Published October 1972 | Version v1
Journal article

Irradiation behavior of boron carbide

Description

Boron carbide is the prime candidate material for neutron absorbers in fast breeder reactors and the Fast Test Reactor. Important data required for design of control rods for these reactors concern swelling, gas release, and structural integrity of boron carbide under the expected operating conditions. Data for irradiations of boron carbide powders in a thermal reactor and powders and pellets in a fast reactor are presented and discussed in terms of expected performance in a fast reactor. The most important variable in determining irradiation behavior appears to be the mobility of the helium produced relative to the rate it is produced. The helium is not trapped in the lattice but precipitates. Denuded zones and absence of bubbles on grain boundaries suggest that helium diffuses rapidly along the grain boundaries. This is a major source of gas release.

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
16
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
226-237
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
4042749
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
BORON CARBIDES; FAST NEUTRONS; GASES; LATTICE PARAMETERS; LOSSES; MICROSTRUCTURE; RADIATION EFFECTS; STABILITY; SWELLING; THERMAL NEUTRONS
Descriptors DEC
BARYONS; BORON COMPOUNDS; CARBIDES; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; FERMIONS; FLUIDS; HADRONS; NEUTRONS; NUCLEONS

Optional Information

Notes
Updated automatically by Metadata and Full-Text Enrichment Agent