Published 2007 | Version v1
Miscellaneous

K validity criterion of neutron irradiated type 316L stainless steel CT specimen for SCC growth test

  • 1. Toshiba Corp., Yokohama, Kanagawa (Japan)
  • 2. Japan Nuclear Energy Safety Organization, Tokyo (Japan)
  • 3. Nippon Nuclear Fuel Development Co. Ltd., Oarai, Ibaraki (Japan)

Description

In order to evaluate SCC growth rate of BWR core shroud by test results with compact tension (CT) specimens, the validity of neutron irradiated small CT specimen was verified on the basis of FEM and the deformation mark observations. As for the same stress intensity factor (K), the plastic zone size differs depending on the combination of the specimen size and the irradiation hardening. The deformation marks near the crack tip of the SUS316L CT specimens irradiated in JMTR were observed by optical microscope and compared with the plastic strain distributions in FEM. The adequate K value of CT specimen was discussed on the basis of comparison with plastic strain distribution near the crack tip of the core shroud model in FEM. For plastic strain comparison, appropriate K in CT specimen is at least 30 MPa√m for 11.4 mm thickness in 5 x 1024 n/m2 and 1 x 1025 n/m2 and for 5.8 mm thickness in 3 x 1025 n/m2. (author)

Part of:
13th International conference on environmental degradation of materials in nuclear power systems

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-89-5
Imprint Title
13th International conference on environmental degradation of materials in nuclear power systems
Imprint Pagination
388 Megabytes
Journal Page Range
[21 p.]

Conference

Title
13. International conference on environmental degradation of materials in nuclear power systems
Dates
19-23 Aug 2007
Place
Whistler, BC (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
39116832
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; CRACK PROPAGATION; CRACKING; DEFORMATION; IRRADIATION; NEUTRONS; STRESS CORROSION; STRESSES
Descriptors DEC
BARYONS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NUCLEONS; POWER REACTORS; PYROLYSIS; REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs., 4 tabs., 14 figs.