Published August 2007 | Version v1
Journal article Metadata-only

Preliminary test results for post irradiation examination on the HTTR fuel

Creators

  • 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
  • 2. Japan Atomic Power Co., Tokai, Ibaraki (Japan)

Description

The future post-irradiation program for the first-loading fuel of the HTTR is scheduled using the HTTR fuel handling facilities and the Hot Laboratory in the Japan Materials Testing Reactor (JMTR) to confirm its irradiation resistance and to obtain data on its irradiation characteristics in the core. This report describes the preliminary test results and the future plan for a post-irradiation examination for the HTTR fuel. In the preliminary test, fuel compacts made with the same SiC-coated fuel particle as the first loading fuel were used. In the preliminary test, dimension, weight, fuel failure fraction, and burnup were measured, and X-ray radiograph, SEM, and EPMA observations were carried out. Finally, it was confirmed that the first-loading fuel of the HTTR showed good quality under an irradiation condition. The future plan for the post-irradiation tests was described to confirm its irradiation performance and to obtain data on its irradiation characteristics in the HTTR core. (author)

Additional details

Identifiers

DOI
10.1080/18811248.2007.9711349;

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
44
Journal Issue
8
Journal Page Range
p. 1081-1088
ISSN
0022-3131

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
53076936
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; CERAMOGRAPHY; COATED FUEL PARTICLES; ELECTRON MICROPROBE ANALYSIS; FAILURES; FUEL INTEGRITY; HTTR REACTOR; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; SCANNING ELECTRON MICROSCOPY; X-RAY RADIOGRAPHY
Descriptors DEC
CHEMICAL ANALYSIS; ELECTRON MICROSCOPY; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INDUSTRIAL RADIOGRAPHY; MATERIALS; MATERIALS TESTING; MICROANALYSIS; MICROSCOPY; NONDESTRUCTIVE ANALYSIS; NONDESTRUCTIVE TESTING; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING

Optional Information

Notes
8 refs., 14 figs., 4 tabs.; This record replaces 39009905