Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 24

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Thermal hydraulic analysis of the JMTR improved LEU-core

Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Takeda, Takashi*; Fujiki, Kazuo

JAERI-Tech 2002-100, 108 Pages, 2003/01

JAERI-Tech-2002-100.pdf:4.44MB

After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the "improved LEU core" that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle.

JAEA Reports

Neutronics analysis of the improved LEU core in JMTR

Komukai, Bunsaku; Naka, Michihiro; Tabata, Toshio; Nagao, Yoshiharu; Takeda, Takashi*; Fujiki, Kazuo

JAERI-Tech 2002-067, 75 Pages, 2002/08

JAERI-Tech-2002-067.pdf:3.41MB

no abstracts in English

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

Progress towards the establishment of integrated safeguards in Japan

Naito, Kaoru; Ogawa, Tsuyoshi*; Osabe, Takeshi*

Proceedings of 42nd INMM Annual Meeting, 12 Pages, 2001/00

no abstracts in English

Journal Articles

Feasibility study for improvement of efficient irradiation with LEU core in JMTR

Naka, Michihiro; Nagao, Yoshiharu; Komukai, Bunsaku; Tabata, Toshio

Proceedings of 7th Meeting of the International Group on Research Reactors (IGORR-7) (CD-ROM), 7 Pages, 1999/10

no abstracts in English

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

Decrease in coolability events analysis for the safety assessment of JRR-3 silicide core by THYDE-W code

Kaminaga, Masanori; Yamamoto, Kazuyoshi

JAERI-Tech 97-016, 120 Pages, 1997/03

JAERI-Tech-97-016.pdf:3.76MB

no abstracts in English

JAEA Reports

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-3 silicide core by EUREKA-2 code

Kaminaga, Masanori

JAERI-Tech 97-014, 125 Pages, 1997/03

JAERI-Tech-97-014.pdf:4.04MB

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

Journal Articles

Dose analysis in safety and site evaluation for the JMTR core conversion to LEU fuel

Tsuchida, Noboru; ; ; ; ; Saito, Minoru;

ANL/RERTR/TM-19, CONF-9209266, 0, p.259 - 266, 1995/00

no abstracts in English

Journal Articles

Study on the reliability of silicide fuels at elevated temperatures

Yanagisawa, Kazuaki;

Proc. of 4th Asian Symp. on Research Reactors; ASRR-IV, p.58 - 69, 1993/00

no abstracts in English

JAEA Reports

Safety analysis of JMTR LEU fuel core, 3; Dose analysis at accidents in safety and site evaluation

Tsuchida, Noboru; ; ; ; ; Saito, Minoru;

JAERI-M 92-152, 92 Pages, 1992/10

JAERI-M-92-152.pdf:2.71MB

no abstracts in English

JAEA Reports

Neutronics design of JMTR-LEU core

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Koike, Sumio; Saito, Minoru;

JAERI-M 92-098, 81 Pages, 1992/07

JAERI-M-92-098.pdf:1.81MB

no abstracts in English

JAEA Reports

Safety analysis of JMTR-LEU cores, 1; Reactivity initiated accident analysis

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;

JAERI-M 92-095, 68 Pages, 1992/07

JAERI-M-92-095.pdf:1.52MB

no abstracts in English

JAEA Reports

Nuclear hot spot factor of JMTR-LEU core

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;

JAERI-M 92-042, 92 Pages, 1992/03

JAERI-M-92-042.pdf:2.18MB

no abstracts in English

Journal Articles

Performance of JRR-3M

Isshiki, Masahiko; Takahashi, Hidetake; Ichikawa, Hiroki; Shirai, Eiji

Nippon Genshiryoku Gakkai-Shi, 34(2), p.108 - 118, 1992/02

 Times Cited Count:5 Percentile:50.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress in safety evaluation for the JMTR core conversion to LEU fuel

; ; Saito, Junichi; Komukai, Bunsaku; Ando, Hiroei; ; ; ; Saito, Minoru;

Proc. on 12th Int. Meeting,Reduced Enrichment for Research and Test Reactors, p.269 - 280, 1991/00

no abstracts in English

Journal Articles

Analyses on LEU conversion of research and test reactors at JAERI

Ando, Hiroei; Saito, Minoru; Tsuruta, Harumichi; ; Sakurai, Hiroshi

Transactions of the American Nuclear Society, 56, p.577 - 578, 1988/00

no abstracts in English

24 (Records 1-20 displayed on this page)