論文 - 山本 章夫
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Application of Data Assimilation based on Bayesian Theory to Subcriticality Measurements using Area Ratio Method 査読有り
K. Maeno,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 113 巻 頁: 1282-1286 2015年11月
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Theoretical Expression of Area Ratio Method Using Detected-Neutron Multiplication Factor 査読有り
T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 113 巻 頁: 1208-1211 2015年11月
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Application of Partially-Converged Solution of Assembly Calculation for Core Sensitivity Analysis based on Reduced Order Modeling 査読有り
R. Katano,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 113 巻 頁: 1161-1164 2015年11月
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Underestimation of Statistical Uncertainty of Monte Carlo Method with Non-Analog of Fission Source Sampling 査読有り
H. Hayashi,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 113 巻 頁: 1153-1157 2015年11月
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Uncertainty Estimation of Analysis Model using the Data Assimilation Method 査読有り
K. Kinoshita,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 113 巻 頁: 1141-1143 2015年11月
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Discontinuity Factors for Simplified P3 Theory 査読有り
A.Yamamoto,T. Sakamoto,T. Endo
Proc. Reactor Physics Asia 2015 (RPHA15),Sep. 17-18, Jeju, Korea 2015年9月
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Reactor Physics Activities in Nagoya University 査読有り
A. Yamamoto,T. Endo
Proc. Reactor Physics Asia 2015 (RPHA15), Sep. 17-18, Jeju, Korea 2015年9月
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Development of New Statistical Geometry Model using the Delta-tracking Method 査読有り
T. Koide,T. Endo,A. Yamamoto
Proc. Reactor Physics Asia 2015 (RPHA15), Sep. 17-18, Jeju, Korea 2015年9月
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Angular Dependent Transmission Probability Method for Fast Reactor Core Transport Analysis 査読有り
A. Yamamoto,K. Kirimura,Y. Kamiyama,K. Yamaji,S. Kosaka,H. Matsumoto
Trans. Am. Nucl. Soc. 112 巻 頁: 736-738 2015年6月
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Development of MHI FBR Nuclear Design Code System CALAXY-H/ENSEMBLE-TRIZ 査読有り
K. Kirimura,Y. Kamiyama,K. Yamaji,S. Kosaka,H. Matsumoto,A. Yamamoto
Trans. Am. Nucl. Soc. 112 巻 頁: 733-735 2015年6月
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Development of Core Sensitivity Analysis Based on Reduced-Order Modeling using Assembly Calculations 査読有り
R. Katano,A. Yamamoto,T. Endo
Trans. Am. Nucl. Soc. 112 巻 頁: 715-718 2015年6月
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Efficient Execution of Monte Carlo Simulation Based on Pseudo-Scattering using GPU 査読有り
T. Okubo,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 112 巻 頁: 652-656 2015年6月
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Application of correction technique using leakage index combined with SPH or discontinuity factors for energy collapsing on pin-by-pin BWR core analysis 査読有り
T. Fujita,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. 52 巻 頁: 355-370 2015年3月
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Uncertainty Quantification of LWR Core Characteristics using Random Sampling Method 査読有り
A. Yamamoto,K. Kinoshita,T. Watanabe,E. Endo,Y. Kodama,T. Ohoka, T. Ushio, H. Nagano
Nucl. Sci. Eng. 181 巻 頁: 160-174 2015年
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Integration of equivalence theory and ultra-fine-group slowing-down calculation for resonance self-shielding treatment in lattice physics code GALAXY 査読有り
H. Koike,K. Yamaji,K. Kirimura,S. Kosaka,H. Matsumoto,A. Yamamoto
J. Nucl. Sci. Technol. 52 巻 頁: 842-869 2015年
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Confidence interval estimation by bootstrap method for uncertainty quantification using random sampling method 査読有り
T. Endo,T. Watanabe,A. Yamamoto
J. Nucl. Sci. Technol. 52 巻 頁: 993-999 2015年
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Statistical Error Estimation Using Bootstrap Method for the Feynman-alpha Method 査読有り
T. Endo,T. Shozawa,A. Yamamoto,C. H. Pyeon,T. Yagi
Trans. Am. Nucl. Soc. 111 巻 頁: 1204-1207 2014年11月
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Development of Overall Safety Evaluation Method for Operating Nuclear Power Plant Considering Aging Effects -Concept and Framework- 査読有り
A. Yamamoto,T. Takata,K. Demachi,N. Sugiyama,A. Yamaguchi, H. Miyano
Proc. ICMST-Kobe 2014 2014年11月
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Development of Overall Safety Evaluation Method for Operating Nuclear Power Plant Considering Aging Effects - New Risk Indicators for Maintenance Procedure- 査読有り
T. Takata,A. Yamaguchi,A. Yamamoto,K. Demachi,N. Sugiyama,H. Miyano
Proc. ICMST-Kobe 2014 2014年11月
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Comparison of Spatial Source Expansion Methods in the Three Dimensional Transport Method LEAF 査読有り
Y. Kato,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. 111 巻 頁: 1405-1408 2014年11月