ROMBUNNO.3N07,   2017 08 29 , http://jglobal.jst.go.jp/public/201702238107652741
  • TOF法を用いたKURRI‐LINACの時間依存性バックグラウンドに関する評価研究, LEE Jaehong, 堀順一, 佐野忠史, 中島健, 日本原子力学会秋の大会予稿集(CD-ROM), 2017, ROMBUNNO.1M19,   2017 08 29 , http://jglobal.jst.go.jp/public/201702253713683295
  • MA入りPu金属燃料高速炉サイクルによる革新的核廃棄物燃焼システムの開発(14)パルス中性子源を用いた金属燃料合金材のドップラ効果測定 II, 宇根崎博信, 佐野忠史, 堀順一, 高橋佳之, 中島健, 原昭浩, 坪井靖, 有江和夫, 日本原子力学会秋の大会予稿集(CD-ROM), 2017, ROMBUNNO.3G14,   2017 08 29 , http://jglobal.jst.go.jp/public/201702294835492780
  • 「もんじゅ」データを活用したマイナーアクチニド核変換の研究(15)MA核変換量の不確かさ評価, 佐野忠史, 竹田敏一, 藤村幸治, 日本原子力学会春の年会予稿集(CD-ROM), 2017, ROMBUNNO.3F04,   2017 03 09 , http://jglobal.jst.go.jp/public/201702213540686117
  • マイナーアクチニドの中性子核データ精度向上に係わる研究開発(6)京大炉ライナックを用いたTOF法による237Np中性子捕獲断面積及び全中性子断面積の測定, 堀順一, 八島浩, 佐野忠史, 高橋佳之, 原田秀郎, 日本原子力学会春の年会予稿集(CD-ROM), 2017, ROMBUNNO.3E06,   2017 03 09 , http://jglobal.jst.go.jp/public/201702233998043335
  • マイナーアクチニドの中性子核データ精度向上に係る研究開発(5)京大炉ライナックを用いた放射化法によるMAの捕獲断面積測定, 高橋佳之, 堀順一, 佐野忠史, 八島浩, 中村詔司, 原田秀郎, 日本原子力学会春の年会予稿集(CD-ROM), 2017, ROMBUNNO.3E05,   2017 03 09 , http://jglobal.jst.go.jp/public/201702236885557358
  • マイナーアクチニドの中性子核データ精度向上に係る研究開発(1)AIMACプロジェクトにおける研究成果のまとめ, 原田秀郎, 岩本修, 岩本信之, 木村敦, 寺田和司, 中尾太郎, 中村詔司, 水山一仁, 井頭政之, 片渕竜也, 佐野忠史, 芝原雄司, 高橋佳之, 高宮幸一, PYEON Cheol Ho, 福谷哲, 藤井俊行, 藤井俊行, 堀順一, 八島浩, 日本原子力学会春の年会予稿集(CD-ROM), 2017, ROMBUNNO.3E01,   2017 03 09 , http://jglobal.jst.go.jp/public/201702237779283906
  • Liガラスシンチレータを用いた電流モードによる測定と応用, 松本哲郎, 増田明彦, 原野英樹, 堀順一, 佐野忠史, 応用物理学会春季学術講演会講演予稿集(CD-ROM), 64th, ROMBUNNO.15a‐E204‐4,   2017 03 01 , http://jglobal.jst.go.jp/public/201702243126709200
  • 関西地区におけるオープンスクール活動と新規放射線教育コンテンツ, 秋吉優史, 泉佳伸, 大石佑治, 佐々木隆之, 佐野忠史, 渥美寿雄, 小田啓二, 古田雅一, 日本保健物理学会研究発表会講演要旨集, 50th, 96,   2017 , http://jglobal.jst.go.jp/public/201702247446374696
  • 時間依存モンテカルロ計算による中性子雑音を用いた軽水炉内ボイド情報の推定, 高山直毅, 山本俊弘, 佐野忠史, 堀順一, 中島健, 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2H06,   2016 08 26 , http://jglobal.jst.go.jp/public/201602215209241858
  • MA入りPu金属燃料高速炉サイクルによる革新的核廃棄物燃焼システムの開発(9)パルス中性子源を用いた金属燃料合金材のドップラ効果測定, 宇根崎博信, 佐野忠史, 堀順一, 高橋佳之, 中島健, 原昭浩, 坪井靖, 有江和夫, 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.1L22,   2016 08 26 , http://jglobal.jst.go.jp/public/201602215569530070
  • BGO検出器を用いたEu‐151,153の中性子捕獲断面積に関する測定的研究, LEE Jaehong, 堀順一, 佐野忠史, 中島健, 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.1N04,   2016 08 26 , http://jglobal.jst.go.jp/public/201602239073480734
  • 原子炉燃料の健全性評価のための非破壊分析技術の開発(5)模擬核燃料ペレットを用いたパルス中性子イメージング, 佐野忠史, 伊藤大介, 堀順一, 高橋佳之, 長谷美宏幸, 加美山隆, 中島健, 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2N02,   2016 08 26 , http://jglobal.jst.go.jp/public/201602268834464146
  • 原子炉燃料の健全性評価のための非破壊分析技術の開発(4)Self‐indication法を用いた中性子共鳴濃度分析, 堀順一, 佐野忠史, 高橋佳之, 中島健, 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2N01,   2016 08 26 , http://jglobal.jst.go.jp/public/201602279597224290
  • トリウム利用原子炉の核特性不確かさ解析, 佐野忠史, 堀順一, 高橋佳之, 宇根崎博信, 日本原子力学会春の年会予稿集(CD-ROM), 2016, ROMBUNNO.1O19,   2016 03 16 , http://jglobal.jst.go.jp/public/201602223698586732
  • Application of Cherenkov Light Observation to Reactor Measurements (2)-Design and Trial Fabrication of Cherenkov Light Estimation System-, 山本圭一, 武内伴照, 林隆康, 林隆康, 小菅史明, 小菅史明, 佐野忠史, 佐野忠史, 土谷邦彦, 日本原子力研究開発機構JAEA-Testing(Web), 2015-001, WEB ONLY,   2015 11 , 10.11484/jaea-testing-2015-001, http://jglobal.jst.go.jp/public/201502204787015497
  • Establishment of Experimental System for 99Mo/99mTc Production by Neutron Activation Method, 石田卓也, 椎名孝行, 椎名孝行, 太田朗生, 太田朗生, 木村明博, 西方香緒里, 柴田晃, 棚瀬正和, 棚瀬正和, 小林正明, 小林正明, 佐野忠史, 佐野忠史, 藤原靖幸, 藤原靖幸, 土谷邦彦, 日本原子力研究開発機構JAEA-Technology(Web), 2015-030, WEB ONLY,   2015 11 , 10.11484/jaea-technology-2015-030, http://jglobal.jst.go.jp/public/201602200627017550
  • 京大炉ライナックを用いたTh‐232の中性子捕獲断面積測定, HORI JUN'ICHI, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, UNESAKI HIRONOBU, 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.O06,   2015 08 21 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502206388807838
