Comparison of SCC growth rate between in-core and ex-core tests in BWR simulated high temperature water

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

Volumn 2, Issue , 2007, Pages 897-908

  Kaji, Yoshiyuki ^a   Ugachi, Hirokazu ^a   Tsukada, Takashi ^a   Matsui, Yoshinori ^a   Ohmi, Masao ^a   Nagata, Nobuaki ^b   Dozaki, Koji ^b   Takiguchi, Hideki ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Mitoshiro Bldg   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; CORROSION; CRACKING (CHEMICAL); DEGRADATION; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; INERT GAS WELDING; LIGHT WATER REACTORS; NUCLEAR ENERGY; NUCLEAR REACTORS; POWER TRANSMISSION; STEEL; STEEL CORROSION; STEEL METALLURGY; STRESS CORROSION CRACKING; SULFATE MINERALS; TESTING;

COMPACT TENSION; HIGH-TEMPERATURE WATER; INTERNATIONAL CONFERENCES; IRRADIATION ASSISTED STRESS CORROSION CRACKING; NEUTRON FLUENCE; NUCLEAR POWER SYSTEMS; NUCLEAR SOCIETY; STAINLESS STEELS; TYPE 304 STAINLESS STEEL;

STAINLESS STEEL;

EID: 51849120669     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (17)

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