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The Application of Structural Materials Data From the BN-350 Fast Reactor to Life Extension of Light Water Reactors

[+] Author Affiliations
O. G. Romanenko

Nuclear Technology Safety Center, Almaty, Kazakhstan

S. B. Kislitsin, O. P. Maksimkin, Ye. V. Chumakov

Institute of Nuclear Physics NNC, Almaty, Kazakhstan

Sh. B. Shiganakov

Kazakhstan Atomic Energy Committee, Almaty, Kazakhstan

I. V. Dumchev

MAEC Kazatomprom, Aktau, Kazakhstan

Paper No. ICONE14-89028, pp. 349-359; 11 pages
doi:10.1115/ICONE14-89028
From:
  • 14th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management
  • Miami, Florida, USA, July 17–20, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4242-8 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME

abstract

This paper describes the results of investigations of 08Cr16Ni11Mo3 (AISI 316 steel analogue) austenitic stainless steel irradiated in BN-350 breeder reactor at irradiation conditions close to that for Light Water Reactor (LWR) Internals. The pores were found in 08Cr16Ni11Mo3 steel irradiated at temperature 280°C up to rather low damage 1.3 dpa and with dose rate 3.9×10−9 dpa/s. There were obtained dose rate dependencies of yield strength, ultimate strength and ductility for 08Cr16Ni11Mo3 steel irradiated up to 7–13 dpa at 302–311°C. These dependencies show a decrease in both yield strength and ultimate strength when dose rate decreases. There was observed an apparent decrease in total elongation when dose rate decreases, which was presumably connected with the pores formation in the steel at low dose rates.

Copyright © 2006 by ASME

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