Published January 1984 | Version v1
Report Metadata-only

PFM - the Westinghouse probabilistic fracture mechanics computer program

Creators

Description

Westinghouse Electric Corporation has developed a multi-purpose probabilistic fracture mechanics computer program designated PFM which is especially oriented toward the evaluation of reactor vessels subjected to transient loads and irradiation induced material toughness degradation. The capabilities of the program are described, applications are briefly summarized and the continuing development is outlined

Additional details

Publishing Information

Imprint Title
Proceedings of the eleventh water reactor safety research information meeting. Volume 4
Journal Page Range
p. 405-406.
Report number
NUREG/CP--0048-Vol.4

Conference

Title
11. NRC water reactor safety research information meeting.
Dates
14-24 Oct 1983.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16007022
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; COPPER; DEFECTS; ELASTICITY; EMBRITTLEMENT; FAILURES; FRACTURE MECHANICS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MONTE CARLO METHOD; NEUTRON FLUENCE; PHOSPHORUS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; PROBABILITY; PWR TYPE REACTORS; REACTOR SAFETY; RESEARCH PROGRAMS; STRESS INTENSITY FACTORS; THERMAL SHOCK; TRANSIENTS
Descriptors DEC
ACCIDENTS; CONTAINERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; MECHANICS; METALS; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS