AN UNCERTAINTY SENSITIVITY STUDY FOR THE STATION BLACKOUT SEQUENCE AT A MARK-I BOILING WATER-REACTOR

被引：6
|
作者：
HELTON, JC
JOHNSON, JD
机构：
[1] ARIZONA STATE UNIV,DEPT GEOG,TEMPE,AZ 85287
[2] SCI APPLICAT INT CORP,ALBUQUERQUE,NM 87102
来源：
RELIABILITY ENGINEERING & SYSTEM SAFETY | 1989年 / 26卷 / 04期
关键词：
D O I：
10.1016/0951-8320(89)90002-1
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
引用
收藏
页码：293 / 328
页数：36
相关论文
共 32 条
  • [21] TIME-DOMAIN MODEL SENSITIVITY IN BOILING WATER-REACTOR STABILITY ANALYSIS USING TRAC/BF1
    BORKOWSKI, JA
    ROBINSON, GE
    BARATTA, AJ
    KATTIC, M
    NUCLEAR TECHNOLOGY, 1993, 103 (01) : 34 - 48
  • [22] I-131 DISCHARGES FROM AN OPERATING BOILING WATER REACTOR NUCLEAR POWER STATION
    STIGALL, GE
    FOWLER, TW
    KRIEGER, HL
    HEALTH PHYSICS, 1971, 20 (06): : 593 - +
  • [23] BEHAVIOR OF RADIOACTIVE CORROSION PRODUCTS IN SYSTEM OF A CHANNEL-TYPE BOILING WATER-REACTOR OF A SINGLE-LOOP NUCLEAR-POWER STATION
    GRUZDEV, NI
    SHCHAPOV, GA
    BOGUSLAVSKII, VB
    PETUKHOV, YI
    THERMAL ENGINEERING, 1977, 24 (01) : 55 - 57
  • [24] COMPARATIVE-STUDY OF MEASUREMENT TECHNIQUES FOR COOLANT TRANSIT TIMES IN A BOILING WATER-REACTOR USING NOISE SIGNALS OF LPRMS
    JOSHI, SS
    ARORA, KK
    KOPARDE, RV
    PROGRESS IN NUCLEAR ENERGY, 1985, 15 (1-3) : 921 - 929
  • [25] A SENSITIVITY STUDY IN PROBABILISTIC FRACTURE-MECHANICS ANALYSIS OF LIGHT WATER-REACTOR CARBON-STEEL PIPE
    FUJIOKA, T
    KASHIMA, K
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1992, 52 (03) : 403 - 416
  • [26] Mass flow rate sensitivity and uncertainty analysis in natural circulation boiling water reactor core from Monte Carlo simulations
    Espinosa-Paredes, Gilberto
    Verma, Surendra P.
    Vazquez-Rodriguez, Alejandro
    Nunez-Carrera, Alejandro
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (05) : 1050 - 1062
  • [27] AN EXPERIMENTAL-STUDY OF BLOWDOWN THRUST AND JET FORCES FOR A PIPE UNDER BOILING WATER-REACTOR LOSS-OF-COOLANT ACCIDENT CONDITIONS
    YANO, T
    ISOZAKI, T
    UEDA, S
    MIYAZAKI, N
    KURIHARA, R
    KATO, R
    MIYAZONO, S
    NUCLEAR SCIENCE AND ENGINEERING, 1984, 88 (03) : 386 - 395
  • [28] A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor
    Chen, Yangli
    Zhang, Huimin
    Villanueva, Walter
    Ma, Weimin
    Bechta, Sevostian
    NUCLEAR ENGINEERING AND DESIGN, 2019, 343 : 22 - 37
  • [29] System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents
    Wu, Xu
    Shirvan, Koroush
    NUCLEAR ENGINEERING AND DESIGN, 2020, 356
  • [30] Nuclear Data Sensitivity and Uncertainty Study for the Pressurized Water Reactor (PWR) Benchmark Using RMC and SCALE
    Jin, Chengjian
    Liu, Shichang
    Zhang, Shenghao
    Liang, Jingang
    Chen, Yixue
    ENERGIES, 2022, 15 (24)
1234