  • 京都大学臨界集合体実験装置の加速器駆動システムにおけるFeynman‐α相関解析, ISHII TOSHIAKI, HOHARA SHIN'YA, SUGIYAMA WATARU, HASHIMOTO KENGO, SANO TADAFUMI, PYEON CHEOL HO, OKUDA RYOHEI, SAKON ATSUSHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.A33,   2015 08 21 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502210195047787
  • TOF法を用いた中性子捕獲断面積測定に対する自己遮蔽効果の補正方法の検討, LEE JAEHONG, HORI JUN'ICHI, SANO TADAFUMI, NAKAJIMA KEN, TAKAHASHI YOSHIYUKI, YAMAMOTO TOSHIHIRO, 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.O05,   2015 08 21 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502210204252968
  • 次世代原子炉燃料の健全性評価のための非破壊分析技術の開発(2)中性子源開発, TAKAHASHI YOSHIYUKI, HORI JUN'ICHI, SANO TADAFUMI, NAKAJIMA KEN, UNESAKI HIRONOBU, KIYANAGI YOSHIAKI, 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.P50,   2015 08 21 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502211987306573
  • 「もんじゅ」データを活用したマイナーアクチニド核変換の研究―(4)感度係数計算法と新しい断面積調整法―, SANO TADAFUMI, TAKEDA TOSHIKAZU, 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.A12,   2015 08 21 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502221463177615
  • Improvement of Neutron Source for the Development of Non-destructive Methods Adapted for Integrity Test of Next Generation Nuclear Fuels at KURRI-LINAC, Y. TAKAHASHI, J. HORI, T. SANO, H. UNESAKI, K. NAKAJIMA, Y. KIYANAGI, 5th International Meeting of Union for Compact Accelerator-driven Neutron Sources,   2015 05
  • 高温ガス炉の燃焼特性と崩壊熱の評価, ISHII TOSHIAKI, OKUDA RYOHEI, SUGIYAMA WATARU, HASHIMOTO KENGO, SHIMAZAKI YOSUKE, TAKADA SHOJI, FUJIMOTO NOZOMU, SANO TADAFUMI, 日本原子力学会春の年会予稿集(CD-ROM), 2015, ROMBUNNO.J34,   2015 03 05 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502275519294573
  • 軽水炉安全対策のための高性能監視システムの開発(4)燃料から放出されるチェレンコフ光の評価, YAMAMOTO KEIICHI, TAKEUCHI TOMOAKI, OTSUKA NORIAKI, TSUCHIYA KUNIHIKO, SANO TADAFUMI, NAKAJIMA KEN, HAYASHI TAKAYASU, KOSUGE FUMIAKI, 日本原子力学会春の年会予稿集(CD-ROM), 2015, ROMBUNNO.I30,   2015 03 05 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201502286167630871
  • マイナーアクチニドの中性子核データ精度向上に係わる研究開発, HARADA HIDEO, IWAMOTO OSAMU, IWAMOTO NOBUYUKI, KIMURA ATSUSHI, TERADA KAZUSHI, NAKAO TARO, NAKAMURA SHOJI, MIZUYAMA KAZUHITO, IGASHIRA MASAYUKI, KATABUCHI TATSUYA, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, TAKAMIYA KOICHI, BEN TETSUKO, FUKUTANI SATOSHI, FUJII TOSHIYUKI, HORI JUN'ICHI, YAGI TAKAHIRO, YASHIMA HIROSHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.JS01,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402214906095388
  • マイナーアクチニドの中性子核データ精度向上に係わる研究開発(2)熱中性子捕獲断面積の高精度化(放射化法), NAKAMURA SHOJI, IWAMOTO OSAMU, IWAMOTO NOBUYUKI, KIMURA ATSUSHI, TERADA KAZUSHI, NAKAO TARO, HARADA HIDEO, MIZUYAMA KAZUHITO, IGASHIRA MASAYUKI, KATABUCHI TATSUYA, UEHARA AKIHIRO, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, TAKAMIYA KOICHI, PYEON CHEOL HO, FUKUTANI SATOSHI, FUJII TOSHIYUKI, HORI JUN'ICHI, YAGI TAKAHIRO, YASHIMA HIROSHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.N36,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402218198211866
  • マイナーアクチニドの中性子核データ精度向上に係る研究開発(8)全中性子断面積測定と組み合わせた共鳴パラメータの決定(京大炉ライナック), TAKAHASHI YOSHIYUKI, HORI JUN'ICHI, SANO TADAFUMI, YASHIMA HIROSHI, YAGI TAKAHIRO, PYEON CHEOL HO, HARADA HIDEO, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.N42,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402222315130985
  • KUCA個体減速架台の臨界性に対する新ポリエチレン減速材及び反射材の効果, SANO TADAFUMI, PYEON CHEOL HO, YAGI TAKAHIRO, TAKAHASHI YOSHIYUKI, SHIGA HIROSHI, UNESAKI HIRONOBU, MISAWA TSUYOSHI, NAKAJIMA KEN, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.L24,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402222952585066
  • マイナーアクチニドの中性子核データ精度向上に係る研究開発(3)熱中性子捕獲断面積の高精度化(可変中性子場), HORI JUN'ICHI, SANO TADAFUMI, YASHIMA HIROSHI, TAKAHASHI YOSHIYUKI, YAGI TAKAHIRO, PYEON CHEOL HO, HARADA HIDEO, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.N37,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402236697174422
