Takamasa Mori

发表

Criticality Benchmarks with a Continuous-Energy Monte Carlo Code MVP and JENDL-3.3

Keisuke Okumura, Yasunobu Nagaya, Takamasa Mori, 2005 .

Advanced Scientific Computational Methods and Their Applications to Nuclear Technologies―(5) Simulation Methods in Discretized Systems, (1): 第5回離散系のシミュレーション手法 (その1)

Toshihisa Yamamoto, Takamasa Mori, 2006 .

Overview of Recent Research Activities of Monte Carlo Simulation in Japan

Yasushi Nomura, Yoshitaka Naito, Toshihiro Yamamoto, 2000 .

Estimation of Sample Reactivity Worth with Differential Operator Sampling Method (Selected Papers of the Joint International Conference of Supercomputing in Nuclear Applications and Monte Carlo : SNA + MC 2010)

Yasunobu Nagaya, Takamasa Mori, Y. Nagaya, 2011 .

ICONE15-10371 Application of Bias Factor Method with Use of Virtual Experimental Value to Prediction Uncertainty Reduction in Void Reactivity Worth of Breeding Light Water Reactor

Toshikazu Takeda, Teruhiko Kugo, Takamasa Mori, 2007 .

ANALYSIS OF VENUS-2 MOX CORE MEASUREMENTS WITH A MONTE CARLO CODE MVP

Keisuke Okumura, Yasunobu Nagaya, Takamasa Mori, 2002 .

Monte Carlo calculations on vector supercomputers using GMVP

Masayuki Nakagawa, Makoto Sasaki, Takamasa Mori, 1990 .

Fusion Integral Experiments and Analysis and the Determination of Design Safety Factors — II: Application to the Prediction Uncertainty of Tritium Production Rate from the U.S. DOE/JAERI Collaborative Program on Fusion Blanket Neutronics

Hiroshi Maekawa, Mohamed A. Abdou, Chikara Konno, 1995 .

Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model

Masayuki Nakagawa, Takamasa Mori, Takamasa Mori, 1996 .

Hexagonal lattice geometry for Monte Carlo calculations

Masayuki Nakagawa, Takamasa Mori, Takamasa Mori, 1991 .

Error estimations and their biases in Monte Carlo eigenvalue calculations

Masayuki Nakagawa, Taro Ueki, Takamasa Mori, 1997 .

Theoretical Study on New Bias Factor Methods to Effectively Use Critical Experiments for Improvement of Prediction Accuracy of Neutronic Characteristics

Toshikazu Takeda, Teruhiko Kugo, Takamasa Mori, 2007 .

Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation

Masayuki Nakagawa, Takamasa Mori, Takamasa Mori, 1992 .

Prediction Accuracy Improvement of Neutronic Characteristics of a Breeding Light Water Reactor Core by Extended Bias Factor Methods with Use of FCA-XXII-1 Critical Experiments

Shigeaki Okajima, Toshikazu Takeda, Yoshihiro Nakano, 2008 .

Whole Core Calculations of Power Reactors by Use of Monte Carlo Method

Masayuki Nakagawa, Takamasa Mori, 1993 .

Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment

Masayuki Nakagawa, Takamasa Mori, K. Kaneko, 2000 .

Validation study of the Monte Carlo code MVP for analysis of two-region TCA critical experiments with PWR-type MOX fuels

T. Suzaki, Takamasa Mori, Mafizur Rahman, 2006 .

New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors

Masayuki Nakagawa, Isao Murata, Takamasa Mori, 1997 .

Measurement of tritium production-rate distribution in a 60 cm-thick Li/sub 2/O slab assembly and its analysis

Hiroshi Maekawa, Masayuki Nakagawa, Yasushi Seki, 1985 .