Papers - YAMAMOTO, Akio
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Development of MHI FBR Nuclear Design Code System CALAXY-H/ENSEMBLE-TRIZ Reviewed
K. Kirimura,Y. Kamiyama,K. Yamaji,S. Kosaka,H. Matsumoto,A. Yamamoto
Trans. Am. Nucl. Soc. Vol. 112 page： 733-735 2015.6
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Development of Core Sensitivity Analysis Based on Reduced-Order Modeling using Assembly Calculations Reviewed
R. Katano,A. Yamamoto,T. Endo
Trans. Am. Nucl. Soc. Vol. 112 page： 715-718 2015.6
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Efficient Execution of Monte Carlo Simulation Based on Pseudo-Scattering using GPU Reviewed
T. Okubo,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. Vol. 112 page： 652-656 2015.6
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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 Reviewed Open Access
T. Fujita,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. Vol. 52 page： 355-370 2015.3
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Uncertainty Quantification of LWR Core Characteristics using Random Sampling Method Reviewed
A. Yamamoto,K. Kinoshita,T. Watanabe,E. Endo,Y. Kodama,T. Ohoka, T. Ushio, H. Nagano
Nucl. Sci. Eng. Vol. 181 page： 160-174 2015
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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 Reviewed
H. Koike,K. Yamaji,K. Kirimura,S. Kosaka,H. Matsumoto,A. Yamamoto
J. Nucl. Sci. Technol. Vol. 52 page： 842-869 2015
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Confidence interval estimation by bootstrap method for uncertainty quantification using random sampling method Reviewed
T. Endo,T. Watanabe,A. Yamamoto
J. Nucl. Sci. Technol. Vol. 52 page： 993-999 2015
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Statistical Error Estimation Using Bootstrap Method for the Feynman-alpha Method Reviewed
T. Endo,T. Shozawa,A. Yamamoto,C. H. Pyeon,T. Yagi
Trans. Am. Nucl. Soc. Vol. 111 page： 1204-1207 2014.11
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Development of Overall Safety Evaluation Method for Operating Nuclear Power Plant Considering Aging Effects -Concept and Framework- Reviewed
A. Yamamoto,T. Takata,K. Demachi,N. Sugiyama,A. Yamaguchi, H. Miyano
Proc. ICMST-Kobe 2014 2014.11
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Development of Overall Safety Evaluation Method for Operating Nuclear Power Plant Considering Aging Effects - New Risk Indicators for Maintenance Procedure- Reviewed
T. Takata,A. Yamaguchi,A. Yamamoto,K. Demachi,N. Sugiyama,H. Miyano
Proc. ICMST-Kobe 2014 2014.11
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Comparison of Spatial Source Expansion Methods in the Three Dimensional Transport Method LEAF Reviewed
Y. Kato,T. Endo,A. Yamamoto
Trans. Am. Nucl. Soc. Vol. 111 page： 1405-1408 2014.11
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Estimation of Sensitivity Coefficient using Random Sampling and L1-norm Minimization Reviewed
T. Watanabe,T. Endo,A. Yamamoto,Y. Kodama,T. Ohoka,T. Ushio
Trans. Am. Nucl. Soc. Vol. 111 page： 1391-1394 2014.11
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Confidence Interval Estimation by Bootstrap Method for Uncertainty Quantification using Random Sampling Reviewed
T. Endo,T. Watanabe,A. Yamamoto
Proc. PHYSOR2014 2014.9
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Impact of Nearest Neighbor Distribution of Fuel Particle on Neutronics Characteristics in Statistical Geometry Model Reviewed
T. KoideT. Endo,A. Yamamoto,K. Kirimura,K. Yamaji
Proc. PHYSOR2014 2014.9
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Theoretical Prediction on Underestimation of Statistical Uncertainty for Fission Rate Tally in Monte Carlo Calculation Reviewed
T. Endo.A. Yamamoto,K. Sakata
Proc. PHYSOR2014 2014.9
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Development of Legendre expansion of Angular Flux Method For 3D MOC Calculation Reviewed
Y. Kato,A. Yamamoto,T. Endo
Proc. PHYSOR2014 2014.9
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Improvement of a Convergence Technique for MOC Calculation with Large Negative Self-Scattering Cross Section Reviewed
M. Tabuchi,M. Tatsumi,A. Yamamoto,T. Endo
Proc. PHYSOR2014 2014.9
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Generation of Simplified Burnup Chain using Contribution Matrix of Nuclide Production Reviewed
R. Katano,A. Yamamoto,T. Endo,Y. Kamiyama,K. Kirimura,S. Kosaka
Proc. PHYSOR2014 2014.9
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Uncertainty Quantification of Neutronics Characteristics using Latin Hypercube Sampling Method Reviewed
K. Kinoshita,A. Yamamoto,T. Endo,Y. Kodama,Y. Ohoka,T. Ushio, H. Nagano
Proc. PHYSOR2014 2014.9
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Applicability of the Cross Section Adjustment Method based on Random Sampling Technique For Burnup Reviewed
T. Watanabe,T. Endo,A. Yamamoto,Y. Kodama,Y. Ohoka,T. Ushio,
Proc. PHYSOR2014 2014.9