  • 「もんじゅ」データを活用したマイナーアクチニド核変換の研究―(1)研究計画と炉物理手法―, TAKEDA TOSHIKAZU, HAZAMA TAIRA, KITADA TAKANORI, SANO TADAFUMI, TAKAKUWA MASAYUKI, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.L08,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402252872633988
  • マイナーアクチニドの中性子核データ精度向上に係わる研究開発(1)AIMACプロジェクトの全体計画, HARADA HIDEO, IWAMOTO OSAMU, IWAMOTO NOBUYUKI, KIMURA ATSUSHI, TERADA KAZUSHI, NAKAO TARO, NAKAMURA SHOJI, MIZUYAMA KAZUHITO, IGASHIRA MASAYUKI, KATABUCHI TATSUYA, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, TAKAMIYA KOICHI, PYEON CHEOL HO, FUKUTANI SATOSHI, FUJII TOSHIYUKI, HORI JUN'ICHI, YAGI TAKAHIRO, YASHIMA HIROSHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2014, ROMBUNNO.N35,   2014 08 22 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402293655329756
  • 近畿大学原子炉の制御棒価値測定と解析, KAWASAKI MASAHIRO, SAKON ATSUSHI, HASHIMOTO KENGO, SANO TADAFUMI, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O06,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402201773186160
  • CCDカメラによるチェレンコフ光画像を用いた原子炉熱出力評価, OTSUKA NORIAKI, YAMAMOTO KEIICHI, TAKEUCHI TOMOAKI, MATSUI YOSHINORI, TSUCHIYA KUNIHIKO, SANO TADAFUMI, NAKAJIMA KEN, HONMA RYOHEI, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.K42,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402216783069495
  • 京都大学臨界集合体の臨界炉心におけるFeynman‐α解析, OKUDA RYOHEI, SAKON ATSUSHI, KAWASAKI MASAHIRO, HASHIMOTO KENGO, SUGIYAMA WATARU, HOHARA SHIN'YA, PYEON CHEOL HO, SANO TADAFUMI, YAGI TAKAHIRO, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O05,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402229523726594
  • (n,γ)法による99Mo製造のための高密度MoO3ペレットの照射特性, NISHIKATA KAORI, KIMURA AKIHIRO, KATO YOSHIAKI, KUROSAWA MAKOTO, ISHIDA TAKUYA, TSUCHIYA KUNIHIKO, SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.K18,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402230191416209
  • JMTRにおける中性子照射場評価の現状, TAKEMOTO NORIYUKI, IMAIZUMI YUMI, KIMURA NOBUAKI, HORI JUN'ICHI, SANO TADAFUMI, NAKAJIMA KEN, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.JS05,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402235281432140
  • 中性子共鳴吸収を用いた核種定量のための非破壊分析法の開発(3)核燃料物質定量のための非破壊核種弁別型中性子イメージング手法開発に向けた基礎研究, TAKAHASHI YOSHIYUKI, HORI JUN'ICHI, SANO TADAFUMI, UNESAKI HIRONOBU, NAKAJIMA KEN, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.J58,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402248124187390
  • 未臨界体系における構造材の中性子捕獲反応のガンマ線測定による定量(3)―Ge半導体検出器による高分解能測定―, NAUCHI YASUSHI, OTA HIROKAZU, UNESAKI HIRONOBU, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O01,   2014 03 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201402277579120871
  • 近畿大学原子炉の実効増倍率に対する感度解析, SANO TADAFUMI, SAKON ATSUSHI, OSAWA TAKAAKI, HASHIMOTO KENGO, HOHARA SHIN'YA, SUGIYAMA WATARU, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J22,   2013 08 20 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201302252882317688
  • 核破砕反応中性子源駆動未臨界炉体系におけるクロスパワースペクトル測定, SAKON ATSUSHI, HASHIMOTO KENGO, SUGIYAMA WATARU, PYEON CHEOLHO, SANO TADAFUMI, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J36,   2013 08 20 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201302257375301607
  • KUCA臨界実験によるトリウム‐232評価済み断面積の積分評価, UNESAKI HIRONOBU, TAKAHASHI YOSHIYUKI, SANO TADAFUMI, HORI JUN'ICHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J55,   2013 08 20 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201302282203369263
  • 中性子共鳴吸収を用いた核種定量のための非破壊分析法の開発(2)Self‐indication法の応用に向けた予備計算, SANO TADAFUMI, HORI JUN'ICHI, TAKAHASHI YOSHIYUKI, UNESAKI HIRONOBU, NAKAJIMA KEN, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.I35,   2013 03 11 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201302216560879587
  • Development of non-destructive assay to determine nuclide density using neutron resonance absorption:(1)Experimental validation using a self-indication method, Hori Jun-ichi, Sano Tadafumi, Takahashi Yoshiyuki, Unesaki Hironobu, Nakajima Ken, Proceedings of AESJ, 2013, 0, ROMBUNNO.I34,   2013 03 11 , http://ci.nii.ac.jp/naid/130004568774
