Published September 1992 | Version v1
Journal article Metadata-only

Effect of neutron irradiation on the strength of electron beam welded JFMS steel

Creators

  • 1. Central Research Lab., Osaka Inst. of Technology (Japan)
  • 2. College of Integrated Arts and Sciences, Univ. of Osaka Prefecture, Nakamozu (Japan)
  • 3. Dept. of Mechanical Engineering, Osaka Inst. of Technology (Japan)

Description

Japanese ferritic-martensitic steel (JFMS) is a candidate material for nuclear fusion reactor application. It is a material for high temperature use. Structural materials of the fusion reactor will be exposed to neutron irradiation. In order to research the fundamental properties of the material under irradiation, low temperature strength of JFMS steel and its electron beam welded joints were investigated under various irradiated conditions in this experiment. It was shown that strength decreases at low temperature in the base metal and, in electron beam welded joints of JFMS steel, increases with increasing neutron fluence. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
191-194
Journal Issue
pt.B
Journal Page Range
p. 901-904.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
5. international conference on fusion reactor materials (ICFRM-5).
Dates
17-22 Nov 1991.
Place
Clearwater, FL (United States).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
24031658
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
CHEMICAL COMPOSITION; ELECTRON BEAM WELDING; ELONGATION; EXPERIMENTAL DATA; FERRITIC STEELS; FISSION NEUTRONS; KUR REACTOR; MARTENSITIC STEELS; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; TEMPERATURE RANGE 0000-0013 K; TEMPERATURE RANGE 0065-0273 K; TEMPERATURE RANGE 0273-0400 K; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIAL; ULTIMATE STRENGTH; WELDED JOINTS; YIELD STRENGTH
Descriptors DEC
ALLOYS; BARYONS; CARBON ADDITIONS; DATA; DEFORMATION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FABRICATION; FERMIONS; HADRONS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINING; JOINTS; MATERIALS; MECHANICAL PROPERTIES; NEUTRONS; NUCLEONS; NUMERICAL DATA; POOL TYPE REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STEELS; TEMPERATURE RANGE; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WELDING