Published 1977 | Version v1
Book Metadata-only

Electron-microscopy of fuel claddings from 0Cr16Ni15Mo3Nb stainless steel irradiated in the Reactor BOR-60 to burn-up 6.12 and 10.8%

Creators

Description

Fuel cladding samples from OCr16Ni15Mo3Nb stainless steel have been examined after irradiation in the Reactor BOR-60 to the fluences 4.2 x 1022 and 6.6 x 1022 n/cm2, E > or = 0.1 MeV. Voids, dislocation loops and precipitates are found. It is established that maximum swelling observed near approximately 5000C is equal to 6.5%. Intergranular M23C6 precipitates and intragranular fine dispersed Nb(C,N) and Laves phase type Fe2(Mo, Nb) precipitates due to radiation-induced diffusion are found

Additional details

Publishing Information

Publisher
American Institute of Mining, Metallurgical, and Petroleum Engineers, Inc.
Imprint Place
New York
Imprint Title
Radiation effects in breeder reactor structural materials
Journal Page Range
p. 613-624.

Conference

Title
Conference on radiation effects in breeder reactor structural materials.
Dates
19 - 23 Jun 1977.
Place
Scottsdale, AZ, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10449618
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOR-60 REACTOR; CHROMIUM-NICKEL STEELS; FUEL CANS; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; SWELLING
Descriptors DEC
ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; DEFORMATION; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STEELS; TRANSITION ELEMENT ALLOYS