    Summary:現在、京都大学原子炉実験所においてパルス中性子源を用いた核種定量のための非破壊分析法の開発を行っている。本研究ではSelf-indication法を用いる。本手法は中性子による共鳴反応に着目し、indicatorとして測定対象核種の高純度サンプルを配置することで、測定対象核種に対し高感度の透過中性子束測定が可能となる。そこで、京大炉電子ライナックのパルス中性子源を用いて金、天然ウラン等に対する定量試験を行ったところ、従来の透過中性子法に比べ高いSN比で核種密度を定量し、定量範囲もまた拡張できることが明らかになった。
  • Quantification of capture reaction of structural material in subcritical system by gamma ray measurement:(2)gamma ray measurement for SUS304 plate loaded sub-critical core, Nauchi Yasushi, Ohta Hirokazu, Unesaki Hironobu, Misawa Tsuyoshi, Sano Tadafumi, Yagi Takahiro, Proceedings of AESJ, 2013, 0, ROMBUNNO.H07,   2013 03 11 , http://ci.nii.ac.jp/naid/130004568863
    Summary:ステンレス鋼と各燃料の混合した燃料デブリを模擬し、KUCA-C架台にU-Al合金燃料板とSUS304板を一様に装荷した未臨界炉心を構成した。これを252Cf中性子源で駆動し、発生するγ線をBGO検出器でスペクトル測定した。SUS304板装荷割合の増加に応じ、体系の未臨界度と核分裂数は減少し、一方SUS304の中性子捕獲反応割合が増加する。SUS304の捕獲反応に代表される 6-9MeVのγ線と核分裂に代表される 3-5MeVγ線との計数率比は、 SUS304板装荷割合の増加に応じて増加することを確認した。
  • Reactivity Worth Measurement for Central Fuel Loading in Kyoto University Critical Assembly, Kawasaki Masahiro, Binmaarof MuhanmadAiman, Sakon Atsushi, Hashimoto Kengo, Sugiyama Wataru, Pyeon Cheolho, Sano Tadafumi, Proceedings of AESJ, 2013, 0, ROMBUNNO.H05,   2013 03 11 , http://ci.nii.ac.jp/naid/130004568782
    Summary:京都大学臨界集合体固体減速炉心の中心架台の反応度価値を、中心架台落下実験、加速器ビームトリップ実験、炉雑音解析、パルス中性子法実験により測定した。数値計算結果は、これら測定結果をよく再現した。
  • Cross-Power Spectral Analysis of Accelerator-Driven Subcritical System:Measurement of Subcriticality 2% to 8%, Sakon Atsushi, Muhamad Aiman Bin Maarof, Hashimoto Kengo, Sugiyama Wataru, Pyeon Cheolho, Sano Tadafumi, Proceedings of AESJ, 2013, 0,   2013 03 , http://ci.nii.ac.jp/naid/130004568917
    Summary:14MeVパルス中性子源により駆動された京都大学臨界集合体の未臨界炉体系において、未臨界度を2%から8%の間で設定し、2系統の中性子検出器信号間および、加速器ビーム電流系と中性子検出器信号間のクロスパワースペクトル密度を測定した。このクロスパワースペクトル密度のゲインと位相差から算出した即発減衰定数は、パルス中性子源による結果を再現した。
  • Development of non-destructive assay to determine nuclide density using neutron resonance absorption:Numerical validation for the application (of the non-destructive assay) using a self-indication method, Sano Tadafumi, Hori Jun-ichi, Takahashi Yoshiyuki, Unesaki Hironobu, Nakajima Ken, Proceedings of AESJ, 2013, 0,   2013 , http://ci.nii.ac.jp/naid/130004568712
    Summary:現在、京都大学原子炉実験所においてパルス中性子源を用いた核種定量のための非破壊分析法の開発を行っている。本研究ではSelf-indication法を用いる。本手法は中性子による共鳴反応に着目し、indicatorとして測定対象核種の高純度サンプルを配置することで、測定対象核種に対し高感度の透過中性子束測定が可能となる。そこで、20GWd/tまで燃焼したBWRのMOX燃料ペレットを対象に、数値計算を用いてSelf-indication法の妥当性を評価した。その結果、従来の透過中性子分析法と比較すると、種々の核種の共鳴が存在していても目的核種の共鳴のみを観測できることが明らかとなり、Self-indication法の妥当性が示された。
  • Current Status and Future Works of Kyoto University Research Reactor, Tadafumi SANO, Yasuhuki FUJIHARA, Yoshiyuki TAKAHASHI, Jian ZHANG, Toshihiro YAMAMOTO, Ken NAKAJIMA, 2nd Asian Symposium on Material Testing Reactors, 0, 0,   2012 10 11
  • 未臨界体系における構造材の中性子捕獲反応のガンマ線測定による定量(1)KUCA‐C架台でのアルミニウムの中性子捕獲反応の検討, NAUCHI YASUSHI, KAMEYAMA TAKANORI, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, YAGI TAKAHIRO, 日本原子力学会秋の大会予稿集(CD-ROM), 2012, 0, ROMBUNNO.Q32,   2012 09 03 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201202213314690398
    Summary:京都大学臨界集合体実験装置でウラン-アルミニウム合金燃料板と軽水減速材、ステンレス鋼性の下部格子板からなる複数の未臨界炉心を構成し、その炉中心に252Cf中性子源を装荷し、炉外に配置したBGO検出器でγ線を測定した。集合体で発生するアルミニウムの熱中性子捕獲γ線に対する検出効率と波高応答をシミュレーション計算し、実測した波高スペクトルと対照してアルミニウムのγ線発生率を求め、その中性子捕獲反応率を導出した。同値は中性子輸送計算値とよく合致した。以上により未臨界体系における構造材の中性子捕獲反応率をγ線スペクトル測定で定量出来る見通しを得た。
  • Cross-Power Spectral Analysis between Current Meter and Neutron Detector Signals for Accelerator-Driven Subcritical Reactor System, Sakon Atsushi, Hashimoto Kengo, Sugiyama Wataru, Pyeon Cheolho, Sano Tadafumi, Misawa Tsuyoshi, Proceedings of AESJ, 2012, 0,   2012 09 , http://ci.nii.ac.jp/naid/130005051350
    Summary:14MeVパルス中性子源により駆動された京都大学臨界集合体の未臨界炉体系において、加速器ビーム電流計と中性子検出器信号間のクロスパワースペクトル密度を測定した。このパワースペクトル密度のゲインと位相差から算出した即発減衰定数は、パルス中性子実験による結果を再現した。
