Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1

Conference · Tue Feb 01 00:00:00 EST 1983

OSTI ID:6103258

Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

• Research Organization: American Nuclear Society, Chicago, IL
• OSTI ID: 6103258
• Report Number(s): NUREG/CP-0027.Vol.1; CONF-820802-Vol.1; ON: DE83901497
• Resource Relation: Conference: International meeting on thermal nuclear reactor safety (ANS topical meeting), Chicago, IL, USA, 29 Aug 1982; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
CANDU TYPE REACTORS
HTGR TYPE REACTORS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
MEETINGS
ENVIRONMENTAL IMPACTS
HUMAN FACTORS
LEADING ABSTRACT
MAN-MACHINE SYSTEMS
RADIATION PROTECTION
REACTOR ACCIDENTS
RELIABILITY
RISK ASSESSMENT
ABSTRACTS
ACCIDENTS
DOCUMENT TYPES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAVY WATER MODERATED REACTORS
NUCLEAR FACILITIES
POWER PLANTS
PRESSURE TUBE REACTORS
REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 - Power Reactors
Nonbreeding
Graphite Moderated
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated