PROPERTIES OF SILICON-CARBIDE FOR NUCLEAR-FUEL PARTICLE COATINGS

被引:172
作者
PRICE, RJ [1 ]
机构
[1] GEN ATOM CO,SAN DIEGO,CA 92138
关键词
SILICON CARBIDE;
D O I
10.13182/NT77-A31892
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
The properties of pyrolytic silicon carbide (SiC) that are important to its use in nuclear fuel particle coatings are reviewed. The structure of material deposited under different conditions varies in growth features and the constituent phases; the principal effects of neutron irradiation on the structure are to create point defect clusters at irradiation temperatures below approximately 1000 C (1273 K) and voids above approximately 1000 C (1273 K), with a concomitant volume expansion. The thermal conductivity is greatly reduced by neutron irradiation.
引用
收藏
页码:320 / 336
页数:17
相关论文
共 64 条
[1]  
Alcock C. B., 1960, SPECIAL CERAMICS, P183
[2]   ACTIVE TO PASSIVE TRANSITION IN OXIDATION OF SIC [J].
ANTILL, JE ;
WARBURTON, JB .
CORROSION SCIENCE, 1971, 11 (06) :337-+
[3]   ZUR TEMPERATURABHANGIGKEIT DER STRAHLENSATTIGUNG IN SIC [J].
BALARIN, M .
PHYSICA STATUS SOLIDI, 1965, 11 (01) :K67-&
[4]   EFFECT OF FISSION-FRAGMENT IRRADIATION UPON OXIDATION OF SILICON CARBIDE BY OXYGEN AT 950 DEGREES C [J].
BENNETT, MJ ;
CHAFFEY, GH .
JOURNAL OF NUCLEAR MATERIALS, 1971, 39 (03) :253-&
[5]   EXPANSION OF SILICON CARBIDE BY NEUTRON IRRADIATION AT HIGH TEMPERATURE [J].
BLACKSTONE, R ;
VOICE, EH .
JOURNAL OF NUCLEAR MATERIALS, 1971, 39 (03) :319-+
[6]   MEASUREMENT OF YOUNGS MODULUS AND FRACTURE STRESS ON HTR PARTICLE COATINGS BY BRITTLE RING TEST [J].
BONGARTZ, K ;
GYARMATI, E ;
NICKEL, H ;
SCHUSTER, H ;
WINTER, W .
JOURNAL OF NUCLEAR MATERIALS, 1972, 45 (03) :261-264
[7]  
BONNKE M, 1966, BER DTSCH KERAM GES, V43, P180
[8]  
BRAMMAN JI, 1969, TRG1911 UK AT EN AUT
[9]  
CHIN J, 1976, GAA13845 GEN AT CO
[10]  
CHINAGLIA B, 1972, DP805 UK AT EN EST H