  • チェレンコフ光を用いた炉内監視システム開発(1)KURでのチェレンコフ光波長・照度測定, KIMURA NOBUAKI, TAKEMOTO NORIYUKI, TANIMOTO MASATAKA, TSUCHIYA KUNIHIKO, NAKAJIMA KEN, UNESAKI HIRONOBU, SANO TADAFUMI, FUJIHARA YASUYUKI, 日本原子力学会春の年会予稿集(CD-ROM), 2012, ROMBUNNO.E02,   2012 03 02 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201202238287003750
  • 「もんじゅ」における高速増殖炉の実用化のための核設計手法に関する技術開発:(8)実用炉に適合する解析値の不確かさ評価・低減システムの構築, SANO TADAFUMI, UNESAKI HIRONOBU, SHIMAZU YOICHIRO, TAKEDA TOSHIKAZU, VAN ROOIJEN W.F.G, 日本原子力学会春の年会予稿集(CD-ROM), 2012, ROMBUNNO.D36,   2012 03 02 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201202248166481456
  • 水素の熱中性子捕獲γ線スペクトル測定による未臨界集合体からの中性子漏洩数の評価(2), NAUCHI YASUSHI, KAMEYAMA TAKANORI, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, YAGI TAKAHIRO, 日本原子力学会春の年会予稿集(CD-ROM), 2012, ROMBUNNO.E39,   2012 03 02 , 10.11561/aesj.2012s.0.163.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201202281953904876
  • Neutron Flux Measurement at KUR in-core Irradiation Domain, 藤原 靖幸, 佐野 忠史, 張 倹, 京都大学原子炉実験所学術講演会報文集, 46, 0, 73, 78,   2012 01 , http://ci.nii.ac.jp/naid/40019174624
  • JENDL‐4を用いた京都大学研究用原子炉の実効増倍率に対する感度解析, SANO TADAFUMI, NAKAJIMA KEN, UNESAKI HIRONOBU, 日本原子力学会秋の大会予稿集(CD-ROM), 2011, ROMBUNNO.N32,   2011 09 02 , 10.11561/aesj.2011f.0.177.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201102208937361831
  • 平成22年度京都大学研究用原子炉の運転実績及び利用状況, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, SANO TADAFUMI, YAMAMOTO TOSHIHIRO, UNESAKI HIRONOBU, NAKAJIMA KEN, 日本原子力学会秋の大会予稿集(CD-ROM), 2011, ROMBUNNO.N29,   2011 09 02 , 10.11561/aesj.2011f.0.174.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201102230329938889
  • PGAを用いた次世代高燃焼度燃料用エルビア濃度測定法の研究(4)ウラン試料を用いたPGA実験, SANO TADAFUMI, LIM JEA-YONG, TAKAMATSU TERUHISA, SUGIMURA NAOKI, ISHIGAKI TOSHIHIRO, HIJIYA MASAYUKI, 日本原子力学会春の年会予稿集(CD-ROM), 2011, ROMBUNNO.I41,   2011 03 11 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201102237951820253
  • PGAを用いた次世代高燃焼度燃料用エルビア濃度測定法の研究(3)中性子照射場の改良, TAKAMATSU TERUHISA, SUGIMURA NAOKI, ISHIGAKI TOSHIHIRO, HIJIYA MASAYUKI, SANO TADAFUMI, LIM JEA-YONG, 日本原子力学会春の年会予稿集(CD-ROM), 2011, ROMBUNNO.I40,   2011 03 11 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201102287375760212
  • 水素の熱中性子捕獲γ線スペクトル測定による未臨界集合体からの中性子漏洩数の評価, NAUCHI YASUSHI, KAMEYAMA TAKANORI, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, YAGI TAKAHIRO, 日本原子力学会春の年会予稿集(CD-ROM), 2011, ROMBUNNO.I39,   2011 03 11 , 10.11561/aesj.2011s.0.170.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201102280007829933
  • Research on Erbia Density Measurement using PGA for Next Generation High Burnup fuel, T. Sano, J. Y. Lim, T. Takamatu, N. Sugimura, T. Ishigaki, M. Hijiya,   2011 03
  • Characteristics measurements of Kyoto University Research Reactor with low-enriched uranium core (1) Approach to critical and control rod worth measurements, 藤原 靖幸, 佐野 忠史, 張 倹, 京都大学原子炉実験所学術講演会報文集, 45, 77, 81,   2011 01 , http://ci.nii.ac.jp/naid/40017662905
  • Characteristics measurements of Kyoto University Research Reactor with low-enriched uranium core (2) Measurements of reactivity worth, 佐野 忠史, 藤原 靖幸, 張 倹, 京都大学原子炉実験所学術講演会報文集, 45, 82, 87,   2011 01 , http://ci.nii.ac.jp/naid/40017662906
  • Characteristics measurements of Kyoto University Research Reactor with low-enriched uranium core (3) Neutron flux distribution and output power calibration, 張 倹, 佐野 忠史, 藤原 靖幸, 京都大学原子炉実験所学術講演会報文集, 45, 88, 93,   2011 01 , http://ci.nii.ac.jp/naid/40017662907
  • Characteristics Measurements of Kyoto University Research Reactor with, J. Zhang, T. Sano, Y. Fujihara, Y. Takahashi, K. Oono, N. Maruyama, K. Nakajima,   2010 09
  • Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core, K. Nakajima, H. Unesaki, T. Misawa, T. Sano, Y. Takahashi, K. Oono, J. Zhang, T. Tsutiyama, A. Nakamori, A. Hasegawa, Y. Fujihara, N. Maruyama, T. Yamamoto,   2010 09
