Effects of irradiation temperature on embrittlement of nuclear pressure vessel steels

Conference · Thu Dec 31 00:00:00 EST 1992

OSTI ID:10163034

Haggag, F M

The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are being investigated, primarily because the operating temperatures are low [121 to 288{degrees}C (250--550{degrees}F)] compared to those for commercial light-water reactors (LWRs) [{approximately}288{degrees}C (550{degrees}F)]. The need for design data on the reference temperature (RT{sub NDT}) shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plates, A 508 class 3 forging, and welds used for the vessel shell, vessel closure head, and vessel flange. This paper presents regular- and mini-tensile, Automated Ball Indentation (ABI), and Charpy V-notch (CVN) impact test results from five irradiation capsules of this program.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10163034
• Report Number(s): CONF-920673-18; ON: DE93015428; TRN: 93:016412
• Resource Relation: Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials,Denver, CO (United States),21-25 Jun 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
HTGR TYPE REACTORS
PRESSURE VESSELS
EMBRITTLEMENT
RADIATION EFFECTS
STEEL-ASTM-A533-B
STEEL-ASTM-A508
CHARPY TEST
NEUTRON FLUENCE
WELDED JOINTS
FORGING
IRRADIATION
TENSILE PROPERTIES
210300
360103
360106
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
MECHANICAL PROPERTIES