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

Abstract

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.

Authors:
Publication Date:
Research Org.:
EPRI (US)
Sponsoring Org.:
USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
OSTI Identifier:
837206
Report Number(s):
1011027
TRN: US0501354
DOE Contract Number:  
FC07-00NE22796
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Sep 2004
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; BAFFLES; CHEMISTRY; COOLANTS; CORROSION; DRILLING EQUIPMENT; NEUTRONS; PWR TYPE REACTORS; STAINLESS STEELS; TESTING; PRESSURIZED WATER REACTOR, RADIATION EFFECTS, TENSILE, SLOW STRAIN RATE TENSILE (SSRT), REACTOR INTERNALS, STAINLESS STEEL, IRRADIATION ASSISTED STRESS CORROSION CRACKING (IASCC)

Citation Formats

M.Krug, R.Shogan. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version). United States: N. p., 2004. Web. doi:10.2172/837206.
M.Krug, R.Shogan. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version). United States. doi:10.2172/837206.
M.Krug, R.Shogan. Wed . "Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)". United States. doi:10.2172/837206. https://www.osti.gov/servlets/purl/837206.
@article{osti_837206,
title = {Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)},
author = {M.Krug, R.Shogan},
abstractNote = {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.},
doi = {10.2172/837206},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Sep 01 00:00:00 EDT 2004},
month = {Wed Sep 01 00:00:00 EDT 2004}
}

Technical Report:

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