Published July 1988 | Version v1
Journal article Metadata-only

Post irradiation tensile and fatigue behavior of austenitic PCA stainless steels irradiated in HFIR

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Dept. of Fuels and Materials Research
  • 2. Oak Ridge National Lab., TN (USA). Metals and Ceramics Div.

Description

Mechanical properties were determined on solution annealed (SA) and cold worked (CW) JPCA (Ti-modified austenitic stainless steel) irradiated in the High Flux Isotope Reactor (HFIR) at temperatures ranging from 300 to 6000C. The irradiation produced damage levels from 16 to 56 dpa and helium concentration from 1020 to 4100 appm. The improved stability of MC precipitates which formed in the matrix during irradiation prevent loss of ductility at 5000C and below. Application of solution annealed JPCA is recommended for structural components of fusion reactors to be operated at 5000C and below. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
155-157
Journal Issue
pt.B
Series
J. Nucl. Mater.
Journal Page Range
957-962
ISSN
0022-3115
CODEN
JNUMA

Conference

Title
3. international conference on fusion reactor materials (ICFRM-3).
Dates
4-8 Oct 1987.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
20010016
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ATOMIC DISPLACEMENTS; AUSTENITIC STEELS; CARBIDES; CHEMICAL COMPOSITION; COLD WORKING; DUCTILITY; ELONGATION; EXPERIMENTAL DATA; FAST NEUTRONS; FATIGUE; FRACTOGRAPHY; HFIR REACTOR; HIGH TEMPERATURE; MECHANICAL PROPERTIES; NEUTRON FLUENCE; PARTICLE SIZE; PHYSICAL RADIATION EFFECTS; SCANNING ELECTRON MICROSCOPY; SWELLING; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIAL; TITANIUM ADDITIONS; YIELD STRENGTH
Descriptors DEC
ALLOYS; BARYONS; CARBON ADDITIONS; CARBON COMPOUNDS; DATA; DEFORMATION; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FABRICATION; FERMIONS; HADRONS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS WORKING; MICROSCOPY; NEUTRONS; NUCLEONS; NUMERICAL DATA; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIZE; STEELS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS