Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]
Abstract
In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.
- Authors:
- Publication Date:
- Research Org.:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- OSTI Identifier:
- 6021014
- Report Number(s):
- NUREG/CR-3999; PNL-5245
ON: TI85007915; TRN: 85-006261
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL CANS; PHYSICAL RADIATION EFFECTS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; PWR TYPE REACTORS; FUEL RODS; FUEL SYSTEMS; SIMULATION; SYSTEM FAILURE ANALYSIS; TESTING; ZIRCALOY; ALLOYS; FUEL ELEMENTS; PELLETS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; SYSTEMS ANALYSIS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Barner, J. O., and Fitzsimmons, D. E. Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]. United States: N. p., 1985.
Web. doi:10.2172/6021014.
Barner, J. O., & Fitzsimmons, D. E. Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]. United States. https://doi.org/10.2172/6021014
Barner, J. O., and Fitzsimmons, D. E. 1985.
"Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]". United States. https://doi.org/10.2172/6021014. https://www.osti.gov/servlets/purl/6021014.
@article{osti_6021014,
title = {Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR]},
author = {Barner, J. O. and Fitzsimmons, D. E.},
abstractNote = {In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.},
doi = {10.2172/6021014},
url = {https://www.osti.gov/biblio/6021014},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Feb 01 00:00:00 EST 1985},
month = {Fri Feb 01 00:00:00 EST 1985}
}