FIRST REPORT ON APPARATUS TO SIMULATE IN-REACTOR TRANSIENT HEATING CONDITIONS IN OXIDE FUEL COLUMNS

被引：21

作者：

WRONA, BJ ^{[1
]}

ROBERTS, JTA ^{[1
]}

JOHANSON, E ^{[1
]}

TUOHIG, WD ^{[1
]}

机构：

[1] ARGONNE NATL LAB,ARGONNE,IL 60439

来源：

NUCLEAR TECHNOLOGY | 1973年 / 20卷 / 02期

关键词：

D O I：

10.13182/NT73-A31347

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：

An apparatus has been developed that simulates, out-of-reactor, both in-reactor thermal gradients and heating rates in oxide fuel pellet stacks through direct electrical heating. Preliminary results of tests of both steady-state and transient operation indicate that fuel phenomena and fuel microstructures similar to those observed in actual in-reactor transients can be produced.

引用

页码：114 / 123

页数：10

共 6 条

[1] ELECTRICAL CONDUCTIVITY OF URANIUM DIOXIDE
BATES, JL
HINMAN, CA
KAWADA, T
[J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1967, 50 (12) : 652 - &
[2] CREEP BEHAVIOR OF CERAMIC NUCLEAR FUELS UNDER NEUTRON-IRRADIATION
BRUCKLACHER, D
DIENST, W
[J]. JOURNAL OF NUCLEAR MATERIALS, 1972, 42 (03) : 285 - +
[3] FREUND D, 1970, EURFNR773 KARLSR NUC
[4] HIKADO T, 1969, GEAP13543 GEN EL CO
[5] RADIATION-INDUCED CREEP OF UO2
SOLOMON, AA
[J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1973, 56 (03) : 164 - 171
[6] THOMAS GR, 1971, 1971 P INT C FAST RE, P679

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