Published 1983 | Version v1
Book Metadata-only

Post-irradiation creep rupture properties of the 12% chromium martensitic steels 1.4914 and 1.4923

Creators

  • 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)

Description

Specimens of the tempered martensitic 12% chromium steels DIN 1.4914 (Nb-stabilized) and DIN 1.4923 were irradiated at 600 deg C in the mixed thermal-fast flux of the BR2-reactor at Mol up to 1.05 x 1026 n/m2 (E > 0.1 MeV). Post-irradiation creep tests were carried out between 600 and 895 deg C with 1.4914 and at 600 deg C with 1.4923. The results are compared with those of specimens thermally aged to simulate the heat exposure during irradiation. A low susceptibility of this class of steels to high temperature (helium) embrittlement even after long time creep exposure was found. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London (UK)
ISBN
0 7277 0175 4
Imprint Title
Dimensional stability and mechanical behaviour of irradiated metals and alloys. V. 1
Imprint Pagination
223 p.
Journal Page Range
p. 161-164.

Conference

Title
Dimensional stability and mechanical behaviour of irradiated metals and alloys conference.
Dates
11-13 Apr 1983.
Place
Brighton (UK).

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
15066864
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; BR-2 REACTOR; CHROMIUM STEELS; CREEP; DUCTILITY; FRACTURE PROPERTIES; HEAT TREATMENTS; HIGH TEMPERATURE; MARTENSITIC STEELS; NIOBIUM ADDITIONS; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; TEMPERATURE DEPENDENCE; VERY HIGH TEMPERATURE
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEELS; TANK TYPE REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS