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

Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Volumn 2, Issue , 2007, Pages 909-929

  Sumiya, Rie ^a   Tanaka, Shigeaki ^a   Nakata, Kiyotomo ^b   Takakura, Kenichi ^b   Ando, Masami ^b   Torimaru, Tadahiko ^c   Kitsunai, Yuji ^c  

^a TOSHIBA CORPORATION   (Japan)

^b JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^c NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; CRACK TIPS; DEFORMATION; DEGRADATION; ELECTRIC INSTRUMENT TRANSFORMERS; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; FINITE ELEMENT METHOD; MATERIALS SCIENCE; MOLECULAR BEAM EPITAXY; NEUTRONS; NUCLEAR ENERGY; PLASTIC DEFORMATION; PLASTICS; POWER TRANSMISSION; SULFATE MINERALS; TESTING;

316 L STAINLESS STEEL; COMPACT TENSION SPECIMENS; CORE SHROUD; CT SPECIMENS; INTERNATIONAL CONFERENCES; IRRADIATION HARDENING; K VALUES; NUCLEAR POWER SYSTEMS; NUCLEAR SOCIETY; OPTICAL MICROSCOPE; PLASTIC STRAINING; PLASTIC ZONE SIZE; STRESS INTENSITY; SUS316L; TEST RESULTS;

STAINLESS STEEL;

EID: 51849136469     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. IC of Metallic Materials", Annual Book of ASTM Standards 2006, Volume 03.01, ASTM, 2006
2. "Standard Test Method for Measurement of Fatigue Crack Growth Rates", Annual Book of ASTM Standards 2006, Volume 03.01, ASTM, 2006
3. "Standard Test Method for Determining Threshold Stress Intensity Factor for Environment-Assisted Cracking of Metallic Materials", Annual Book of ASTM Standards 2006, Volume 03.01, ASTM, 2006
4. Andresen P.L., "K / Size Effects on SCC in Irradiated, Cold Worked and Unirradiated Stainless Steel", 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, Aug. 10-14, 2003, pp.870-886
5. Jenssen A., Efsing P., Gott K. and Andersson P., "Crack Growth Behavior of Irradiated Type 304L Stainless Steel in Simulated BWR Environment", 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, Aug. 10-14, 2003, pp.1015-1026
6. "Fitness-for-Service", API RECOMMENDED PRACTICE 579 FIRST EDITION, JANUARY 2000, American Petroleum Institute