Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)

Technical Report · Wed Sep 01 04:00:00 EDT 2004

DOI:https://doi.org/10.2172/837206· OSTI ID:837206

M Krug, R Shogan ^[1]

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1. EPRI

Pressurized water reactor (PWR) cores operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs requires detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel (internals) subjected to such conditions. This project studied the effects of reactor service on the mechanical and corrosion properties of samples of baffle plate, former plate, and core barrel from a decommissioned PWR.

• Research Organization: EPRI (US)
• Sponsoring Organization: USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
• DOE Contract Number: FC07-00NE22796
• OSTI ID: 837206
• Report Number(s): 1011027
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BAFFLES
CHEMISTRY
COOLANTS
CORROSION
DRILLING EQUIPMENT
NEUTRONS
PRESSURIZED WATER REACTOR
RADIATION EFFECTS
TENSILE
SLOW STRAIN RATE TENSILE (SSRT)
REACTOR INTERNALS
STAINLESS STEEL
IRRADIATION ASSISTED STRESS CORROSION CRACKING (IASCC)
PWR TYPE REACTORS
STAINLESS STEELS
TESTING