Faculty Profiles - YAMAMOTO, Akio

Papers - YAMAMOTO, Akio

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Recent developments in the GENESIS code based on the Legendre polynomial expansion of angular flux method Reviewed

A. Yamamoto,A. Giho,T. Endo

Nucl. Eng. Technol. Vol. 49 page： 1143-1156 2017

Automated Generation of Burnup Chain for Reactor Analysis Applications Reviewed

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

Kerntechnik Vol. 82 page： 196-205 2017

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

T. Mitsuyasu, M. Aoyama, A. Yamamoto

Ann. Nucl. Energy Vol. 102 page： 77-84 2017

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 Vol. 54 ( 6 ) page： 637-647 2017

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

Okubo Takuya, Endo Tomohiro, Yamamoto Akio

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY Vol. 54 ( 1 ) page： 30 - 38 2017

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

Language：Japanese Publishing type：Research paper (scientific journal) Publisher：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

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

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 Vol. 117 page： 1269 - 1272 2017

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

Yamamoto A., Giho A., Endo T.

Transactions of the American Nuclear Society Vol. 117 page： 1403 - 1406 2017

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

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

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

GENESIS - a Transport Solver in Three-Dimensional Heterogeneous Geometry based on the Leaf Method Reviewed

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

Proc. PHYSOR2016 2016.4

Statistical Error Estimation of the Feynman-α Method using the Bootstrap Method Reviewed

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

J. Nucl. Sci. Technol. Vol. 53 page： 1447-1453 2016

Discontinuity Factors for Simplified P3 Theory Reviewed

A. Yamamoto,T. Sakamoto,T. Endo

Nucl. Sci. Eng. Vol. 183 page： 39-51 2016

Bias Factor Method Using Random Sampling Technique Reviewed

T. Endo,A. Yamamoto,T. Watanabe

J. Nucl. Sci. Technol. Vol. 53 page： 1491-1501 2016

Cross Section Adjustment Methods based on Minimum Variance Unbiased Estimation Reviewed

K. Yokoyama,A. Yamamoto

J. Nucl. Sci. Technol. Vol. 53 page： 1622-1638 2016

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

T. Okubo,A. Yamamoto,E. Endo

J. Nucl. Sci. Technol. Vol. 53 page： 1-9 2016

Reduction of MOC Discretization Errors Through a Minimization of Source Ratio Variances Reviewed

M. Tabuchi,A. Yamamoto,E. Endo,M. Tatsumi

J. Nucl. Sci. Technol. Vol. 53 page： 1858-1869 2016

A CMFD Acceleration Method for SP3 Advanced Nodal Method Reviewed

A. Yamamoto,T. Sakamoto,T. Endo

Nucl. Sci. Eng. Vol. 184 page： 168-173 2016

Uncertainty Quantification of Spatial Correction Factor for Sjöstrand Method due to Cross-Section Data Reviewed

T. Kimura,T. Endo,A. Yamamoto

Trans. Am. Nucl. Soc. Vol. 115 page： 1081-1084 2016

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Papers - YAMAMOTO, Akio