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JAEA Reports

Evaluation of the minimum critical amount for heterogeneous lattice systems composed of fuel rods utilized in low-power water-moderated research and test reactors by using continuous-energy Monte Carlo code MVP with JENDL-4.0

Yanagisawa, Hiroshi

JAEA-Technology 2021-023, 190 Pages, 2021/11

JAEA-Technology-2021-023.pdf:5.25MB

Computational analyses on nuclear criticality characteristics were carried out for heterogeneous lattice systems composed of water moderator and fuel rods utilized in lowpower research and test reactors, in which the depletion of fuel due to burnup is relatively small, by using the continuous-energy Monte Carlo code MVP Version 2 with the evaluated nuclear data library JENDL-4.0. In the analyses, the minimum critical number of fuel rods was evaluated using calculated neutron multiplication factors for the heterogeneous systems of the uranium dioxide fuel rod in the Static Experiments Critical Facility (STACY) and the Tank-type Critical Assembly (TCA), and the uranium-zirconium hydride fuel rod in the Nuclear Safety Research Reactor (NSRR). In addition, six sorts of the ratio of reaction rates, which are components of neutron multiplication factors, were calculated in the analyses to explain the variation of neutron multiplication factors with the ratio of water moderator to fuel volume in a unit fuel rod cell. Those results of analyses are considered to be useful for the confirmation of reasonableness and validity of criticality safety measures as data showing criticality characteristics for water-moderated heterogeneous lattice systems composed of the existing fuel rods in research and test reactors, of which criticality data are not sufficiently provided by the Criticality Safety Handbook.

Journal Articles

Simplified calculation method for radiation streaming

Matsuda, Norihiro

Hoshasen Shahei Handobukku; Kisohen, p.229 - 288, 2015/03

no abstracts in English

Journal Articles

Calculation of nuclear characteristic parameters and drawing subcriticality judgment graphs of infinite fuel systems for typical nuclear fuels

Okuno, Hiroshi; Takada, Tomoyuki

Journal of Nuclear Science and Technology, 41(4), p.481 - 492, 2004/04

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

Nuclear characteristic parameters were calculated and subcriticality judgement graphs were drawn for revision purposes of the Data Collection for the Nuclear Criticality Safety Handbook. The nuclear characteristic parameters were the neutron multiplication factor in infinite media, migration area and diffusion constants for 11 kinds of typical fuels encountered in criticality safety evaluation of nuclear fuel cycle facilities. These fuels included ADU-H$$_{2}$$O, UF6-HF and Pu(NO$$_{3}$$)$$_{4}$$-UO$$_{2}$$(NO$$_{3}$$)$$_{2}$$ solution, of which data were not cited in the Data Collection. The calculation was made with the Japanese evaluated nuclear data library JENDL-3.2 and a sequence of criticality calculation codes, SRAC, POST and SIMCRI. The subcriticality judgement graphs that depict the region satisfying the inequality relation of the neutron multiplication factor less than 0.98 between the two variables (a) uranium enrichment, 239Pu/Pu ratio or plutonium enrichment and (b) H/(Pu+U) ratio were drawn for the same kinds of fuels except UF6-HF in infinite media.

Journal Articles

Activities for revising Nuclear Criticality Safety Handbook

Okuno, Hiroshi; Nomura, Yasushi

Proceedings of the 2001 Topical Meeting on Practical Implementation of Nuclear Criticality Safety (CD-ROM), 8 Pages, 2001/11

The nuclear criticality safety handbook of Japan was first published in 1988, which was translated into English in 1995. This paper intends to introduce the American community of nuclear criticality safety to activities for revising the Japanese handbook, putting an emphasis on practical use of code validation. They include (1) publication of "Nuclear Criticality Safety Handbook, Version 2" and its English translation, (2) publication of "A Guide Introducing Burnup Credit, Preliminary Version," and (3) preparation of "Nuclear Criticality Safety Handbook, -Data Collection-, Version 2."

