Mitigation of irradiation embrittlement by annealing

ASTM Special Technical Publication

Volumn 1270, Issue , 1996, Pages 232-247

  Amayev, Amir D ^a   Kryukov, Alexander M ^a   Levit, Vladimir I ^a   Platonov, Pavel A ^a   Sokolov, Mikhail A ^b,c  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b Kurchatov Institute

^c OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Annealing; Neutron fluence; Pressure vessel steels; Radiation effects; Radiation embrittlement; Reembrittlement

Indexed keywords

ANNEALING; IRRADIATION; NEUTRONS; PRESSURE VESSELS; RADIATION EFFECTS; STEEL; THERMAL EFFECTS;

ANNEALING TEMPERATURE; CHARPY TRANSITION TEMPERATURE; IRRADIATION EMBRITTLEMENT; LATERAL SHIFT METHOD; NEUTRON FLUENCE; REEMBRITTLEMENT; TRANSITION TEMPERATURE SHIFT;

EMBRITTLEMENT;

EID: 0030217373     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16476s     Document Type: Article

References (9)

1. A.D. Amayev, A.M. Kryukov, V.I. Levit, and M.A. Sokolov, "Radiation Stability of WWER-440 Vessel Materials," pp. 9-29 in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume), ASTM STP 1170, L.E. Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993.
2. A.D. Amayev, A.M. Kryukov, and M.A. Sokolov, "Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing," pp. 369-379 in Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume), ASTM STP 1170, L.E. Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993.
3. A.D. Amayev, A.M. Kryukov, V.I. Levit, P.A. Platonov, and M.A. Sokolov, "Investigation of Irradiation Embrittlement and Recovery Properties of Pressure Vessel Steels of WWER Reactors in the USSR," pp. 77-97 In Proceedings of a Technical Committee Meeting held in Plzen, Czechoslovakia, 14-17 May 1991, IAEA-TECDOC-665, International Atomic Energy Agency, 1991.
4. A.D. Amayev, A.M. Kryukov, V.I. Levit, P.A. Platonov, M.F. Rogov and M.A. Sokolov, "Radiation Damage and Recovery in VVER-440 Vessel Materials," in Proceedings of International Conference PLEX-93, 29 Nov.-1 Dec., 1993, Nuclear Engineering International, to be published.
5. A.D. Amayev, V.I. Badanin, A.M. Kryukov, V.A. Nikolayev, M.F. Rogov, and M.A. Sokolov, "Use of Subsize Specimens for Determination of Radiation Embrittlement of Operating Reactor Pressure Vessels," pp.. 424-439 in Small Specimen Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, ASTM STP 1204, W.R. Corwin, F.M. Haggag, and W.L. Server, Eds., American Society for Testing and Materials, Philadelphia, 1993.
6. V.A. Nikolayev, V.I. Badanin and A.M. Morozov, "Summing of Damages in Annealing and Reirradiation of Reactor Vessel Steel," pp. 165-167 in Atomnaya Energia, Vol. 57, No. 3, 1984, (in Russian).
7. A.M. Kryukov and M.A. Sokolov, "Investigation of Material Behavior Under Reirradiation after Annealing Using Subsize Specimens," pp.. 417-423 in Small Specimen Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, ASTM STP 1204, W.R. Corwin, F.M. Haggag, and W.L. Server, Eds., American Society for Testing and Materials, Philadelphia, 1993.
8. W.L. Server and A. Taboada, "An Approach for Estimating Post-Anneal Reirradiation Embrittlement for Reactor Vessel Steels," pp. 361-368 in Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, American Nuclear Society, La Grange Park, IL, 1986,
9. Standard Guide for In-Service Annealing of Water-Cooled Nuclear Reactor Vessels, ASTM E 509-86, American Society for Testing and Materials, Philadelphia.