論文 - 山本 章夫
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Estimation of Sensitivity Coefficient using Random Sampling and L1-norm Minimization 査読有り
T. Watanabe,T. Endo,A. Yamamoto,Y. Kodama,T. Ohoka,T. Ushio
Trans. Am. Nucl. Soc. 111 巻 頁： 1391-1394 2014年11月
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Confidence Interval Estimation by Bootstrap Method for Uncertainty Quantification using Random Sampling 査読有り
T. Endo,T. Watanabe,A. Yamamoto
Proc. PHYSOR2014 2014年9月
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Impact of Nearest Neighbor Distribution of Fuel Particle on Neutronics Characteristics in Statistical Geometry Model 査読有り
T. KoideT. Endo,A. Yamamoto,K. Kirimura,K. Yamaji
Proc. PHYSOR2014 2014年9月
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Theoretical Prediction on Underestimation of Statistical Uncertainty for Fission Rate Tally in Monte Carlo Calculation 査読有り
T. Endo.A. Yamamoto,K. Sakata
Proc. PHYSOR2014 2014年9月
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Development of Legendre expansion of Angular Flux Method For 3D MOC Calculation 査読有り
Y. Kato,A. Yamamoto,T. Endo
Proc. PHYSOR2014 2014年9月
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Improvement of a Convergence Technique for MOC Calculation with Large Negative Self-Scattering Cross Section 査読有り
M. Tabuchi,M. Tatsumi,A. Yamamoto,T. Endo
Proc. PHYSOR2014 2014年9月
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Generation of Simplified Burnup Chain using Contribution Matrix of Nuclide Production 査読有り
R. Katano,A. Yamamoto,T. Endo,Y. Kamiyama,K. Kirimura,S. Kosaka
Proc. PHYSOR2014 2014年9月
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Uncertainty Quantification of Neutronics Characteristics using Latin Hypercube Sampling Method 査読有り
K. Kinoshita,A. Yamamoto,T. Endo,Y. Kodama,Y. Ohoka,T. Ushio, H. Nagano
Proc. PHYSOR2014 2014年9月
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Applicability of the Cross Section Adjustment Method based on Random Sampling Technique For Burnup 査読有り
T. Watanabe,T. Endo,A. Yamamoto,Y. Kodama,Y. Ohoka,T. Ushio,
Proc. PHYSOR2014 2014年9月
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Uncertainty Quantification of BWR Core Characteristics using Latin Hypercube Sampling Method 査読有り
K. Kinoshita,A. Yamamoto,T. Endo,Y. Kodama,Y. Ohoka,T. Ushio,H. Nagano
Proc. PHYSOR2014 2014年9月
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Investigation on Subcriticality Measurement using Inherent Neutron Source in Nuclear Fuel 査読有り
T. Shiozawa,T. Endo,A. Yamamoto,C. H. Pyeon,T. Yagi
Proc. PHYSOR2014 2014年9月
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Prediction on Underestimation of Variance for Fission Rate Distribution in Monte-Carlo Calculation 査読有り
A. Yamamoto,K. Sakata,T. Endo
Trans. Am. Nucl. Soc. 110 巻 頁： 515-518 2014年6月
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An Improved CMFD Acceleration for SP3 Advanced Nodal Method 査読有り
T. Sakamoto,A. Yamamoto,T. Endo
Trans. Am. Nucl. Soc. 110 巻 頁： 535-537 2014年6月
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Applicability of angular flux discontinuity factor preserving region-wise leakage for integro-differential transport equation 査読有り
T. Sakamoto,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. 51 巻 頁： 1264-1273 2014年6月
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Applicability of angular flux discontinuity factor preserving region-wise leakage for integro-differential transport equation 査読有り
T. Sakamoto,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. 51 巻 頁： 00-00 2014年
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A new technique for spectral interference correction on pin-by-pin BWR core analysis 査読有り
T. Fujita,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. 51 巻 頁： 783-797 2014年
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Cross Section Adjustment Method Based on Random Sampling Technique 査読有り
T. Watanabe,T. Endo,A. Yamamoto,Y. Kodama,T. Ohoka,T. Ushio
J. Nucl. Sci. Technol. 51 巻 頁： 590-599 2014年
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A macroscopic cross-section model for BWR pin-by-pin core analysis 査読有り
T. Fujita,T. Endo,A. Yamamoto
J. Nucl. Sci. Technol. 51 巻 頁： 282-304 2014年
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Application of Augmented Reality to Nuclear Reactor Core Simulation for Fundamental Nuclear Engineering Education 査読有り
K. Tsujita,T. Endo,A. Yamamoto
Nucl. Technol. 185 巻 頁： 71-84 2014年
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Subcriticality Measurement Technique using Inherent Neutron Source in Uranium Fuel 査読有り
T. Shiozawa,T. Endo,A. Yamamoto,C. H. Pyeon,T. Yagi
Trans. Am. Nucl. Soc. 109 巻 頁： 826-829 2013年11月