AVAILABILITY OF A PRESSURIZED WATER-REACTOR PRESSURE-VESSEL AFTER A SMALL LOCA

被引：0

作者：

GOLSHANI, M ^{[1
]}

LOYALKA, SK ^{[1
]}

机构：

[1] UNIV MISSOURI,PROGRAM NUCL ENERGY,COLUMBIA,MO 65201

来源：

NUCLEAR ENGINEERING AND DESIGN | 1979年 / 52卷 / 01期

关键词：

D O I：

10.1016/0029-5493(79)90006-2

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：59 / 66

页数：8

共 50 条

[31] SAFEGUARDING CONTAINMENT BY REACTOR PRESSURE-VESSEL
KUSSMAUL, K
ATOMWIRTSCHAFT-ATOMTECHNIK, 1978, 23 (7-8): : 354 - 361
[32] TRANSPORTATION OF SHIPPINGPORT REACTOR PRESSURE-VESSEL
DUERR, D
JOURNAL OF CONSTRUCTION ENGINEERING AND MANAGEMENT-ASCE, 1991, 117 (03): : 551 - 564
[33] REACTOR PRESSURE-VESSEL DESIGN AND PRACTICE
BANGASH, Y
PROGRESS IN NUCLEAR ENERGY, 1982, 10 (01) : 69 - 124
[34] LIFT OF SHIPPINGPORT REACTOR PRESSURE-VESSEL
DUERR, D
JOURNAL OF CONSTRUCTION ENGINEERING AND MANAGEMENT-ASCE, 1990, 116 (01): : 188 - 197
[35] REACTOR PRESSURE-VESSEL AGING AND COUNTERMEASURES
LEITZ, C
KERNTECHNIK, 1987, 51 (04) : 256 - 258
[36] INVESTIGATION ON CYCLIC CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEELS PLACED AND LOADED IN THE CORE REGION OF AN OPERATING BOILING WATER-REACTOR
ANDERS, D
FOHL, J
NUCLEAR ENGINEERING AND DESIGN, 1992, 136 (03) : 265 - 276
[37] CRACK INITIATION AND ARREST IN A PRESSURIZED THERMAL-SHOCK TEST FOR A MODEL PRESSURE-VESSEL MADE OF VVER-440 REACTOR PRESSURE-VESSEL STEEL
KEINANEN, H
TALJA, H
RINTAMAA, R
TORRONEN, K
AHLSTRAND, R
NURKKALA, P
KARZOV, G
TIMOFEEV, B
BLUMIN, A
NUCLEAR ENGINEERING AND DESIGN, 1995, 158 (2-3) : 217 - 226
[38] AN EVALUATION OF PRESSURIZED WATER-REACTOR FREQUENT REFUELING
BERNSTEIN, I
GREACEN, JS
MATZIE, RA
MILLER, DD
NUCLEAR TECHNOLOGY, 1982, 56 (03) : 516 - 526
[39] THORIUM UTILIZATION IN AN UNMODIFIED PRESSURIZED WATER-REACTOR
GUNGOR, S
ANNALS OF NUCLEAR ENERGY, 1990, 17 (08) : 455 - 459
[40] PASSIVE CONTAINMENT COOLING OF A PRESSURIZED WATER-REACTOR
SEIFRITZ, W
KERNENERGIE, 1991, 34 (7-8): : 353 - 353

← 1 2 3 4 5 →