Evaluation of advanced reactor pressure vessel steels under neutron irradiation
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:5836151
- United Kingdom Atomic Energy Authority, London, England
The objective of the work described in this paper is to assess the radiation behavior of improved steels and weldments, produced in various countries. Three of the materials supplied by France and Japan to the IAEA program have been irradiated at 290 and/or 250/sup 0/C in the HERALD light water research reactor to assess the mechanical and upper shelf toughness properties after exposure to neutron fluences of approx. 1 x 10/sup 19/ n.cm/sup 2/ (E > 1 MeV). A fourth material, a weld supplied by the UK, has been included in the program for reference. Supplementary test methods used in the evaluation include hardness tests, chemical analyses, electron microscopy and positron annihilation. Results indicate that the improved steels are more resistant to radiation induced embrittlement compared to both the UK reference material and published data on older steels. The mechanistic understanding of irradiation embrittlement is becoming increasingly important particularly in terms of deriving a damage correlation model. The data from the supplementary tests are making a significant contribution towards this objective.
- OSTI ID:
- 5836151
- Report Number(s):
- CONF-820628-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) Journal Volume: 782
- Country of Publication:
- United States
- Language:
- English
Similar Records
International Atomic Energy Agency (IAEA) Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
Evaluation of IAEA coordinated program steels and welds for 288 deg C radiation embrittlement resistance
Effect of accelerated irradiation on fracture behavior. [C-Mn pressure vessel steel]
Journal Article
·
Wed Dec 31 23:00:00 EST 2008
· Journal of ASTM International
·
OSTI ID:979185
Evaluation of IAEA coordinated program steels and welds for 288 deg C radiation embrittlement resistance
Technical Report
·
Sun Jan 31 23:00:00 EST 1982
·
OSTI ID:5046065
Effect of accelerated irradiation on fracture behavior. [C-Mn pressure vessel steel]
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:5709732
Related Subjects
36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BARYONS
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
ELEMENTARY PARTICLES
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
FAST NEUTRONS
FERMIONS
HADRONS
HERALD REACTOR
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL TESTS
NEUTRON FLUENCE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POOL TYPE REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STEEL-ASTM-A508
STEELS
TEST REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BARYONS
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
ELEMENTARY PARTICLES
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
FAST NEUTRONS
FERMIONS
HADRONS
HERALD REACTOR
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL TESTS
NEUTRON FLUENCE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
POOL TYPE REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STEEL-ASTM-A508
STEELS
TEST REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS