研究者詳細 - 山本　章夫

論文 - 山本　章夫

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Estimation of Modeling Approximation Error of Core Analysis Using the Surrogate Model with Kriging 査読有り

Tomomi Hanai,Tomohiro Endo,Yasuhiro Kodama,Yasunori Ohoka,Akio Yamamoto

Trans. Am. Nucl. Soc. 117 巻頁： 1269-1272 2017年

Application of the Bias Factor Method Using the Random Sampling Technique for Prediction Accuracy Improvement of Neutronics Parameters of BWR 査読有り

Motohiro Ito,Tomohiro Endo,Akio Yamamoto,Yusuke Kuroda,Takashi Yoshii

Trans. Am. Nucl. Soc. 117 巻頁： 804-807 2017年

Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method 査読有り

A. Yamamoto,A. Giho,T. Endo

Nucl. Eng. Technol. 49 巻頁： 1143-1156 2017年

Automated Generation of Burnup Chain for Reactor Analysis Applications 査読有り

V. P. Tran,H. N. Tran,A. Yamamoto,T. Endo

Kerntechnik 82 巻頁： 196-205 2017年

A Coupling Model for the Two-stage Core Calculation Method with Subchannel Analysis for Boiling Water Reactors 査読有り

T. Mitsuyasu, M. Aoyama, A. Yamamoto

Ann. Nucl. Energy 102 巻頁： 77-84 2017年

Estimation of Sensitivity Coefficients of Core Characteristics based on Reduced-order Modeling using Sensitivity Matrix of Assembly Characteristics 査読有り

R. Katano,T. Endo,A. Yamamoto,M. Abdo,H. Abdel-Khalik

J. Nucl. Sci. Technol. 54 巻頁： 637-647 2017年

An efficient execution of Monte Carlo simulation based on delta-tracking method using GPUs

Okubo, T; Endo, T; Yamamoto, A

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 54 巻 ( 1 ) 頁： 30 - 38 2017年

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：Journal of Nuclear Science and Technology

An efficient execution method for Monte Carlo simulation using graphic processing unit (GPU) is proposed. The delta-tracking method is used since the delta-tracking method can reduce conditional branches and complexity of code implementation, which degrade computational performance on GPUs. In order to improve parallel efficiency in the eigenvalue calculation, generated fission neutrons are recorded using the atomic operation which avoids the data race in GPUs. We also propose a method to efficiently tally neutron flux in a region. The present method is based on the atomic operation and use of fixed-point type number instead of common floating-point type number. The verification calculations using the C5G7 benchmark problem show effectiveness of the proposed numerical algorithms on GPUs through comparison with calculations using central processing units.

DOI： 10.1080/00223131.2016.1202793

Web of Science

Scopus

Estimation of sensitivity coefficients of core characteristics based on reduced-order modeling using sensitivity matrix of assembly characteristics

Katano Ryota, Endo Tomohiro, Yamamoto Akio, Abdo Mohammad, Abdel-Khalik Hany

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 54 巻 ( 6 ) 頁： 637-647 2017年

Uncertainty quantification of activation due to cross section data in neutron shielding calculation

Yoko K., Endo T., Yamamoto A., Mizuno R., Kimura Y.

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings

Quantification of activation in structure materials around a nuclear reactor using results of neutron shielding calculations is necessary for efficient planning of decommissioning. In this study, the random sampling method is applied to the neutron shielding calculation in order to estimate uncertainties of neutron flux and activation of 59Co in structure materials due to cross section covariance. The calculation results indicate that the magnitude of uncertainty of activation of 59Co due to cross section data is approximately 15∼30% inside structure materials.

Scopus

Evaluation of the n/γ discrimination performance of the neutron detector with eu doped TRUST-LiCaAlF6

Maeno K., Endo T., Yamamoto A.

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年

The n/γ discrimination performance of the prototype neutron detector using Eu doped TRUST-LiCaAlF6 is quantitatively investigated, in order to confirm its applicability to the subcriticality monitoring in the decommissioning works at Fukushima Daiichi Nuclear Power Plant units 1-3, especially focusing on removal of fuel debris. In this paper, the experimental results of pulse-height distribution measurement using 252Cf at the Nagoya University Cobalt 60 irradiation facility are shown. Additionally, in order to investigate the applicability to the reactor noise analysis, preliminary experimental results of the Feynman-α method are also shown.

Scopus

Application of the genesis code to the Kobayashi 3D benchmark problem

Yamamoto A., Giho A., Endo T.

Transactions of the American Nuclear Society 117 巻頁： 1403 - 1406 2017年

Development of dynamic probabilistic risk assessment model for PWR using simplified plant simulation method

Otsuki S., Endo T., Yamamoto A.

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年

The CMMC (Continuous Markov Monte Carlo) coupling method is proposed for quantifying accident scenarios that have time-dependence in accident progression and inter-dependence of individual events. In order to analyze large number of samples within realistic computing time, we developed a simplified accident progression analysis model and coupled the simplified model to the CMMC method. Large number of samples for station black out in PWR were analyzed using the random sampling method based on the CMMC method considering uncertainty of decay heat from a core. As a result, uncertainties of event initiation time and FPs release ratio to the atmosphere are estimated.

Scopus

Effective use of engineering reactor simulator for education of nuclear safety

Yamamoto A., Endo T.

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年

Effective use of a reactor simulator to lecture nuclear safety for undergraduate/master's course students majoring nuclear engineering is discussed. Various scenarios from normal operating to severe accident conditions are used for an exercise of a few days' course. Through discussions on plant behaviors of various scenarios within a small group and among class members, participants can understand physics behind responses of a nuclear power plant.

Scopus

Estimation of modeling approximation error of core analysis using the surrogate model with kriging

Hanai T., Endo T., Kodama Y., Ohoka Y., Yamamoto A.

Transactions of the American Nuclear Society 117 巻頁： 1269 - 1272 2017年

GENESIS - a Transport Solver in Three-Dimensional Heterogeneous Geometry based on the Leaf Method 査読有り

A. Yamamoto,A. Giho,Y. Kato,T. Endo

Proc. PHYSOR2016 2016年4月

Statistical Error Estimation of the Feynman-α Method using the Bootstrap Method 査読有り

T. Endo,A. Yamamoto,T. Yagi,C. H. Pyeon

J. Nucl. Sci. Technol. 53 巻頁： 1447-1453 2016年

Discontinuity Factors for Simplified P3 Theory 査読有り

A. Yamamoto,T. Sakamoto,T. Endo

Nucl. Sci. Eng. 183 巻頁： 39-51 2016年

Bias Factor Method Using Random Sampling Technique 査読有り

T. Endo,A. Yamamoto,T. Watanabe

J. Nucl. Sci. Technol. 53 巻頁： 1491-1501 2016年

Cross Section Adjustment Methods based on Minimum Variance Unbiased Estimation 査読有り

K. Yokoyama,A. Yamamoto

J. Nucl. Sci. Technol. 53 巻頁： 1622-1638 2016年

An efficient execution of Monte Carlo simulation based on delta-tracking method using GPUs 査読有り

T. Okubo,A. Yamamoto,E. Endo

J. Nucl. Sci. Technol. 53 巻頁： 1-9 2016年

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