JAEA Reports

Nuclear criticality safety handbook, 2; English translation

Working Group on Nuclear Criticality Satety Data

JAERI-Review 2001-028, 217 Pages, 2001/08

JAERI-Review-2001-028.pdf:10.04MB

no abstracts in English

JAEA Reports

JAEA Reports

Study on safety of crystallization method applied to dissolver solution in fast breeder reactor reprocessing

; Fujine, Sachio; Asakura, Toshihide; Murazaki, Minoru*; *; Sakakibara, Tetsuro*; *

JAERI-Research 99-027, 37 Pages, 1999/03

JAERI-Research-99-027.pdf:1.82MB

no abstracts in English

JAEA Reports

Base data for looking-up tables of calculation errors in JACS code system

Murazaki, Minoru*;

JAERI-Data/Code 99-019, 103 Pages, 1999/03

JAERI-Data-Code-99-019.pdf:3.69MB

no abstracts in English

JAEA Reports

Nuclear criticality safety handbook, 2

Working Group on Nuclear Criticality Satety Data

JAERI 1340, 189 Pages, 1999/03

JAERI-1340.pdf:8.41MB

no abstracts in English

Journal Articles

Introduction to ``International handbook of criticality safety benchmark experiments''

Komuro, Yuichi

Nihon Genshiryoku Gakkai-Shi, 40(9), p.697 - 701, 1998/00

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

no abstracts in English

Journal Articles

Studies on burnup credit at JAERI

; Nomura, Yasushi; Suyama, Kenya

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.742 - 748, 1998/00

no abstracts in English

Journal Articles

Preparation for the 2nd edition of nuclear criticality safety handbook

; Nomura, Yasushi

Nihon Genshiryoku Gakkai-Shi, 39(10), p.832 - 841, 1997/00

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

no abstracts in English

JAEA Reports

Criticality data of water-reflected and-moderated homogeneous mixed oxide fuel

Komuro, Yuichi; *

JAERI-Data/Code 96-002, 73 Pages, 1996/02

JAERI-Data-Code-96-002.pdf:2.65MB

no abstracts in English

JAEA Reports

Supplement report to the nuclear criticality safety handbook of Japan

Okuno, Hiroshi; Komuro, Yuichi; Nakajima, Ken; Nomura, Yasushi; Naito, Yoshitaka; Nishina, Kojiro*; *; *; Miyoshi, Yoshinori; *; et al.

JAERI-Tech 95-048, 168 Pages, 1995/10

JAERI-Tech-95-048.pdf:4.87MB

no abstracts in English

Journal Articles

Supplements to the Nuclear Criticality safety Handbook of Japan

Okuno, Hiroshi; Komuro, Yuichi; Nakajima, Ken; Nomura, Yasushi; Naito, Yoshitaka

ICNC 95: 5th Int. Conf. on Nuclear Criticality Safety, Vol. I, 0, p.2.61 - 2.65, 1995/00

no abstracts in English

JAEA Reports

Criticality parameters and data for various nuclear fuel materials in infinite dimensions; Calculations with the combination of MGCL-J3 and SIMCRI

Okuno, Hiroshi; Umeda, Kentaro*; Komuro, Yuichi; Naito, Yoshitaka

JAERI-M 93-135, 98 Pages, 1993/08

JAERI-M-93-135.pdf:4.1MB

no abstracts in English

JAEA Reports

Handbook for thermal analysis of radioactive material transport casks

JAERI-M 91-061, 119 Pages, 1991/04

JAERI-M-91-061.pdf:1.5MB

no abstracts in English

JAEA Reports

Handbook for structural analysis of radioactive material transport casks

JAERI-M 91-060, 164 Pages, 1991/04

JAERI-M-91-060.pdf:3.1MB

no abstracts in English

Journal Articles

Preparations for revising the criticality safety handbook of Japan

Okuno, Hiroshi; Komuro, Yuichi; Naito, Yoshitaka

Proc. of the 91 Int. Conf. on Nuclear Criticality Safety,Vol. 1, p.III-38 - III-43, 1991/00

no abstracts in English

Journal Articles

Preparations for revising the criticality safety handbook of Japan

Okuno, Hiroshi; Komuro, Yuichi; Naito, Yoshitaka

Proc. of the CSNI Specialist Meeting on Safety and Risk Assessment in Fuel Cycle Facilities, p.103 - 109, 1991/00

no abstracts in English

27 (Records 1-20 displayed on this page)