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(1)概要, NAKAJIMA KEN, UNESAKI HIRONOBU, MISAWA TSUYOSHI, SANO TADAFUMI, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, ZHANG JIAN, TSUCHIYAMA TATSUO, NAKAMORI AKIRA, HASEGAWA KIYOSHI, FUJIWARA YASUYUKI, MARUYAMA NAOYA, YAMAMOTO TOSHIHIRO, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O01,   2010 08 27 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002216526896187
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(2)臨界近接及び制御棒校正, FUJIWARA YASUYUKI, SANO TADAFUMI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, TSUCHIYAMA TATSUO, HASEGAWA KIYOSHI, NAKAMORI AKIRA, MISAWA TSUYOSHI, UNESAKI HIRONOBU, NAKAJIMA KEN, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O02,   2010 08 27 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002254728651886
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(3)各種反応度測定, SANO TADAFUMI, FUJIWARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, NAKAJIMA KEN, YAMAMOTO TOSHIHIRO, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O03,   2010 08 27 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002267387095798
  • 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(5)中性子束分布及び出力校正, ZHANG JIAN, SANO TADAFUMI, FUJIWARA YASUYUKI, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, NAKAJIMA KEN, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O05,   2010 08 27 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002292881553485
  • PGAを用いた次世代高燃焼度燃料用エルビア濃度測定法の研究(1)研究概要とモンテカルロ計算による検討, TAKAMATSU TERUHISA, SUGIMURA NAOKI, ISHIGAKI TOSHIHIRO, HIJIYA MASAYUKI, SANO TADAFUMI, LIM JAE-YONG, 日本原子力学会春の年会予稿集(CD-ROM), 2010, ROMBUNNO.G06,   2010 03 09 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002253372104749
  • PGAを用いた次世代高燃焼度燃料用エルビア濃度測定法の研究(2)京都大学原子炉実験所におけるPGA実験, SANO TADAFUMI, LIM JEA-YONG, TAKAMATSU TERUHISA, SUGIMURA NAOKI, ISHIGAKI TOSHIHIRO, HIJIYA MASAYUKI, 日本原子力学会春の年会予稿集(CD-ROM), 2010, ROMBUNNO.G07,   2010 03 09 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201002205586044218
  • Evaluation of temperature coefficient for KUR core with low enriched uranium fuel using SRAC code system, 張 倹, 佐野 忠史, 藤原 靖幸, 京都大学原子炉実験所学術講演会報文集, 44, 88, 93,   2010 01 , http://ci.nii.ac.jp/naid/40016957496
  • Investigation of fuel loading step in critical approach for a KUR low enriched uranium core using SRAC code system, 藤原 靖幸, 佐野 忠史, 張 倹, 京都大学原子炉実験所学術講演会報文集, 44, 94, 99,   2010 01 , http://ci.nii.ac.jp/naid/40016957497
  • KUR低濃縮燃料炉心の実効増倍率に対する感度解析, SANO TADAFUMI, NAKAJIMA KEN, UNESAKI HIRONOBU, 日本原子力学会秋の大会予稿集(CD-ROM), 2009, G10,   2009 08 28 , 10.11561/aesj.2009f.0.210.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902200835043518
  • KUR低濃縮燃料炉心の核特性解析, SANO TADAFUMI, NAKAJIMA KEN, UNESAKI HIRONOBU, 日本原子力学会春の年会予稿集(CD-ROM), 2009, K53,   2009 03 06 , 10.11561/aesj.2009s.0.185.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902209036997000
  • ビームトリップおよびリスタート実験における加速器駆動未臨界炉体系の未臨界度測定, TANINAKA HIROSHI, HASHIMOTO KENGO, PYEON CHEOLHO, SANO TADAFUMI, MISAWA TSUYOSHI, 日本原子力学会春の年会予稿集(CD-ROM), 2009, K48,   2009 03 06 , 10.11561/aesj.2009s.0.180.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902213471146485
  • 加速器駆動未臨界炉体系におけるファインマン‐α解析に対する階差フィルタの適用, MIYOSHI ATSUKO, TANINAKA HIROSHI, HASHIMOTO KENGO, PYEON CHEOLHO, SANO TADAFUMI, MISAWA TSUYOSHI, 日本原子力学会春の年会予稿集(CD-ROM), 2009, K50,   2009 03 06 , 10.11561/aesj.2009s.0.182.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902268474710542
  • The exploratory analysis of neutronics characteristics for KUR core loading low enriched fuel, 佐野 忠史, 藤原 靖幸, 中島 健, 京都大学原子炉実験所学術講演会報文集, 43, 78, 83,   2009 01 , http://ci.nii.ac.jp/naid/40016433437
  • KUR低濃縮燃料炉心の核特性予備解析, SANO TADAFUMI, FUJIHARA YASUYUKI, NAKAJIMA KEN, UNESAKI HIRONOBU, 京都大学原子炉実験所学術講演会報文集, 43rd, 78, 83,   2009 01 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902272797061877
  • Analysis of Neutronics Characteristics for KUR core with low enriched fuel, T. Sano, K. Nakajima, H. Unesaki,   2009
