GRABB - A COMPUTER CODE FOR SIMULATING FISSION-GAS DISPOSITION IN OXIDE FUEL DURING FAST THERMAL TRANSIENT

被引：2

作者：

CHIEN, SH ^{[1
]}

WAZZAN, AR ^{[1
]}

OKRENT, D ^{[1
]}

机构：

[1] UNIV CALIF LOS ANGELES,SCH ENGN & APPL SCI,DEPT CHEM NUCL & THERMAL ENGN,LOS ANGELES,CA 90024

来源：

NUCLEAR TECHNOLOGY | 1983年 / 60卷 / 01期

关键词：

D O I：

10.13182/NT83-A33103

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：

引用

页码：69 / 83

页数：15

共 50 条

[31] MODELING TRANSIENT FISSION GAS RELEASE FROM OXIDE FUEL
GRUBER, EE
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 18 (JUN23): : 126 - 126
[32] MODEL TO DESCRIBE ROLE OF NONEQUILIBRIUM INTRAGRANULAR FISSION-GAS BUBBLES DURING TRANSIENT HEATING
WOOD, MH
JOURNAL OF NUCLEAR MATERIALS, 1978, 78 (01) : 58 - 63
[33] SIMULATION OF THE EFFECTS OF GRAIN-BOUNDARY FISSION-GAS DURING THERMAL TRANSIENTS
FENSKE, GR
EMERSON, JE
BEIERSDORF, BA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 278 - 280
[34] THE PREDICTION OF TRANSIENT FISSION-GAS RELEASE AND FUEL MICROCRACKING UNDER SEVERE CORE-ACCIDENT CONDITIONS
REST, J
NUCLEAR TECHNOLOGY, 1982, 56 (03) : 553 - 564
[35] MODELING FISSION-GAS BEHAVIOR IN MIXED-OXIDE FUEL UNDER NORMAL AND OFF-NORMAL CONDITIONS IN FAST-REACTORS
VATH, L
JOURNAL OF NUCLEAR MATERIALS, 1992, 188 : 308 - 311
[36] ROLE OF FISSION-GAS AND FUEL MELTING IN FUEL RESPONSE DURING SIMULATED HYPOTHETICAL LOSS-OF-FLOW TRANSIENTS
BANDYOPADHYAY, G
BUZZELL, JA
NUCLEAR TECHNOLOGY, 1980, 47 (01) : 91 - 109
[37] FISSION-GAS RELEASE FROM PYROLYTIC-CARBON-COATED FUEL PARTICLES DURING IRRADIATION
REAGAN, PE
CARLSEN, FL
CARROLL, RM
NUCLEAR SCIENCE AND ENGINEERING, 1964, 18 (03) : 301 - &
[38] BEHAVIOR OF FISSION-GAS IN LWR FUEL DURING STEADY-STATE OPERATING-CONDITIONS
REST, J
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 171 - 172
[39] PREDICTION OF TRANSIENT FISSION-GAS RELEASE AND FUEL MICROCRACKING UNDER SEVERE CORE-ACCIDENT CONDITIONS.
Rest, J.
Nuclear Technology, 1981, 56 (03) : 553 - 564
[40] MODELS OF FISSION-GAS BEHAVIOR IN FAST-REACTOR FUELS UNDER STEADY-STATE AND TRANSIENT CONDITIONS
HAYNS, MR
WOOD, MH
JOURNAL OF NUCLEAR MATERIALS, 1977, 67 (1-2) : 155 - 170

← 1 2 3 4 5 →