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JAEA Reports

Experiments of JRR-4 low-enriched-uranium-silicied fuel core

Hirane, Nobuhiko; Ishikuro, Yasuhiro; Nagadomi, Hideki; Yokoo, Kenji; Horiguchi, Hironori; Nemoto, Takumi; Yamamoto, Kazuyoshi; Yagi, Masahiro; Arai, Nobuyoshi; Watanabe, Shukichi; et al.

JAEA-Technology 2006-028, 115 Pages, 2006/03

JAEA-Technology-2006-028.pdf:7.96MB

JRR-4, a light-water-moderated and cooled, swimming pool type research reactor using high-enriched uranium plate-type fuels had been operated from 1965 to 1996. In order to convert to low-enriched-uranium-silicied fuels, modification work had been carried out for 2 years, from 1996 to 1998. After the modification, start-up experiments were carried out to obtain characteristics of the low-enriched-uranium-silicied fuel core. The measured excess reactivity, reactor shutdown margin and the maximum reactivity addition rate satisfied the nuclear limitation of the safety report for licensing. It was confirmed that conversion to low-enriched-uranium-silicied fuels was carried out properly. Besides, the necessary data for reactor operation were obtained, such as nuclear, thermal hydraulic and reactor control characteristics. This report describes the results of start-up experiments and burnup experiments. The first criticality of low-enriched-uranium-silicied core was achieved on 14th July 1998, and the operation for joint-use has been carried out since 6th October 1998.

JAEA Reports

Measurement of coolant flow in fuel elements at the JRR-4 silicide fuel core

Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nagatomi, Hideki; Kaminaga, Masanori; Funayama, Yoshiro

JAERI-Tech 2002-034, 40 Pages, 2002/03

JAERI-Tech-2002-034.pdf:1.97MB

JRR-4, a swimming-pool type research reactor with a thermal power of 3.5MW, attained criticality in July 1998, after replacing its 90% enrichment fuel with a 20% enrichment fuel under the Reduced Enrichment Program. As a part of the program, safety analysis on thermo-hydraulics of the reactor core was conducted on cases including single channel blockage accident. With the conclusion that a certain margin on thermo-hydraulics was necessary, investigation and experiments were carried out with an aim to increase the core flow rate. To increase the core flow, it was carried out to reduce the bypass flow in the core and to increase the primary coolant flow rate from 7m$$^{3}$$/min to 8m$$^{3}$$/min. After flow measurements using a mock-up fuel element, flow velocity of the fuel channel was determined as 1.45m/s as opposed to the designed value of 1.44m/s, and the ratio of core flow to total flow was 0.88, exceeding the value 0.86 used for the safety analysis.This report describes the JRR-4 core flow increase plan as well as the results of the channel flow rate measurement

Journal Articles

Conversion of JRR-4 fuel to LEU

Watanabe, Shukichi; Nakajima, Teruo; Kaieda, Keisuke

JAERI-Conf 99-006, p.119 - 124, 1999/08

no abstracts in English

JAEA Reports

Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-4 silicide LEU core

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi

JAERI-Tech 96-039, 72 Pages, 1996/09

JAERI-Tech-96-039.pdf:2.43MB

no abstracts in English

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-4 silicide LEU core

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro

JAERI-Tech 95-040, 79 Pages, 1995/07

JAERI-Tech-95-040.pdf:2.25MB

no abstracts in English

JAEA Reports

Basic experiments of reactor physics using the research reactor JRR-4 and NSRR

Obara, Toru*; Horiki, Oichiro*; Nakajima, Teruo; Watanabe, Shukichi; Ishijima, Kiyomi; Katanishi, Shoji

JAERI-Review 95-010, 39 Pages, 1995/06

JAERI-Review-95-010.pdf:1.14MB

no abstracts in English

JAEA Reports

Neutronic and thermo-hydraulic design of LEU core for Japan Research Reactor 4

Arigane, Kenji; Watanabe, Shukichi; Tsuruta, Harumichi

JAERI-M 88-078, 21 Pages, 1988/04

JAERI-M-88-078.pdf:0.67MB

no abstracts in English

Journal Articles

Neutronic and thermo-hydralic design of JRR-4 LEU core

Arigane, Kenji; Watanabe, Shukichi; Tsuruta, Harumichi

Japan-China Symp. on Research and Test Reactors, 17 Pages, 1988/00

no abstracts in English

Oral presentation

Evaluation of heat generation in JRR-4 reflector elements

Yagi, Masahiro; Kashima, Yoichi; Nagadomi, Hideki; Watanabe, Shukichi

no journal, , 

no abstracts in English

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