Simulating the CTR environment in the HVEM, 1981

Technical Report · Wed Jul 01 04:00:00 EDT 1981

OSTI ID:5475644

Jesser, W A

The problem of helium embrittlement and helium-microstructure interactions in a candidate first wall material, 316 stainless steel, continues to be of significant importance to the development of fusion energy. Recently there has been some interest developing in the possibility of utilizing ferritic alloys, however the main focus remains on the type 316 stainless steel. Employing microsamples for in-situ tensile testing is a viable means for obtaining qualitative, and semiquantitative information about the mechanisms of plastic deformation under conditions of embrittlement. The availability of the ion accelerator HVEM facility permits detailed observations to be made regarding the helium-microstructure interplay. The effects of helium on the development of radiation damage induced microstructural changes as well as the effects of preexisting microstructure on the distribution, and migration of helium can be elucidated.

• Research Organization: Virginia Univ., Charlottesville (USA). Dept. of Materials Science
• DOE Contract Number: AS05-76ET52023
• OSTI ID: 5475644
• Report Number(s): DOE/ET/52023-38; ON: DE85015811
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACCELERATORS
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
ELEMENTS
EMBRITTLEMENT
FLUIDS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEST FACILITIES
THERMONUCLEAR REACTOR MATERIALS