You need JavaScript to view this

Annual progress report on the NSRR experiments, (21). April 1989 through March 1990

Technical Report:

Abstract

Fuel behavior studies under simulated reactivity-initiated accident (RIA) conditions have been performed in the Nuclear Safety Research Reactor (NSRR) since 1975. This report gives the results of experiments performed from April, 1989 through March, 1990 and discussions of them. A total of 41 tests were carried out during this period. The tests are distinguished into pre-irradiated fuel tests and fresh fuel tests; the former includes 2 JMTR pre-irradiated fuel tests, 2 PWR pre-irradiated fuel tests, and 2 BWR pre-irradiated fuel tests, and the latter includes 6 standard fuel tests (6 SP{center_dot}CP scoping tests), 7 power and cooling condition parameter tests (4 flow shrouded fuel tests, 1 bundle simulation test, 1 fully water-filled vessel test, 1 high pressure/high temperature loop test), 12 special fuel tests (3 stainless steel clad fuel tests, 3 improved PWR fuel tests, 6 improved BWR fuel tests), 3 severe fuel damage tests (1 high temperature flooding test, 1 flooding behavior observation test, 1 debris coolability test), 3 fast breeder reactor fuel tests (2 moderator material characteristic measurement tests, 1 fuel behavior observation test), and 2 miscellaneous tests (2 preliminary tests for pre-irradiated fuel tests). (author).
Publication Date:
May 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-072
Reference Number:
SCA: 220900; 220600; PA: JPN-92:011111; SN: 93000918516
Resource Relation:
Other Information: PBD: May 1992
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL ELEMENT FAILURE; NSRR REACTOR; PROGRESS REPORT; IRRADIATION; IRRADIATION CAPSULES; FUEL INTEGRITY; POST-IRRADIATION EXAMINATION; METALLOGRAPHY; PWR TYPE REACTORS; BWR TYPE REACTORS; FUEL SCANNING; TEMPERATURE DEPENDENCE; PRESSURE DEPENDENCE; COMPUTER CODES; FUEL CANS; 220900; 220600; REACTOR SAFETY; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10111144
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93753190; TRN: JP9211111
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
210 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

None. Annual progress report on the NSRR experiments, (21). April 1989 through March 1990. Japan: N. p., 1992. Web.
None. Annual progress report on the NSRR experiments, (21). April 1989 through March 1990. Japan.
None. 1992. "Annual progress report on the NSRR experiments, (21). April 1989 through March 1990." Japan.
@misc{etde_10111144,
title = {Annual progress report on the NSRR experiments, (21). April 1989 through March 1990}
author = {None}
abstractNote = {Fuel behavior studies under simulated reactivity-initiated accident (RIA) conditions have been performed in the Nuclear Safety Research Reactor (NSRR) since 1975. This report gives the results of experiments performed from April, 1989 through March, 1990 and discussions of them. A total of 41 tests were carried out during this period. The tests are distinguished into pre-irradiated fuel tests and fresh fuel tests; the former includes 2 JMTR pre-irradiated fuel tests, 2 PWR pre-irradiated fuel tests, and 2 BWR pre-irradiated fuel tests, and the latter includes 6 standard fuel tests (6 SP{center_dot}CP scoping tests), 7 power and cooling condition parameter tests (4 flow shrouded fuel tests, 1 bundle simulation test, 1 fully water-filled vessel test, 1 high pressure/high temperature loop test), 12 special fuel tests (3 stainless steel clad fuel tests, 3 improved PWR fuel tests, 6 improved BWR fuel tests), 3 severe fuel damage tests (1 high temperature flooding test, 1 flooding behavior observation test, 1 debris coolability test), 3 fast breeder reactor fuel tests (2 moderator material characteristic measurement tests, 1 fuel behavior observation test), and 2 miscellaneous tests (2 preliminary tests for pre-irradiated fuel tests). (author).}
place = {Japan}
year = {1992}
month = {May}
}