論文 - 山本 章夫
-
Acceleration of Response Matrix Method by Cross Section Scaling 査読有り
A. Yamamoto
Proc. International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing 頁: 1A-03 2002年10月
-
SCOPE2:Object-Oriented Parallel Code for Multi-Group Diffusion/Transport Calculations in Three-Dimensional Fine-Mesh Reactor Core Geometry 査読有り
M. Tatsumi, A. Yamamoto
Proc. International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing 頁: 12A-01 2002年10月
-
Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels 査読有り
A. Yamamoto, T. Ikehara, T. Ito, E. Saji
J. Nucl. Sci. Technol. 39 巻 頁: 900-912 2002年8月
-
Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses 査読有り
M. Tatsumi, A. Yamamoto
Nucl. Sci. Eng. 141 巻 頁: 190-217 2002年7月
-
PWR Core Calculations by the Multigroup Nodal-Transport Method in 3-D Pin-by-Pin Geometry 査読有り
M. Tatsumi, A. Yamamoto
Trans. Am. Nucl. Soc. 87 巻 頁: 232-234 2002年6月
-
Basic study on neutronics of future neutron source based on accelerator driven subcritical reactor concept in Kyoto University Research Reactor Institute (KURRI) 査読有り
S. Shiroya, A. Yamamoto, K. Shin, T. Ikeda, S. Nakano, H. Unesaki
Prog. Nucl. Energy 40 巻 頁: 489-496 2002年3月
-
Recent Activities of Loading Pattern Optimization Research in Japan 招待有り 査読有り
A. Yamamoto
Trans. Am. Nucl. Soc 84 巻 頁: 57-59 2001年11月
-
A Conceptual Neuronics Design Study for Next Generation Neutron Source in Kyoto University research Reactor Institute (KURRI) 査読有り
A. Yamamoto, S. Shiroya
Proc. ICENES 2000: The Tenth International Conference on Emerging Nuclear Energy Systems, Petten CD-ROM 巻 頁: 66-75 2000年9月
-
Effect of Core Calculation Models on Optimum Cycle Length Analyses of Pressurized Water Reactors 査読有り
A. Yamamoto, T. Kimoto
Ann. Nucl. Energy 27 巻 頁: 1039-1050 2000年7月
-
Analysis of the Ikata-3 Initial Core with the CHAPLET Heterogeneous Transport Calculation Code Based on the Method of Characteristics 招待有り 査読有り
M. Tatsumi, T.Kimoto, A. Yamamoto
Trans. Am. Nucl. Soc. 83 巻 頁: 286-287 2000年6月
-
Verification of Cell-Homogenized Whole-Core Transport Calculations in Actual PWR Core Geometry 招待有り 査読有り
A. Yamamoto, M. Tatsumi, T. Kimoto, S, Kosaka, E. Saji
Trans. Am. Nucl. Soc. 83 巻 頁: 287-289 2000年6月
-
Effect of Core Calculation Accuracy on Fuel Cycle Cost 査読有り
A. Yamamoto
Proc. Advances in Reactor Physics and Mathematics and Computation into the Next Millennium 頁: Ⅶ.A-2 2000年5月
-
A Study on Effects of Pin Cell Homogenization in an Actual Reactor Core Geometry 査読有り
M. Tatsumi, A. Yamamoto,S.Kosaka,E.Saji
Proc. Advances in Reactor Physics and Mathematics and Computation into the Next Millennium 頁: IX.D-5 2000年5月
-
A Study on Non-Proliferative, Retrofittable PWR fuel 査読有り
Y. Katagiri, Y. Yamane, A. Yamamoto
Proc. of ICONE 8: 8th International Conference on Nuclear Engineering CD-ROM 巻 頁: 8366 2000年4月
-
Application of Temperature Parallel Simulated Annealing to Loading Pattern Optimizations of Pressurized Water Reactors," 査読有り
A. Yamamoto, H. Hashimoto
Nucl Sci. Eng. 136 巻 頁: 247-257 2000年
-
Loading Pattern Optimizations in a Distributed Parallel Environment 招待有り 査読有り
A. Yamamoto, H. Hashimoto
Trans. Am. Nucl. Soc. 80 巻 頁: 223-224 1999年11月
-
Applications of Temperature Parallel Simulated Annealing to Loading Pattern Optimizations of Pressurized Water Reactors 招待有り 査読有り
A. Yamamoto, H. Hashimoto
Proc. Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications 2 巻 頁: 1445-1458 1999年9月
-
Effective Utilization of Weapon-Grade Plutonium to Upgrade Repeatedly-Reprocessed Mixed-Oxide Fuel for Use in Pressurized Water Reactors 査読有り
Y. Hanayama, A. Yamamoto K. Kanda
J. Nucl. Sci. Technol. 36 巻 頁: 746-754 1999年9月
-
Advanced Reactor Core Analysis by the Object-oriented 3-D Fine Mesh Transport Calculation on Parallel/Distributed Environment 招待有り 査読有り
M. Tatsumi, A. Yamamoto, H. Hashimoto
Proc. Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications 2 巻 頁: 1288-1297 1999年9月
-
A Comparison Between a One Point Reactor Model And a Two-Dimensional Core Model on Equilibrium Cycle Analysis of Pressurized Water Reactors 査読有り
A. Yamamoto, T. Kimoto
Proc. International Conference of the Physics of Nuclear Science and Technology 1 巻 頁: 84-90 1998年10月