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Nanstad, R.K.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.
Irradiation effects and mitigation. Proceedings of the IAEA Specialists Meeting. Working material1997
Irradiation effects and mitigation. Proceedings of the IAEA Specialists Meeting. Working material1997
AbstractAbstract
[en] One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. This paper summarizes experimental results from work performed as part of the Heavy-Section Steel Irradiation (HSSI) Program managed by Oak Ridge National Laboratory (ORNL) for the U.S. Nuclear Regulatory Commission. The HSSI Program focuses on annealing and re-embrittlement response of materials which are representative of those in commercial RPVs and which are considered to be radiation-sensitive. Experimental studies include (1) the annealing of materials in the existing inventory of previously irradiated materials, (2) reirradiation of previously irradiated/annealed materials in a collaborative program with the University of California, Santa Barbara (UCSB), (3) irradiation/annealing/reirradiation of U.S. and Russian materials in a cooperative program with the Russian Research Center-Kurchatov Institute (RRC-KI), (4) the design and fabrication of an irradiation/anneal/reirradiation capsule and facility for operation at the University of Michigan Ford Reactor, (5) the investigation of potential for irradiation-and/or thermal-induced temper embrittlement in heat-affected zones (HAZs) of RPV steels due to phosphorous segregation at grain boundaries, and (6) investigation of the relationship between Charpy impact toughness and fracture toughness under all conditions of irradiation, annealing, and reirradiation
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International Atomic Energy Agency, Vienna (Austria). International Working Group on Life Management of Nuclear Power Plants; 398 p; 1997; p. 154-162; IAEA specialists meeting on irradiation effects and mitigation; Vladimir (Russian Federation); 15-19 Sep 1997; CONTRACT DE-AC05-96OR22464; 8 refs, figs
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Report
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Conference
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ALLOYS, CARBON ADDITIONS, CONTAINERS, CRYSTAL STRUCTURE, ELEMENTS, ENRICHED URANIUM REACTORS, HEAT TREATMENTS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, METALS, NATIONAL ORGANIZATIONS, NONMETALS, POWER REACTORS, PWR TYPE REACTORS, RADIATION EFFECTS, REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENTS, US AEC, US DOE, US ERDA, US ORGANIZATIONS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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