Experiments and analyses on reactivity worth of gas expansion module (GEM) in FCA XX-1 (Joint research)

Oigawa, Hiroyuki; Ando, Masaki; Iijima, Susumu; Takaki, Naoyuki*; Uematsu, Mari Marianne*

JAERI-Research 2001-036, 48 Pages, 2001/06

JAERI-Research-2001-036.pdf:2.38MB

no abstracts in English

None

; Numata, Kazuyuki*; ; *; Oigawa, Hiroyuki*

JNC TY9400 2000-006, 162 Pages, 2000/04

JNC-TY9400-2000-006.pdf:4.57MB

no abstracts in English

A Proposal of benchmark calculation on reactor physics for metallic fueled and MOX fueled LMFBR based upon mock-up experiment at FCA

Oigawa, Hiroyuki; Iijima, Susumu; Sakurai, Takeshi; Okajima, Shigeaki; Ando, Masaki; Nemoto, Tatsuo; Kato, Yuichi*; Osugi, Toshitaka

Journal of Nuclear Science and Technology, 37(2), p.186 - 201, 2000/02

https://doi.org/10.3327/jnst.37.186

no abstracts in English

Analysis of measurements for a Uranium-free core experiment at the BFS-2 critical assembly

Hunter

JNC TN9400 99-049, 74 Pages, 1999/04

JNC-TN9400-99-049.pdf:2.03MB

This document describes a series of calculations that were carried out to model various measurements from the BFS-58-1-I1 experiment. BFS-58-1-I1 was a mock-up of a uranium-free, Pu burning core at BFS-2, a Russian critical assembly operated by IPPE. The experiment measured values of keff, Na void reactivity worth, material sample reactivity worths and reaction rate ratios. The experiments were modelled using a number of different methods. Basic nuclear data was taken from JENDL-3.2, in either 70 or 18 groups. Cross-section data for the various material regions of the assembly were calculated by either SLAROM or CASUP; the heterogeneous structure of the core regions was modelled in these calculations, with 3 different options considered for representing the (essentially 2d) geometry of the assembly components in a 1D cell model. Whole reactor calculations of flux and keff were done using both a diffusion model (CITATION) and a transport model (TWOTRAN2), both using an RZ geometry. Reactivity worths were calculated both directly from differences in keff values and by using the exact perturbation calculations of PERKY and SN-PERT (for CITATION and TWOTRAN2, respectively). Initial calculations included a number of inaccuracies in the assembly representation, a result of communication difficulties between JNC and IPPE; these errors were removed for the final calculations that are presented. Calculations for the experiments have also been carried out in Russia (IPPE) and France (CEA) as part of an international comparison exercise, some of those results are also presented here. The calculated value of keff was 1.1%k/k higher than the measured value, Na void worth C/E values were 1.06; these results were considered to be reasonable. (Discrepancies in certain Na void values were probably due to experimental causes, though the efect should be investigated in any future experiments.) several sample worth values were small compared with calculational uncertaint

None

PNC TJ2222 94-001, 264 Pages, 1994/03

PNC-TJ2222-94-001.pdf:9.07MB

None

Doppler effect measurement up to 2000C at FCA

Okajima, Shigeaki; Oigawa, Hiroyuki; Ando, Masaki; Mukaiyama, Takehiko

Proc., Int. Conf. on Nuclear Data for Science and Technology,Vol. 2, 0, p.1009 - 1011, 1994/00

no abstracts in English

None

*; *; *

PNC TJ2222 92-001, 145 Pages, 1992/03

PNC-TJ2222-92-001.pdf:4.74MB

None

Experimental study on reactivity worth in high conversion light water reactor using FCA-HCLWR cores

Okajima, Shigeaki; Sakurai, Takeshi; Osugi, Toshitaka; Oigawa, Hiroyuki

JAERI-M 90-042, 53 Pages, 1990/03

JAERI-M-90-042.pdf:1.34MB

no abstracts in English

Fast Critical Experiments in FCA and their Analysis

*

JAERI 1289, 132 Pages, 1984/02

JAERI-1289.pdf:7.99MB

no abstracts in English

None

*; Ishiguro, Yukio*; *; Inagaki, Tatsutoshi*; *; *; *; Kato, Yasuyoshi*; Shirakata, Keisho;

PNC TN241 84-07, 16 Pages, 1982/10

PNC-TN241-84-07.pdf:0.37MB

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