EXPERIMENTAL AND THERMODYNAMIC EVALUATION OF THE MELTING BEHAVIOR OF IRRADIATED OXIDE FUELS

被引：64

作者：

ADAMSON, MG

AITKEN, EA

CAPUTI, RW

机构：

[1] GE, Sunnyvale, CA, USA, GE, Sunnyvale, CA, USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1985年 / 130卷 / FEB期

关键词：

NUCLEAR REACTORS - Fission Products - THERMODYNAMICS;

D O I：

10.1016/0022-3115(85)90323-X

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Onset of melting is an important performance limit for irradiated UO//2 and UO//2 based nuclear reactor fuels. The principal focus in this paper is the influence of soluble and insoluble fission products on UO//2 and mixed (U,Pu)-oxide fuel melting behavior - specifically, on the fuel solidus temperature.

引用

页码：349 / 365

页数：17

共 37 条

[1] AITKEN EA, 1968, GEAP5672 GEN EL REP
[2] BAKER RB, 1979, P INT C FAST BREED R, P258
[3] MELTING POINT OF IRRADIATED URANIUM DIOXIDE
BATES, JL
[J]. JOURNAL OF NUCLEAR MATERIALS, 1970, 36 (02) : 234 - &
[4] BEHAVIOR OF URANIA-RARE-EARTH OXIDES AT HIGH TEMPERATURES
BEALS, RJ
HANDWERK, JH
WRONA, BJ
[J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1969, 52 (11) : 578 - &
[5] Chase M. W., 1975, Journal of Coordination Chemistry, V4, P1
[6] CHRISTENSEN JA, 1964, T AM NUCL SOC, V7, P390
[7] CHRISTENSEN JA, 1965, WCAP6065 US REP
[8] CHRISTENSEN JA, 1962, HW69234 US REP
[9] BINARY MIXTURES OF UO2 AND OTHER OXIDES
EPSTEIN, LF
HOWLAND, WH
[J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1953, 36 (10) : 334 - 335
[10] IDEAL SOLUTION BEHAVIOR AND HEATS OF FUSION FROM UO2-PUO2 PHASE DIAGRAM
EPSTEIN, LF
[J]. JOURNAL OF NUCLEAR MATERIALS, 1967, 22 (03) : 340 - &

← 1 2 3 4 →