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Title: Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors

Abstract

The ZrC coating layer is a candidate to replace the SiC coating layer of the Triso-coated fuel particle. To compare the irradiation performance of the ZrC Triso-coated fuel particles with that of the normal Triso-coated fuel particles at high temperatures, a capsule irradiation experiment was performed, where both types of the coated fuel particles were irradiated under identical conditions. The burnup was 4.5% FIMA and the irradiation temperature was 1,400 to 1,650 C. The postirradiation measurement of the through-coating failure fractions of both types of coated fuel particles revealed better irradiation performance of the ZrC Triso-coated fuel particles. The optical microscopy and electron probe microanalysis on the polished cross section of the ZrC Triso-coated fuel particles revealed no interaction of palladium with the ZrC coating layer nor accumulation of palladium at the inner surface of the ZrC coating layer, whereas severe corrosion of the SiC coating layer was observed in the normal Triso-coated fuel particles. Although no corrosion of the ZrC coating layer was observed, additional evaluations need to be made of this layer's ability to satisfactorily retain the fission product palladium.

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Japan Atomic Energy Research Inst., Ibaraki (JP)
OSTI Identifier:
20067741
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 130; Journal Issue: 3; Other Information: PBD: Jun 2000; Journal ID: ISSN 0029-5450
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ZIRCONIUM CARBIDES; COATED FUEL PARTICLES; MATERIAL SUBSTITUTION; BURNUP; POST-IRRADIATION EXAMINATION; PHYSICAL RADIATION EFFECTS; HTGR TYPE REACTORS

Citation Formats

Minato, Kazuo, Ogawa, Toru, Sawa, Kazuhiro, Ishikawa, Akiyoshi, Tomita, Takeshi, Iida, Shozo, and Sekino, Hajime. Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors. United States: N. p., 2000. Web.
Minato, Kazuo, Ogawa, Toru, Sawa, Kazuhiro, Ishikawa, Akiyoshi, Tomita, Takeshi, Iida, Shozo, & Sekino, Hajime. Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors. United States.
Minato, Kazuo, Ogawa, Toru, Sawa, Kazuhiro, Ishikawa, Akiyoshi, Tomita, Takeshi, Iida, Shozo, and Sekino, Hajime. Thu . "Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors". United States.
@article{osti_20067741,
title = {Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors},
author = {Minato, Kazuo and Ogawa, Toru and Sawa, Kazuhiro and Ishikawa, Akiyoshi and Tomita, Takeshi and Iida, Shozo and Sekino, Hajime},
abstractNote = {The ZrC coating layer is a candidate to replace the SiC coating layer of the Triso-coated fuel particle. To compare the irradiation performance of the ZrC Triso-coated fuel particles with that of the normal Triso-coated fuel particles at high temperatures, a capsule irradiation experiment was performed, where both types of the coated fuel particles were irradiated under identical conditions. The burnup was 4.5% FIMA and the irradiation temperature was 1,400 to 1,650 C. The postirradiation measurement of the through-coating failure fractions of both types of coated fuel particles revealed better irradiation performance of the ZrC Triso-coated fuel particles. The optical microscopy and electron probe microanalysis on the polished cross section of the ZrC Triso-coated fuel particles revealed no interaction of palladium with the ZrC coating layer nor accumulation of palladium at the inner surface of the ZrC coating layer, whereas severe corrosion of the SiC coating layer was observed in the normal Triso-coated fuel particles. Although no corrosion of the ZrC coating layer was observed, additional evaluations need to be made of this layer's ability to satisfactorily retain the fission product palladium.},
doi = {},
journal = {Nuclear Technology},
issn = {0029-5450},
number = 3,
volume = 130,
place = {United States},
year = {2000},
month = {6}
}