skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: FRAPCON analysis of cladding performance during dry storage operations

Abstract

There is an increasing need in the U.S. and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations (ISFSI) or interim storage sites. The NRC limits cladding temperature to 400°C while maintaining cladding hoop stress below 90 MPa in an effort to avoid radial hydride reorientation. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at 400 °C. Results were representative of the majority of U.S. LWR fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.

Authors:
;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1434858
Report Number(s):
PNNL-SA-125967
Journal ID: ISSN 1738-5733; 453040371
DOE Contract Number:
AC05-76RL01830
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Engineering and Technology; Journal Volume: 50; Journal Issue: 2
Country of Publication:
United States
Language:
English
Subject:
Dry Storage; FRAPCON; Spent Fuel; Vacuum Drying

Citation Formats

Richmond, David J., and Geelhood, Kenneth J.. FRAPCON analysis of cladding performance during dry storage operations. United States: N. p., 2018. Web. doi:10.1016/j.net.2018.01.003.
Richmond, David J., & Geelhood, Kenneth J.. FRAPCON analysis of cladding performance during dry storage operations. United States. doi:10.1016/j.net.2018.01.003.
Richmond, David J., and Geelhood, Kenneth J.. Thu . "FRAPCON analysis of cladding performance during dry storage operations". United States. doi:10.1016/j.net.2018.01.003.
@article{osti_1434858,
title = {FRAPCON analysis of cladding performance during dry storage operations},
author = {Richmond, David J. and Geelhood, Kenneth J.},
abstractNote = {There is an increasing need in the U.S. and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations (ISFSI) or interim storage sites. The NRC limits cladding temperature to 400°C while maintaining cladding hoop stress below 90 MPa in an effort to avoid radial hydride reorientation. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at 400 °C. Results were representative of the majority of U.S. LWR fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.},
doi = {10.1016/j.net.2018.01.003},
journal = {Nuclear Engineering and Technology},
number = 2,
volume = 50,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 2018},
month = {Thu Mar 01 00:00:00 EST 2018}
}