  • Am‐241蓄積による高速炉炉心核特性の不確かさ評価, NAKAMURA YUSUKE, TAKEDA TOSHIKAZU, SANO TADAFUMI, 日本原子力学会春の年会予稿集(CD-ROM), 2008, L10,   2008 03 11 , 10.11561/aesj.2008s.0.178.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902237392449479
  • エルビア入り次世代高燃度焼燃料の研究開発(10)改良GB因子法の粉末調整工程への応用, SANO TADAFUMI, TAKEDA TOSHIKAZU, KITADA TAKANORI, YAMASAKI MASATOSHI, 日本原子力学会秋の大会予稿集(CD-ROM), 2007, M26,   2007 09 07 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902272659426368
  • エルビア入り次世代高燃焼燃料の研究開発(6)一般化バイアス因子(GB)法の改良, TAKEDA TOSHIKAZU, SANO TADAFUMI, KITADA TAKANORI, YAMASAKI MASATOSHI, 日本原子力学会春の年会要旨集(CD-ROM), 2007, E40,   2007 03 06 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902268819366629
  • FCAドップラー反応度に対する感度解析, TAKEDA TOSHIKAZU, NAITO KEITA, SANO TADAFUMI, ANDO MASAKI, 日本原子力学会秋の大会予稿集(CD-ROM), 2006, O36,   2006 08 17 , 10.11561/aesj.2006f.0.162.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902256960871622
  • 種々の臨界実験データを用いた核特性予測誤差の低減, SANO TADAFUMI, TAKEDA TOSHIKAZU, 日本原子力学会秋の大会予稿集(CD-ROM), 2005, E68,   2005 08 12 , 10.11561/aesj.2005f.0.128.0, http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902238916897721
  • モンテカルロ燃焼計算における計算誤差伝播, SANO TADAFUMI, TAKEDA TOSHIKAZU, 日本原子力学会春の年会要旨集, 41st, 399,   2003 03 05 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902207430206147
  • 制御棒落下法による二分割炉心出力非対称度の測定, HASHIMOTO KENGO, SANO TADAFUMI, UNESAKI HIRONOBU, KITADA TAKANORI, YAMAMOTO JUNJI, HORIGUCHI TETSUO, TAKEDA TOSHIKAZU, AIZAWA OTSUHIKO, SHIROYA SEIJI, 日本原子力学会秋の大会予稿集, 1999, 277,   1999 08 10 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902172276579913
  • Analysis of Doppler Reactivity in Transient with Space Dependence of Selfshielding., SANO TADAFUMI, TAKEDA TOSHIKAZU, SAJI ETSURO, IKEDA HIDEAKI, KOSAKA SHIN'YA, 日本原子力学会春の年会要旨集, 36th, 265,   1998 03 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=200902157356700536
  • Neutron capture cross section measurements of 151,153Eu using a pair of C6D6 detectors, LEE Jaehong, HORI Jun‐ichi, NAKAJIMA Ken, SANO Tadafumi, LEE Samyol, Journal of Nuclear Science and Technology, 54, 9-10, 1046‐1057,   2017 09 , http://jglobal.jst.go.jp/public/201702291330523427
  • Uncertainty analysis of minor actinides transmutation in fast reactor cores, Toshikazu Takeda, Koji Fujimura, Tadafumi Sano, Basma Fouad, ANNALS OF NUCLEAR ENERGY, 101, 591, 599,   2017 03 , 10.1016/j.anucene.2016.11.013, http://jglobal.jst.go.jp/public/201702233681126998
    Summary:The uncertainty of minor actinides transmutation in fast reactors has been estimated for individual nuclides of minor actinides (MA). The burn-up dependent sensitivities of MA number densities are calculated using the generalized perturbation theory, and a method is derived to transform the sensitivities to the sensitivities of minor actinides transmutation. The sensitivities are used to obtain the uncertainties of minor actinides transmutation together with the cross-section covariance data of JENDL-4. The method is applied to the two MA transmutation fast reactor cores with MA content of 6% and 11%. It is seen that the uncertainties of the total MA transmutation amounts are about 3% and 4% for the two cores because the uncertainties of Np-237 and Am-241 transmutations which mainly contribute the total transmutation are small (about 3%). The contribution to the uncertainties is mainly caused by the Np-237 and Am-241 capture cross sections. The transmutation uncertainties for Np-239, Am-233, Cm-243, and Cm-245 are rather large. However the transmutation amounts of these nuclides are very small, and the large uncertainties are not the problem in practice. However, it is found that the transmutation amount of Cm-244 has large uncertainties of 10% and 13% for the cores with MA content of 6% and 11%, and this large uncertainties have to be considered when MA fuels are fabricated and reprocessed because Cm-244 produces large decay heat and neutron emission. (C) 2016 Elsevier Ltd. All rights reserved.
