Published May 2008 | Version v1
Journal article Metadata-only

Fission gas release in BWR fuel with a burnup of 56 GWd/t during simulated reactivity initiated accident (RIA) condition

Creators

  • 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)

Description

A pulse irradiation simulated reactivity initiated accident (RIA) condition was tested for the test rod prepared from a BWR fuel rod with a burnup of 56 GWd/t irradiated in a commercial reactor, and fission gas release during pulse irradiation was investigated based on the result of a rod-puncture test and the electron probe microanalysis of a fuel pellet. The local xenon concentration of a pulse-irradiated pellet decreased compared with that of a base-irradiated pellet in the relative radius range of 0 to approximately 0.8. The decrease in local xenon concentration corresponded to a fractional fission gas release of approximately 11%, and this value was comparable to the rod-puncture test result after pulse irradiation. Considering the microstructural change of the fuel pellet and the amount of gas retained in the grain boundary, it is likely that the fission gas release during pulse irradiation was affected by grain boundary separation, which occurred near the midradius rather than near the peripheral region of the fuel pellet during pulse irradiation. (author)

Additional details

Identifiers

DOI
10.1080/18811248.2008.9711451;

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
45
Journal Issue
5
Journal Page Range
p. 423-431
ISSN
0022-3131

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
53077022
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; BWR TYPE REACTORS; ELECTRON MICROPROBE ANALYSIS; FISSION PRODUCT RELEASE; FUEL PELLETS; FUEL RODS; GRAIN BOUNDARIES; NSRR REACTOR; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; PULSED IRRADIATION; REACTIVITY; REACTOR ACCIDENT SIMULATION; XENON
Descriptors DEC
CHEMICAL ANALYSIS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; FUELS; GASES; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION; MATERIALS; MICROANALYSIS; MICROSTRUCTURE; MIXED SPECTRUM REACTORS; NONDESTRUCTIVE ANALYSIS; NONMETALS; PELLETS; POWER REACTORS; PULSED REACTORS; RARE GASES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
21 refs., 10 figs., 2 tabs.; This record replaces 39068102