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Title: Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (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 require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested 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:
836105
Report Number(s):
1009799
TRN: US200706%%799
DOE Contract Number:  
FC07-00NE22796
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; CHEMISTRY; COOLANTS; CORROSION; NEUTRONS; PWR TYPE REACTORS; REACTOR COMPONENTS; STAINLESS STEELS; PRESSURIZED WATER REACTOR; RADIATION EFFECTS; RADIATION HISTORY; THERMAL HISTORY; REACTOR INTERNALS; STAINLESS STEEL

Citation Formats

M. Krug, R. Shogan, A. Fero, and M. Snyder. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version). United States: N. p., 2004. Web. doi:10.2172/836105.
M. Krug, R. Shogan, A. Fero, & M. Snyder. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version). United States. doi:10.2172/836105.
M. Krug, R. Shogan, A. Fero, and M. Snyder. Mon . "Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)". United States. doi:10.2172/836105. https://www.osti.gov/servlets/purl/836105.
@article{osti_836105,
title = {Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)},
author = {M. Krug and R. Shogan and A. Fero and M. Snyder},
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 require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.},
doi = {10.2172/836105},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2004},
month = {11}
}