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

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-2000-018.pdf

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.

The Nuclear interaction at Oklo 2 billion years ago

Fujii, Yasunori*; Iwamoto, Akira; Fukahori, Tokio; Onuki, Toshihiko; Nakakawa, Masayuki; Hidaka, Hiroshi*; Oura, Yasutsugu*; Mller, P.*

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

https://doi.org/10.1016/S0550-3213(00)00038-9

no abstracts in English

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

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

https://doi.org/10.3327/jnst.37.128

no abstracts in English

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

https://doi.org/10.3327/jnst.36.332

no abstracts in English

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

https://doi.org/10.3327/jnst.35.6

no abstracts in English

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

https://doi.org/10.3327/jnst.34.760

no abstracts in English

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

https://doi.org/10.13182/NSE97-1

no abstracts in English

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

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