Fracture Toughness and Tensile Properties of Irradiated Reactor Pressure Vessel Cladding Material

ASTM Special Technical Publication

Volumn STP 1405, Issue , 2001, Pages 328-342

  Horsten, Marc G ^a   Belcher, William P A ^b  

^a NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

^b BRITISH ENERGY GENERATION LTD   (United Kingdom)

Author keywords

fracture resistance; neutron irradiation; orientation; pressure vessel cladding; temperature; tensile; thermal ageing

Indexed keywords

CLADDING (COATING); DUCTILE FRACTURE; FRACTURE TESTING; FRACTURE TOUGHNESS; NEUTRON IRRADIATION; NEUTRONS; PRESSURIZED WATER REACTORS; TENSILE TESTING; THERMAL AGING; YIELD STRESS;

CLAD MATERIALS; CLADDING MATERIAL; END OF LIVES; NEUTRON DOSE; ORIENTATION; PRESSURE VESSEL CLADDING; REACTOR PRESSURE VESSEL; RESISTANCE PROPERTIES; TENSILE; TEST TEMPERATURES;

PRESSURE VESSELS;

EID: 85164936913     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/STP10542S     Document Type: Conference Paper

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