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Experimental data report for Test JM-2. Series of reactivity initiated accident test in the NSRR with fuel rod pre-irradiated in the JMTR

Technical Report:

Abstract

This report presents experimental data for Test JM-2 performed in the Nuclear Safety Research Reactor (NSRR) in January, 1990. This test is the second test using a test fuel rod which was pre-irradiated in the Japan Materials Testing Reactor (JMTR). The test fuel rod is a short-sized PWR (14 x 14) type one and was pre-irradiated up to a fuel burnup of approximately 26,800 MWd/t. Pulse irradiation of the test fuel rod was performed under the stagnant water cooling conditions of atmospheric pressure and room temperature using a newly developed double container type experimental capsule. Energy deposited in the test fuel rod by the pulse irradiation was estimated to be 116 cal/g{center_dot}UO{sub 2} (87 cal/g{center_dot}UO{sub 2} in terms of peak fuel enthalpy) by chemical FP analyses. No fuel failure was observed. This report contains test design and conduct, fuel burnup measurements, transient behavior of the rod during pulse irradiation and results of post-pulse-irradiation examination. (author).
Authors:
Tanzawa, Sadamitsu; Fuketa, Toyoshi; Homma, Kozo; Ishijima, Kiyomi; Fujishiro, Toshio [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Sep 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-157
Reference Number:
SCA: 220600; 210200; PA: JPN-91:012175; SN: 92000659209
Resource Relation:
Other Information: PBD: Sep 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; FUEL INTEGRITY; NSRR REACTOR; SPENT FUELS; POST-IRRADIATION EXAMINATION; IRRADIATION CAPSULES; TRANSIENTS; PHYSICAL RADIATION EFFECTS; METALLOGRAPHY; EXPERIMENTAL DATA; FUEL ELEMENT FAILURE; 220600; 210200; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10117391
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92768097; TRN: JP9112175
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
90 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Tanzawa, Sadamitsu, Fuketa, Toyoshi, Homma, Kozo, Ishijima, Kiyomi, and Fujishiro, Toshio. Experimental data report for Test JM-2. Series of reactivity initiated accident test in the NSRR with fuel rod pre-irradiated in the JMTR. Japan: N. p., 1991. Web.
Tanzawa, Sadamitsu, Fuketa, Toyoshi, Homma, Kozo, Ishijima, Kiyomi, & Fujishiro, Toshio. Experimental data report for Test JM-2. Series of reactivity initiated accident test in the NSRR with fuel rod pre-irradiated in the JMTR. Japan.
Tanzawa, Sadamitsu, Fuketa, Toyoshi, Homma, Kozo, Ishijima, Kiyomi, and Fujishiro, Toshio. 1991. "Experimental data report for Test JM-2. Series of reactivity initiated accident test in the NSRR with fuel rod pre-irradiated in the JMTR." Japan.
@misc{etde_10117391,
title = {Experimental data report for Test JM-2. Series of reactivity initiated accident test in the NSRR with fuel rod pre-irradiated in the JMTR}
author = {Tanzawa, Sadamitsu, Fuketa, Toyoshi, Homma, Kozo, Ishijima, Kiyomi, and Fujishiro, Toshio}
abstractNote = {This report presents experimental data for Test JM-2 performed in the Nuclear Safety Research Reactor (NSRR) in January, 1990. This test is the second test using a test fuel rod which was pre-irradiated in the Japan Materials Testing Reactor (JMTR). The test fuel rod is a short-sized PWR (14 x 14) type one and was pre-irradiated up to a fuel burnup of approximately 26,800 MWd/t. Pulse irradiation of the test fuel rod was performed under the stagnant water cooling conditions of atmospheric pressure and room temperature using a newly developed double container type experimental capsule. Energy deposited in the test fuel rod by the pulse irradiation was estimated to be 116 cal/g{center_dot}UO{sub 2} (87 cal/g{center_dot}UO{sub 2} in terms of peak fuel enthalpy) by chemical FP analyses. No fuel failure was observed. This report contains test design and conduct, fuel burnup measurements, transient behavior of the rod during pulse irradiation and results of post-pulse-irradiation examination. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}