Published 2006 | Version v1
Book Metadata-only

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

Creators

  • 1. Nuclear Technology Safety Center, Liza Chaikina 4, Almaty 050020 (Kazakhstan)
  • 2. Institute of Nuclear Physics, 1 Ibragimova St., Almaty, 050032 (Kazakhstan)
  • 3. Kazakhstan Atomic Energy Committee, Liza Chaikina 4, Almaty (Kazakhstan)
  • 4. MAEC Kazatomprom, Aktau, 130000 (Kazakhstan)

Description

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 deg. C up to rather low damage 1.3 dpa and with dose rate 3.9 x 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 deg. 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. (authors)

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
Imprint Pagination
11 p.

Conference

Title
14. international conference on nuclear engineering (ICONE 14)
Dates
17-20 Jul 2006
Place
Miami, FL (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
39019409
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATOMIC DISPLACEMENTS; AUSTENITIC STEELS; BREEDER REACTORS; BUILDING MATERIALS; DAMAGE; DOSE RATES; DUCTILITY; ELONGATION; FAST REACTORS; IRRADIATION; ULTIMATE STRENGTH; WATER COOLED REACTORS; WATER MODERATED REACTORS; YIELD STRENGTH
Descriptors DEC
ALLOYS; CARBON ADDITIONS; DEFORMATION; EPITHERMAL REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTORS; STEELS; TENSILE PROPERTIES; TRANSITION ELEMENT ALLOYS