Annual report, FY 1979 Spent fuel and fuel pool component integrity.
Abstract
International meetings under the BEFAST program and under INFCE Working Group No. 6 during 1978 and 1979 continue to indicate that no cases of fuel cladding degradation have developed on pool-stored fuel from water reactors. A section from a spent fuel rack stand, exposed for 1.5 y in the Yankee Rowe (PWR) pool had 0.001- to 0.003-in.-deep (25- to 75-..mu..m) intergranular corrosion in weld heat-affected zones but no evidence of stress corrosion cracking. A section of a 304 stainless steel spent fuel storage rack exposed 6.67 y in the Point Beach reactor (PWR) spent fuel pool showed no significant corrosion. A section of 304 stainless steel 8-in.-dia pipe from the Three Mile Island No. 1 (PWR) spent fuel pool heat exchanger plumbing developed a through-wall crack. The crack was intergranular, initiating from the inside surface in a weld heat-affected zone. The zone where the crack occurred was severely sensitized during field welding. The Kraftwerk Union (Erlangen, GFR) disassembled a stainless-steel fuel-handling machine that operated for 12 y in a PWR (boric acid) spent fuel pool. There was no evidence of deterioration, and the fuel-handling machine was reassembled for further use. A spent fuel pool at a Swedish PWR was decontaminated.more »
- Authors:
- Publication Date:
- Research Org.:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- OSTI Identifier:
- 5475124
- Report Number(s):
- PNL-3171
TRN: 80-009304
- DOE Contract Number:
- EY-76-C-06-1830
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUEL STORAGE; CORROSION; WATER COOLED REACTORS; FUEL CYCLE; BORIC ACID; FUEL POOLS; INSPECTION; STAINLESS STEELS; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; IRON ALLOYS; IRON BASE ALLOYS; REACTORS; STEELS; 050900* - Nuclear Fuels- Transport, Handling, & Storage
Citation Formats
Johnson, Jr, A B, Bailey, W J, Schreiber, R E, and Kustas, F M. Annual report, FY 1979 Spent fuel and fuel pool component integrity.. United States: N. p., 1980.
Web. doi:10.2172/5475124.
Johnson, Jr, A B, Bailey, W J, Schreiber, R E, & Kustas, F M. Annual report, FY 1979 Spent fuel and fuel pool component integrity.. United States. https://doi.org/10.2172/5475124
Johnson, Jr, A B, Bailey, W J, Schreiber, R E, and Kustas, F M. 1980.
"Annual report, FY 1979 Spent fuel and fuel pool component integrity.". United States. https://doi.org/10.2172/5475124. https://www.osti.gov/servlets/purl/5475124.
@article{osti_5475124,
title = {Annual report, FY 1979 Spent fuel and fuel pool component integrity.},
author = {Johnson, Jr, A B and Bailey, W J and Schreiber, R E and Kustas, F M},
abstractNote = {International meetings under the BEFAST program and under INFCE Working Group No. 6 during 1978 and 1979 continue to indicate that no cases of fuel cladding degradation have developed on pool-stored fuel from water reactors. A section from a spent fuel rack stand, exposed for 1.5 y in the Yankee Rowe (PWR) pool had 0.001- to 0.003-in.-deep (25- to 75-..mu..m) intergranular corrosion in weld heat-affected zones but no evidence of stress corrosion cracking. A section of a 304 stainless steel spent fuel storage rack exposed 6.67 y in the Point Beach reactor (PWR) spent fuel pool showed no significant corrosion. A section of 304 stainless steel 8-in.-dia pipe from the Three Mile Island No. 1 (PWR) spent fuel pool heat exchanger plumbing developed a through-wall crack. The crack was intergranular, initiating from the inside surface in a weld heat-affected zone. The zone where the crack occurred was severely sensitized during field welding. The Kraftwerk Union (Erlangen, GFR) disassembled a stainless-steel fuel-handling machine that operated for 12 y in a PWR (boric acid) spent fuel pool. There was no evidence of deterioration, and the fuel-handling machine was reassembled for further use. A spent fuel pool at a Swedish PWR was decontaminated. The procedure is outlined in this report.},
doi = {10.2172/5475124},
url = {https://www.osti.gov/biblio/5475124},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu May 01 00:00:00 EDT 1980},
month = {Thu May 01 00:00:00 EDT 1980}
}