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Title: Post-irradiation Examinations of High Burnup PWR Rods

Abstract

The High Burnup Spent Fuel Data Project (herein referred to as the “project”), sponsored by the US Department of Energy (DOE) Office of Nuclear Energy (NE), is focused on experimentally evaluating the effects of long-term storage and transportation on high burnup (HBU) (defined as >45 gigawatt days per metric ton uranium) pressurized water reactor (PWR) spent nuclear fuel (SNF) [1]. To support this project, in the fall of 2017, an instrumented bolted-lid cask (project cask) at the North Anna reactor site was loaded with intact, HBU PWR fuel assemblies (project assemblies) having four different kinds of cladding and will be reopened in approximately 10-years for inspection. To support pre- and post-storage SNF rod characterization, 25 “sister rods” that are similar to the rods being stored in the project cask were extracted from seven different fuel assemblies at the North Anna nuclear power plant for post-irradiation examination (PIE).The sister rod testing program has multiple objectives, including: 1) Baseline testing to provide essential information on the physical condition and properties of the cladding and the fuel in the cladding prior to the loading, drying, and long-term dry storage process (analogous to an experiment control group). Similar tests are expected to be performedmore » at the end of the 10-year storage period on rods extracted from the cask to identify any changes in the properties of the fuel rods that may have occurred during the dry storage period; and 2) Tests to provide material property and physical data using accelerated separate effects tests (SETs) and small-scale tests (SSTs) to explore a wide range of conditions that may occur for other dry storage systems and/or while the fuel is being transported after aging.Testing will be focused on understanding overall SNF rod strength and durability, and be comprised of both composite fuel and defueled clad testing with a focus on measuring cladding material and mechanical properties. Nondestructive testing is currently underway and plans are being updated to support the initial set of destructive tests that are expected to begin by early 2018. While the data generated can be used for multiple purposes, a primary goal of the sister rod PIE data and associated measured mechanical properties are expected to support existing fuel storage licensing and relicensing activities by addressing identified knowledge gaps, and enhance the technical bases for post-storage transportation, handling, and consolidation activities [1]. This paper presents results obtained from the sister rod testing to date, and describes some of the planned measurements, equipment, and procedures that will be implemented for the initial set of destructive examinations.« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1480633
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: WM2018 Conference - Phoenix, Arizona, United States of America - 3/18/2018 4:00:00 AM-3/22/2018 4:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Montgomery, Rose, Scaglione, John M., and Bevard, Bruce Balkcom. Post-irradiation Examinations of High Burnup PWR Rods. United States: N. p., 2018. Web.
Montgomery, Rose, Scaglione, John M., & Bevard, Bruce Balkcom. Post-irradiation Examinations of High Burnup PWR Rods. United States.
Montgomery, Rose, Scaglione, John M., and Bevard, Bruce Balkcom. Thu . "Post-irradiation Examinations of High Burnup PWR Rods". United States. https://www.osti.gov/servlets/purl/1480633.
@article{osti_1480633,
title = {Post-irradiation Examinations of High Burnup PWR Rods},
author = {Montgomery, Rose and Scaglione, John M. and Bevard, Bruce Balkcom},
abstractNote = {The High Burnup Spent Fuel Data Project (herein referred to as the “project”), sponsored by the US Department of Energy (DOE) Office of Nuclear Energy (NE), is focused on experimentally evaluating the effects of long-term storage and transportation on high burnup (HBU) (defined as >45 gigawatt days per metric ton uranium) pressurized water reactor (PWR) spent nuclear fuel (SNF) [1]. To support this project, in the fall of 2017, an instrumented bolted-lid cask (project cask) at the North Anna reactor site was loaded with intact, HBU PWR fuel assemblies (project assemblies) having four different kinds of cladding and will be reopened in approximately 10-years for inspection. To support pre- and post-storage SNF rod characterization, 25 “sister rods” that are similar to the rods being stored in the project cask were extracted from seven different fuel assemblies at the North Anna nuclear power plant for post-irradiation examination (PIE).The sister rod testing program has multiple objectives, including: 1) Baseline testing to provide essential information on the physical condition and properties of the cladding and the fuel in the cladding prior to the loading, drying, and long-term dry storage process (analogous to an experiment control group). Similar tests are expected to be performed at the end of the 10-year storage period on rods extracted from the cask to identify any changes in the properties of the fuel rods that may have occurred during the dry storage period; and 2) Tests to provide material property and physical data using accelerated separate effects tests (SETs) and small-scale tests (SSTs) to explore a wide range of conditions that may occur for other dry storage systems and/or while the fuel is being transported after aging.Testing will be focused on understanding overall SNF rod strength and durability, and be comprised of both composite fuel and defueled clad testing with a focus on measuring cladding material and mechanical properties. Nondestructive testing is currently underway and plans are being updated to support the initial set of destructive tests that are expected to begin by early 2018. While the data generated can be used for multiple purposes, a primary goal of the sister rod PIE data and associated measured mechanical properties are expected to support existing fuel storage licensing and relicensing activities by addressing identified knowledge gaps, and enhance the technical bases for post-storage transportation, handling, and consolidation activities [1]. This paper presents results obtained from the sister rod testing to date, and describes some of the planned measurements, equipment, and procedures that will be implemented for the initial set of destructive examinations.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {3}
}

Conference:
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