Published 1977 | Version v1
Report Metadata-only

Brittleness. Presupposition (criteria) for reactor vessel brittle fracture

Creators

  • 1. Babcock - Brown Boveri Reaktor G.m.b.H., Mannheim (Germany, F.R.)

Description

Safety approaches and criteria related to reactor pressure vessels as well as the applicability of fracture mechanics concepts are discussed. (author)

Additional details

Publishing Information

Imprint Title
Reactor pressure vessel surveillance
Journal Page Range
p. 139-161.
Report number
IAEA--202

Conference

Title
Technical committee meeting on reactor pressure vessel surveillance.
Dates
17 - 18 May 1976.
Place
Plzen, Czechoslovakia.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
9376424
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHARPY TEST; CRACKS; DUCTILE-BRITTLE TRANSITIONS; FRACTURE PROPERTIES; IRRADIATION; NEUTRON FLUX; REACTOR VESSELS; TRANSITION TEMPERATURE
Descriptors DEC
CONTAINERS; DESTRUCTIVE TESTING; IMPACT TESTS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; PHYSICAL PROPERTIES; RADIATION FLUX; TESTING; THERMODYNAMIC PROPERTIES