Fission product release behavior of individual coated fuel particles for high-temperature gas-cooled reactors

被引:55
作者
Minato, K [1 ]
Sawa, K
Koya, T
Tomita, T
Ishikawa, A
Baldwin, CA
Gabbard, WA
Malone, CM
机构
[1] Japan Atom Energy Res Inst, Tokai, Ibaraki 3191195, Japan
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
D O I
10.13182/NT00-A3103
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Postirradiation heating tests of TRISO-coated UO2 particles at 1700 and 1800 degrees C were performed to understand fission product release behavior at accident temperatures. The inventory measurements of the individual particles were carried out before and after the heating rests with gamma-ray spectrometry to study the behavior of the individual particles. The time-dependent release behavior of Kr-85, Ag-110m, Cs-134, Cs-137, and Eu-154 were obtained with on-line measurements of fission gas release and intermittent measurements of metallic fission product release during the heating tests. The inventory measurements of the individual particles revealed that fission product release behavior of the individual particles was not uniform, and large particle-to-particle variations in the release behavior of Ag-110, Cs-134, Cs-137, and Eu-154 were found X-my microradiography and ceramography showed that the variations could not be explained by only the presence or absence of cracks in the SiC coating layer The SiC degradation may have been related to the variations.
引用
收藏
页码:36 / 47
页数:12
相关论文
共 18 条
[11]   A MODEL TO PREDICT THE ULTIMATE FAILURE OF COATED FUEL-PARTICLES DURING CORE HEATUP EVENTS [J].
OGAWA, T ;
MINATO, K ;
FUKUDA, K ;
NUMATA, M ;
MIYANISHI, H ;
SEKINO, H ;
MATSUSHIMA, H ;
ITOH, T ;
KADO, S ;
TAKAHASHI, I .
NUCLEAR TECHNOLOGY, 1991, 96 (03) :314-322
[12]  
Saito S., 1994, JAERI, V1332
[13]   HIGH-TEMPERATURE REACTOR-FUEL FISSION-PRODUCT RELEASE AND DISTRIBUTION AT 1600-DEGREES-C TO 1800-DEGREES-C [J].
SCHENK, W ;
NABIELEK, H .
NUCLEAR TECHNOLOGY, 1991, 96 (03) :323-336
[14]   FUEL ACCIDENT PERFORMANCE TESTING FOR SMALL HTRS [J].
SCHENK, W ;
POTT, G ;
NABIELEK, H .
JOURNAL OF NUCLEAR MATERIALS, 1990, 171 (01) :19-30
[15]  
SCHENK W, 1989, KUGELBRENNELEMENTE T
[16]  
VALENTINE KH, 1979, ORNLTM6576
[17]   PASSIVE SAFETY CHARACTERISTICS OF FUEL FOR A MODULAR HIGH-TEMPERATURE REACTOR AND FUEL PERFORMANCE MODELING UNDER ACCIDENT CONDITIONS [J].
VERFONDERN, K ;
SCHENK, W ;
NABIELEK, H .
NUCLEAR TECHNOLOGY, 1990, 91 (02) :235-246
[18]  
ZHONG D, 1995, P IAEA TECHN COMM M, P11