Temper and neutron irradiation embrittlement in 2 1/4 Cr-1 Mo steels for pressure vessels of high-temperature gas-cooled reactors
A 2 1/4 Cr-1 Mo steel is a promising candidate material for structural components of the pressure vessel of the experimental very high temperature gascooled reactor (VHTR) in Japan. Since the service temperature of such components is expected to be about 400/sup 0/C, the behavior of the temper and neutron irradiation embrittlements in these chromium-molybdenum steels should be confirmed from the viewpoint of structural integrity. The experimental verification on the degree of the embrittlement due to thermal aging, including the effect of applied stress and neutron irradiation, is described. Steel containing substantial amounts (about 100 ppm) of phosphorus atoms, which are believed to cause the temper embrittlement, showed that applied stress enhanced the embrittlement due to thermal aging. Embrittlement caused by neutron irradiation appears to be minimal in the case of the material containing <1000 ppm of copper as impurity with neutrons irradiated at about 400/sup 0/C.
- Research Organization:
- Japan Atomic Energy Research Institute High Temperature Engineering Division, Shirakata Tokai-mura, Ibaraki
- OSTI ID:
- 6216445
- Journal Information:
- Nucl. Technol.; (United States), Vol. 66:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CHROMIUM-MOLYBDENUM STEELS
DAMAGING NEUTRON FLUENCE
EMBRITTLEMENT
THERMAL DEGRADATION
HTGR TYPE REACTORS
REACTOR MATERIALS
PRESSURE VESSELS
COPPER
HIGH TEMPERATURE
IMPURITIES
IRRADIATION
MATERIALS TESTING
PHOSPHORUS
PHYSICAL RADIATION EFFECTS
STRESSES
TEMPERATURE EFFECTS
VHTR REACTOR
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CONTAINERS
ELEMENTS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
NEUTRON FLUENCE
NONMETALS
POWER REACTORS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
STEELS
TESTING
THERMAL REACTORS
TRANSITION ELEMENTS
360106* - Metals & Alloys- Radiation Effects
210300 - Power Reactors
Nonbreeding
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