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Journal Articles

Development of continuous energy Monte Carlo burn-up calculation code MVP-BURN

Okumura, Keisuke; Nakakawa, Masayuki; Kaneko, Kunio*; *

JAERI-Conf 2000-018, p.31 - 41, 2001/01

Burnup calculation codes based on the conventional deterministic approach often encounter difficult problems because of the constraints on the geometry description, limit of approximation on the effective resonance cross-sections, failing of the diffusion approximation due to extremely strong anisotropic or heterogenity. They are, for example, the prediction of burn characteristics of plutonium spot, core design of ultra-small reactors, analysis of the sample material in an irradiation capsule of the research rector. To deal with these problems any time, a burn-up calculation code (MVP-BURN) was developed by using a continuous energy Monte Carlo code MVP. MVP-BURN was validated by comparison with the results of deterministic codes in the international benchmark problems, and by comparison with the measured values of the spent fuel composition irradiated in a commercial reactor.

Journal Articles

Report of international conference 'Monte Carlo 2000'

Nakakawa, Masayuki

Robutsuri No Kenkyu, (51), p.47 - 51, 2000/12

no abstracts in English

Journal Articles

The Nuclear interaction at Oklo 2 billion years ago

Fujii, Yasunori*; Iwamoto, Akira; Fukahori, Tokio; Onuki, Toshihiko; Nakakawa, Masayuki; Hidaka, Hiroshi*; Oura, Yasutsugu*; M$"o$ller, P.*

Nuclear Physics B, 573(1-2), p.377 - 401, 2000/05

 Times Cited Count:188 Percentile:97.74(Physics, Particles & Fields)

no abstracts in English

JAEA Reports

Investigation of a neutron measuring system with a position-sensitive-fission-counter

Yamagishi, Hideshi; Ikeda, Yujiro; Ito, Hiroshi; Kakuta, Tsunemi; Nakakawa, Masayuki; Iwamura, Takamichi; Tabata, Hiroaki*; Urakami, Masao*

JAERI-Tech 2000-037, p.12 - 0, 2000/03

JAERI-Tech-2000-037.pdf:1.12MB

no abstracts in English

JAEA Reports

Core neutronics module and database access module for intelligent reactor design system (IRDS)

Kugo, Teruhiko; Tsuchihashi, Keiichiro*; Nakakawa, Masayuki; Ido, Masaru*

JAERI-Data/Code 2000-011, p.138 - 0, 2000/02

JAERI-Data-Code-2000-011.pdf:7.41MB

no abstracts in English

JAEA Reports

Multi-dimensional design window search system using neural networks in reactor core design

Kugo, Teruhiko; Nakakawa, Masayuki

JAERI-Data/Code 2000-004, p.97 - 0, 2000/02

JAERI-Data-Code-2000-004.pdf:10.51MB

no abstracts in English

Journal Articles

Validation of a continuous-energy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment

Okumura, Keisuke; Mori, Takamasa; Nakakawa, Masayuki; Kaneko, Kunio*

Journal of Nuclear Science and Technology, 37(2), p.128 - 138, 2000/02

no abstracts in English

Journal Articles

Application of continuous energy Monte Carlo code MVP to burn-up and whloe core calculations using cross sections at arbitrary temperatures

Mori, Takamasa; Okumura, Keisuke; Nagaya, Yasunobu; Nakakawa, Masayuki

Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, 2, p.987 - 996, 1999/09

no abstracts in English

Journal Articles

Application of neural network to multi-dimensional design window search in reactor core design

Kugo, Teruhiko; Nakakawa, Masayuki

Journal of Nuclear Science and Technology, 36(4), p.332 - 343, 1999/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present status of Monte Carlo simulation for neutron and photon transport

Ueki, Kotaro*; Mori, Takamasa; Sakurai, Kiyoshi; Nakakawa, Masayuki; *

Nihon Genshiryoku Gakkai-Shi, 41(6), p.614 - 627, 1999/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Benchmark analysis of experiments in fast critical assemblies using a continuous-energy monte carlo code MVP

Nagaya, Yasunobu; Nakakawa, Masayuki; Mori, Takamasa

Journal of Nuclear Science and Technology, 35(1), p.6 - 19, 1998/01

 Times Cited Count:3 Percentile:32.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Applicability of design window search procedure using neural network to neutronics

Kugo, Teruhiko; Nakakawa, Masayuki

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.704 - 711, 1998/00

no abstracts in English

Journal Articles

Development of intelligent code system to support conceptual design of nuclear reactor core

Kugo, Teruhiko; Nakakawa, Masayuki;

Journal of Nuclear Science and Technology, 34(8), p.760 - 770, 1997/08

 Times Cited Count:2 Percentile:23.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

New or improved computational methods and advanced reactor design

Iijima, Susumu; Okajima, Shigeaki; Nakakawa, Masayuki

Nihon Genshiryoku Gakkai-Shi, 39(1), p.25 - 27, 1997/00

no abstracts in English

Journal Articles

Error estimations and their biases in Monte Carlo eigenvalue calculations

Ueki, Taro*; Mori, Takamasa; Nakakawa, Masayuki

Nuclear Science and Engineering, 125(1), p.1 - 11, 1997/00

no abstracts in English

Journal Articles

Development of burn-up calculation code system MVP-BURN based on continuous energy Monte Carlo method and its validation

Okumura, Keisuke; Nakakawa, Masayuki; Kaneko, Kunio*

Proc. of SARATOGA 1997, 1, p.495 - 508, 1997/00

no abstracts in English

JAEA Reports

Neutron cross section library production code system for continuous energy Monte Carlo code MVP; LICEM

Mori, Takamasa; Nakakawa, Masayuki; *

JAERI-Data/Code 96-018, 121 Pages, 1996/05

JAERI-Data-Code-96-018.pdf:3.38MB

no abstracts in English

JAEA Reports

Continuous energy Monte Carlo calculations for randomly distributed spherical fuels based on statistical geometry model

Murata, Isao*; Mori, Takamasa; Nakakawa, Masayuki; Itakura, Hirofumi*

JAERI-Research 96-015, 44 Pages, 1996/03

JAERI-Research-96-015.pdf:1.32MB

no abstracts in English

JAEA Reports

Packing simulation code to calculate distribution on function of hard spheres by Monte Carlo method: MCRDF

Murata, Isao*; Mori, Takamasa; Nakakawa, Masayuki; *

JAERI-Data/Code 96-016, 79 Pages, 1996/03

JAERI-Data-Code-96-016.pdf:2.81MB

no abstracts in English

Journal Articles

Continuous energy Monte Carlo calculations of randomly distributed spherical fuels in high-temperature gas-cooled reactors based on a statistical geometry model

Murata, Isao; Mori, Takamasa; Nakakawa, Masayuki

Nuclear Science and Engineering, 123, p.96 - 109, 1996/00

 Times Cited Count:34 Percentile:92.69(Nuclear Science & Technology)

no abstracts in English

53 (Records 1-20 displayed on this page)