Effects of thermal annealing and reirradiation on toughness of reactor pressure vessel steels

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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 recent experimental results from work performed at the Oak Ridge National Laboratory (ORNL) to study the annealing response, or {open_quotes}recovery,{close_quotes} of several irradiated RPV steels; it also includes recent results from both ORNL and the Russian Research Center-Kurchatov Institute (RRC-KI) on a cooperative program of irradiation, annealing and reirradiation of both U.S. and Russian RPV steels. The cooperative program was conducted under the auspices of ... continued below

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12 p.

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Nanstad, R.K.; Iskander, S.K. & Sokolov, M.A. December 31, 1996.

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Description

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 recent experimental results from work performed at the Oak Ridge National Laboratory (ORNL) to study the annealing response, or {open_quotes}recovery,{close_quotes} of several irradiated RPV steels; it also includes recent results from both ORNL and the Russian Research Center-Kurchatov Institute (RRC-KI) on a cooperative program of irradiation, annealing and reirradiation of both U.S. and Russian RPV steels. The cooperative program was conducted under the auspices of Working Group 3, U.S./Russia Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS). The materials investigated are an RPV plate and various submerged-arc welds, with tensile, Charpy impact toughness, and fracture toughness results variously determined. Experimental results are compared with applicable prediction guidelines, while observed differences in annealing responses and reirradiation rates are discussed.

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12 p.

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INIS; OSTI as DE97002618

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  • 24. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1996

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  • Other: DE97002618
  • Report No.: CONF-9610202--4
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 442136
  • Archival Resource Key: ark:/67531/metadc677307

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • December 31, 1996

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  • July 25, 2015, 2:21 a.m.

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  • April 7, 2016, 8:51 p.m.

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Nanstad, R.K.; Iskander, S.K. & Sokolov, M.A. Effects of thermal annealing and reirradiation on toughness of reactor pressure vessel steels, article, December 31, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc677307/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.