RECOVERY OF TRITIUM FROM ZIRCALOY-CLAD UO2 FUEL-RODS

被引：0

|

作者：

WOLFLE, R

KNIEPER, J

STOCKLIN, G

机构：

来源：

RADIOCHIMICA ACTA | 1981年 / 29卷 / 2-3期

关键词：

D O I：

暂无

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

引用

收藏

页码：153 / 157

页数：5

相关论文

共 50 条

[31] FISSION-PRODUCT BEHAVIOR IN INTACT UO2 FUEL-RODS - REVIEW OF STUDSVIK EXPERIMENTAL RESULTS
BLACKADDER, WH
FORSYTH, RS
MALEN, K
AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 392 - 392
[32] EFFECTS OF UO2 ZIRCALOY-4 MOLE RATIOS ON REACTION OF UO2 FUEL WITH MOLTEN ZIRCALOY-4
MOK, YK
YOON, YK
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1994, 31 (05) : 432 - 442
[33] FAILURE MODES OF ZIRCALOY-CLAD FUEL RODS - TASK-3 - EFFECT OF DIMENSIONAL CHANGES ON COOLING EFFICIENCY
RITTENHO.PL
NUCLEAR SAFETY, 1972, 13 (01): : 62 - +
[34] ONE AND 2 DIMENSION ANALYSIS OF THE CLAD BALLOONING IN PRESSURIZED FUEL-RODS
LERIDON, A
NUCLEAR ENGINEERING AND DESIGN, 1980, 61 (01) : 143 - 149
[35] KINETICS OF PORE MOVEMENT IN UO2 FUEL RODS
SENS, PF
JOURNAL OF NUCLEAR MATERIALS, 1972, 43 (03) : 293 - &
[36] TRANSIENT THERMAL CHARACTERISTICS OF UO2 FUEL RODS
NAGAI, M
KAWAI, T
HORI, M
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-TOKYO, 1969, 6 (09): : 494 - &
[37] ZIRCALOY-UO2 AND ZIRCALOY-WATER REACTIONS AND CLADDING TEMPERATURE ESTIMATION FOR RAPIDLY-HEATED FUEL-RODS UNDER AN RIA CONDITION
SHIOZAWA, S
SAITO, S
YANAGIHARA, S
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1982, 19 (05) : 368 - 383
[38] BONDING BETWEEN UO2 FUEL AND ZIRCALOY-2 CLADDING
ROMEO, G
WOLFF, UE
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 213 - 214
[39] CLADDING CORROSION AND HYDRIDING IN IRRADIATED DEFECTED ZIRCALOY FUEL-RODS
CLAYTON, JC
CORROSION, 1989, 45 (12) : 996 - 1002
[40] EFFECT OF ZIRCALOY-CLAD FUEL ROD FAILURE ON BWR CORE SPRAY COOLING
BOCK, RG
DUNCAN, JD
LEONARD, JE
NUCLEAR TECHNOLOGY, 1971, 11 (04) : 532 - &

← 1 2 3 4 5 →