Temper and neutron irradiation embrittlement in 2 1/4 Cr-1 Mo steels for pressure vessels of high-temperature gas-cooled reactors
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6216445
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), Journal Name: Nucl. Technol.; (United States) Vol. 66:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CONTAINERS
COPPER
DAMAGING NEUTRON FLUENCE
ELEMENTS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HIGH TEMPERATURE
HTGR TYPE REACTORS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
METALS
NEUTRON FLUENCE
NONMETALS
PHOSPHORUS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
STEELS
STRESSES
TEMPERATURE EFFECTS
TESTING
THERMAL DEGRADATION
THERMAL REACTORS
TRANSITION ELEMENTS
VHTR REACTOR
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CONTAINERS
COPPER
DAMAGING NEUTRON FLUENCE
ELEMENTS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HIGH TEMPERATURE
HTGR TYPE REACTORS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
METALS
NEUTRON FLUENCE
NONMETALS
PHOSPHORUS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
STEELS
STRESSES
TEMPERATURE EFFECTS
TESTING
THERMAL DEGRADATION
THERMAL REACTORS
TRANSITION ELEMENTS
VHTR REACTOR