FIRE PROTECTION CRITERIA FOR NUCLEAR FACILITIES

被引：0
|
作者：
PATTERSO.DE
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1970年 / 13卷 / 02期
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：840 / &
相关论文
共 50 条
  • [31] MANUAL FIRE PROTECTION SYSTEMS IN NUCLEAR DESIGN
    RIOPELLE, JH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 673 - 674
  • [32] ACCEPTANCE CRITERIA FOR DAMAGED AND REPAIRED PASSIVE FIRE PROTECTION
    Kerr, Diane
    Willoughby, Deborah
    Thurlbeck, Simon
    Connolly, Stephen
    HAZARDS XX: PROCESS SAFETY AND ENVIRONMENTAL PROTECTION: HARNESSING KNOWLEDGE - CHALLENGING COMPLACENCY, 2008, (154):
  • [33] PHYSICAL PROTECTION SAFEGUARDS FOR NUCLEAR-MATERIALS AND FACILITIES
    JONES, OE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 176 - 177
  • [34] Risk analysis and protection in case of intrusion of nuclear facilities
    Wadoud, Amir A.
    Saleh, Alaa A.
    Abdel-Rahman, Mohamed A. E.
    KERNTECHNIK, 2025,
  • [35] OPTIMIZATION OF RADIOLOGICAL PROTECTION AND THE DESIGN OF NUCLEAR-FACILITIES
    LOCHARD, J
    RADIATION PROTECTION DOSIMETRY, 1994, 53 (1-4) : 43 - 48
  • [36] Special issue on PRISME-Fire safety in nuclear facilities
    Audouin, Laurent
    Torero, Jose L.
    FIRE SAFETY JOURNAL, 2013, 62 : 79 - 79
  • [37] CRITERIA FOR THE PROTECTION OF THE PUBLIC IN THE EVENT OF A NUCLEAR EMERGENCY
    UTTING, RE
    HEALTH PHYSICS, 1983, 44 (06): : 714 - 714
  • [38] Consideration of Uncertainties in Analyzing Nuclear Power Facilities' Fire Hazard
    Vorobyev, Yu. B.
    Urtenov, D. S.
    Karnaukhov, V. E.
    Podgornyi, V. N.
    Lukashenko, M. L.
    THERMAL ENGINEERING, 2020, 67 (09) : 640 - 646
  • [39] Consideration of Uncertainties in Analyzing Nuclear Power Facilities’ Fire Hazard
    Yu. B. Vorobyev
    D. S. Urtenov
    V. E. Karnaukhov
    V. N. Podgornyi
    M. L. Lukashenko
    Thermal Engineering, 2020, 67 : 640 - 646
  • [40] Seismic design criteria for structures, systems, and components in nuclear facilities
    ASCE Standard, 2005, (43-5):
12345