A RETRAN ANALYSIS OF CALVERT CLIFFS FEED-AND-BLEED CAPABILITY

被引：0
|
作者：
COOK, TL [1 ]
MIRSKY, SM [1 ]
KEY, MC [1 ]
机构：
[1] BALTIMORE GAS & ELECT CO, BALTIMORE, MD 21203 USA
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1984年 / 47卷
关键词：
D O I：
暂无
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
收藏
页码：505 / 507
页数：3
相关论文
共 31 条
  • [1] AN ANALYSIS OF FEED-AND-BLEED COOLING OF A PRESSURIZED WATER-REACTOR
    MIN, L
    WU, JH
    NUCLEAR TECHNOLOGY, 1992, 98 (03) : 289 - 306
  • [2] AN ANALYSIS OF A FEED-AND-BLEED MODE OF PWR EMERGENCY CORE COOLING
    SALAMEALFIE, A
    LAHEY, RT
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 468 - 469
  • [3] EVALUATION OF PRIMARY FEED-AND-BLEED COOLING CAPABILITY OF PRESSURIZED WATER-REACTOR SYSTEMS
    PWU, LC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 85 - 86
  • [4] FEED-AND-BLEED OPERATION AT RANCHO-SECO
    WHITNEY, DD
    ANDERSON, SI
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 65 - 66
  • [5] AN ASSESSMENT OF THE UTILITY OF FEED-AND-BLEED OPERATING MAPS
    BOYACK, BE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 263 - 265
  • [6] Dynamic sequence analysis for feed-and-bleed operation in an OPR1000
    Kim, Bo Gyung
    Yoon, Ho Joon
    Kim, Sang Ho
    Kang, Hyun Gook
    ANNALS OF NUCLEAR ENERGY, 2014, 71 : 361 - 375
  • [7] Advanced operation strategy for feed-and-bleed operation in an OPR1000
    Kim, Bo Gyung
    Yoon, Ho Joon
    Kim, Jaewhan
    Kang, Hyun Gook
    ANNALS OF NUCLEAR ENERGY, 2016, 90 : 32 - 43
  • [8] HUMAN RELIABILITY ANALYSIS FOR STEAM GENERATOR FEED-AND-BLEED ACCIDENT IN A TYPICAL VVER POWER PLANT
    Yousefi, Mohammad
    Jafarian, Reza
    CONTEMPORARY ERGONOMICS AND HUMAN FACTORS 2011, 2011, : 502 - 508
  • [9] SECONDARY-SIDE FEED-AND-BLEED EFFECTIVENESS IN PRESSURIZED-WATER REACTORS
    ANNUNZIATO, A
    NUCLEAR TECHNOLOGY, 1994, 105 (03) : 301 - 321
  • [10] TRAC-PF1 FEED-AND-BLEED CALCULATIONS FOR TMI-1
    HENNINGER, RJ
    DEMUTH, NS
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 45 : 469 - 471
1234