  • Evaluation of Neutron Spectrum at KURRI-LINAC for Nuclear Data Measurement, TAKAYAMA Naoki, OKAZAKI Souichiro, HORI Jun‐ichi, SANO Tadafumi, NAKAJIMA Ken, 日本原子力研究開発機構JAEA-Conf(Web), 2016-004, 177‐181 (WEB ONLY),   2016 09 , http://jglobal.jst.go.jp/public/201602230633190594
  • Isotopic analysis of americium by thermal ionization mass spectrometry, SHIBAHARA Yuji, TAKAMIYA Koichi, FUJII Toshiyuki, FUKUTANI Satoshi, SANO Tadafumi, HORI Jun‐ichi, HARADA Hideo, 日本原子力研究開発機構JAEA-Conf(Web), 2016-004, 15‐20 (WEB ONLY),   2016 09 , http://jglobal.jst.go.jp/public/201602290821318651
  • Re-analysis of MAs reaction rate ratio measurement in the KUCA, SANO Tadafumi, HORI Jun‐ichi, TAKAHASHI Yoshiyuki, SHIBAHARA Yuji, YASHIMA Hiroshi, TAKAMIYA Koichi, PYEON Cheol Ho, HARADA Hideo, 日本原子力研究開発機構JAEA-Conf(Web), 2016-004, 33 (WEB ONLY),   2016 09 , http://jglobal.jst.go.jp/public/201602281540240857
  • Prediction Calculation of Criticality at KUCA Solid Moderator Core for Integral Validation of MA nuclear data, SANO Tadafumi, YAGI Takahiro, HORI Jun‐ichi, TAKAHASHI Yoshiyuki, YASHIMA Hiroshi, TAKAMIYA Koichi, PYEON Cheol Ho, HARADA Hideo, 日本原子力研究開発機構JAEA-Conf(Web), 2015-003, 50 (WEB ONLY),   2016 03 , http://jglobal.jst.go.jp/public/201602226503576800
  • Investigation of Variable Neutron Field for Accurate Determination of Thermal Neutron Capture Cross Section at KURRI-LINAC, YAGI Takahiro, HORI Jun‐ichi, SANO Tadafumi, YASHIMA Hiroshi, TAKAHASHI Yoshiyuki, PYEON Cheol Ho, HARADA Hideo, 日本原子力研究開発機構JAEA-Conf(Web), 2015-003, 35 (WEB ONLY),   2016 03 , http://jglobal.jst.go.jp/public/201602296876605603
  • Neutronic Analysis for Utilization of Low Enriched Uranium Fuel At Light Water Moderated / Reflected Core of Kyoto University Critical Assembly (KUCA), H. Unesaki, T. Misawa, C. Pyeon, T. Sano, Y. Takahashi, K. Nakajima, 34th International Meeting on Reduced Enrichment for Research And Test Reactors (RERTR),   2012 10 , Refereed
  • Sensitivity Analysis of Kyoto University Research Reactor Using JENDL-4.0, T. Sano, K. Nakajima, H. Unesaki, 2011 Symposium on Nuclear Data,   2011 11
  • On the Feasibility Study for Utilization of Low Enrichment Uranium Fuel at Kyoto University Assembly (KUCA), H. Unesaki, T. Misawa, T. Sano, K. Nakajima, J. Roglans-Ribas, RERTR 2011 — 33rd INTERNATIONAL MEETING ON REDUCED ENRICHMENT FOR RESEARCH AND TEST REACTORS, 0, 0,   2011 10 23
  • Experimental Investigation of Power Spectral Analysis for Periodic and Pulsed Neutron Source, A. Sakon, K. Hashimoto, C. H. Pyeon, T. Sano, T. Misawa, H. Unesaki, W. Sugiyama, T. Osawa, Proc. 2nd Int. Conf. Physics & Technol. of Reactors & Applications (PHYTRA-2),   2011 09 , Refereed
  • CALCULATED RESULTS OF KUCA CRITICALITY EXPERIMENTS FOR ER-SHB FUEL BY USING SCALE CODE SYSTEM, T. Kuroishi, M. Yamasaki, H. Unesaki, T. Sano, A. Yamamoto, International Conference on Criticality Safety 2011, 0, 0,   2011
  • Preliminary Experimental Results of Erbia Density Measurement Using PGAA for Uranium Fuel, T.TAKAMATSU, N. SUGIMURA, T. SANO, Proc. of ANS 2010 Winter Meeting, Riviera Hotel, Las Vegas, Nevada, USA, November 7-11, 2010[CD-ROM],   2010 10 , Refereed
  • A New Uncertainty Reduction Method for Fuel Fabrication Process and PWR Cores with Erbia-Bearing Fuel, T. Sano, Proc. IAEA TM on Advanced Fuel Pellet Materials and Fuel Rod Designs for Water Cooled ReactorsPSI, 5, 0,   2009 11 23 , 10.3327/jnst.46.226
  • The Outline of Development Project on Erbia Bearing Super-High Burnup Fuel, Masatoshi Yamasaki, Takeshi Kuroishi, Toshikazu Takeda, Akio Yamamoto, Hironobu Unesaki, Tadafumi Sano, Masaaki Mori, Advances in Nuclear Fuel Management IV (ANFM 2009), 0, 0,   2009
  • A new uncertainty reduction method for PWR cores with erbia bearing fuel, T. Takeda, T. Sano, T. Kitada, T. Kuroishi, M. Yamasaki, H. Unesaki, International Conference on the Physics of Reactors 2008, PHYSOR 08, 2, 1290, 1297,   2008 , Refereed
  • Transient analysis of u02 and mox-fueled cores based on microscopic reactor physics, T. Takeda, H. Tagawa, T. Sano, International Conference on Nuclear Engineering, Proceedings, ICONE, 1, 805, 812,   2008 , Refereed, 10.1115/ICONE16-48344

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