CREEP LIMIT APPROACH TO DESIGN OF ZIRCALOY-2 REACTOR PRESSURE TUBES AT 275 DEGREES C

被引：25

|

作者：

WOOD, DS

WATKINS, B

机构：

来源：

JOURNAL OF NUCLEAR MATERIALS | 1971年 / 41卷 / 03期

关键词：

D O I：

10.1016/0022-3115(71)90170-X

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

下载

收藏

页码：327 / &

相关论文

共 50 条

[1] IN-REACTOR TUBULAR CREEP OF ZIRCALOY-2 AT 260 TO 300 DEGREES C
IBRAHIM, EF
JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (02) : 169 - 182
[2] EXTERNAL-PRESSURE CREEP OF ZIRCALOY-2 FUEL CLADDING TUBES
KUBO, T
OGUMA, M
HARA, T
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1981, 23 (07): : 530 - 536
[3] OUT-OF-REACTOR STUDY ON EXTERNAL-PRESSURE CREEP OF ZIRCALOY-2 FUEL CLADDING TUBES
MAKI, H
HARA, T
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1975, 12 (01) : 43 - 52
[4] ADDITIONAL CRACK PROPAGATION TESTS ON ZIRCALOY-2 REACTOR PRESSURE TUBES
AUNGST, RC
ELECTROCHEMICAL TECHNOLOGY, 1966, 4 (7-8): : 353 - &
[5] INFLUENCE OF NEUTRON IRRADIATION ON CREEP OF ZIRCALOY-2 AT 300 DEGREES C
FIDLERIS, V
WILLIAMS, CD
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1965, 112 (08) : C192 - &
[6] INFLUENCE OF NEUTRON IRRADIATION ON CREEP OF ZIRCALOY-2 AT 300 DEGREES C
FIDLERIS, V
WILLIAMS, CD
ELECTROCHEMICAL TECHNOLOGY, 1966, 4 (5-6): : 258 - &
[7] METALLURGICAL PROPERTIES OF ZIRCALOY-2 RELEVANT TO ITS USE IN REACTOR PRESSURE TUBES
HURST, P
NICHOLS, RW
PICKLES, B
WATKINS, B
WOOD, DS
ATOMIC ENERGY REVIEW, 1976, 14 (03) : 439 - 520
[8] IN-REACTOR CREEP OF COLD-WORKED ZIRCALOY-2 AND ZIRCONIUM-2.5 WT PERCENT NIOBIUM PRESSURE TUBES
ROSSROSS, PA
HUNT, CEL
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 2 - &
[9] FRACTURE AND TENSILE PROPERTIES OF IRRADIATED ZIRCALOY-2 PRESSURE TUBES
HUANG, FH
MILLS, WJ
NUCLEAR TECHNOLOGY, 1993, 102 (03) : 367 - 375
[10] ZIRCALOY-2 PRESSURE TUBE EXPERIENCE AT HANFORD N REACTOR
CARLSON, PA
RUSSELL, A
SCHMIDT, JP
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 16 (JUN): : 98 - 99

← 1 2 3 4 5 →