Fuel safety research 2001

Uetsuka, Hiroshi

JAERI-Review 2002-027, 147 Pages, 2002/11

JAERI-Review-2002-027.pdf:9.54MB

The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the NSRR, the JMTR, the JRR-3 and the Reactor Fuel Examination Facility of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents.This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory.

Improvement of irradiation facilities performance in JMTR

Kanno, Masaru; ; ; Sagawa, Hisashi;

JAERI-Conf 99-006, p.264 - 269, 1999/08

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-99-006.pdf

no abstracts in English

Fission gas release during power change; Re-irradiation test of LWR fuel rod at JMTR

Nakamura, Jinichi; Endo, Yasuichi; ; ; Furuta, Teruo

JAERI-Research 95-083, 38 Pages, 1995/11

JAERI-Research-95-083.pdf:1.42MB

no abstracts in English

Irradiation experience of power ramping test facility in JMTR

; ; ;

UTNL-R-0274, p.2-1 - 2-6, 1992/00

no abstracts in English

Experimental plan on irradiated LWR fuels at JAERI

Uetsuka, Hiroshi; Nakamura, Jinichi; Nagase, Fumihisa; Uchida, Masaaki; Furuta, Teruo

Fuel Performance Experiment and Analysis and Computerised Man-Machine Communication, p.1 - 11, 1990/09

no abstracts in English

A Method for Evaluating the Linear Heat Rate of the Fuel Rod in BOCA/OSF-1

Kawamura, Hiroshi; ; ; ;

JAERI-M 85-211, 50 Pages, 1985/12

JAERI-M-85-211.pdf:0.99MB

no abstracts in English

Development of fuel transient test facility in JMTR

Kimura, Nobuaki; Matsui, Yoshinori; Tobita, Masahiro*; Nakamura, Jinichi; Yamaura, Takayuki

no journal, , 

Power transient tests for the fuels of light water reactors were to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels had been to be investigated by the tests. Prior to the irradiation tests of the fuels, evaluation of thermal-hydraulic behavior in the capsule using ACE-3D code were carried out. And more, the out-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. From these analytical and experimental results, it was confirmed that the power ramping tests for 1010 BWR fuel are able to achieve linear heat rate of 600W/cm in JMTR.