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

Title: A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel

Abstract

Accident-tolerant fuels are expected to have considerably longer coping time to respond to the loss of active cooling under severe accidents and, at the same time, have comparable or improved fuel performance during normal operation. The wear resistance of accident tolerant fuels, therefore, needs to be examined to determine the applicability of these cladding candidates to the current operating PWRs because the most common failure of nuclear fuel claddings is still caused by grid-to-rod fretting during normal operations. In this study, reciprocating sliding wear tests on three kinds of cladding candidates for accident-tolerant fuels have been performed to investigate the tribological compatibilities of selfmated cladding candidates and to determine the direct applicability of conventional Zirconium-based alloys as supporting structural materials. The friction coefficients of the cladding candidates are strongly influenced by the test environments and coupled materials. The wear test results under water lubrication conditions indicate that the supporting structural materials for the cladding candidates of accident-tolerant fuels need to be replaced with the same cladding materials instead of using conventional Zirconium-based alloys.

Authors:
ORCiD logo [1];  [2]
  1. Korea Atomic Energy Research Inst., Daejeon (South Korea)
  2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1337726
Report Number(s):
PNNL-SA-117477
Journal ID: ISSN 0022-3115; AF5810000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 465; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Lee, Young-Ho, and Byun, Thak Sang. A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel. United States: N. p., 2015. Web. doi:10.1016/j.jnucmat.2015.05.017.
Lee, Young-Ho, & Byun, Thak Sang. A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel. United States. doi:10.1016/j.jnucmat.2015.05.017.
Lee, Young-Ho, and Byun, Thak Sang. Thu . "A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel". United States. doi:10.1016/j.jnucmat.2015.05.017.
@article{osti_1337726,
title = {A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel},
author = {Lee, Young-Ho and Byun, Thak Sang},
abstractNote = {Accident-tolerant fuels are expected to have considerably longer coping time to respond to the loss of active cooling under severe accidents and, at the same time, have comparable or improved fuel performance during normal operation. The wear resistance of accident tolerant fuels, therefore, needs to be examined to determine the applicability of these cladding candidates to the current operating PWRs because the most common failure of nuclear fuel claddings is still caused by grid-to-rod fretting during normal operations. In this study, reciprocating sliding wear tests on three kinds of cladding candidates for accident-tolerant fuels have been performed to investigate the tribological compatibilities of selfmated cladding candidates and to determine the direct applicability of conventional Zirconium-based alloys as supporting structural materials. The friction coefficients of the cladding candidates are strongly influenced by the test environments and coupled materials. The wear test results under water lubrication conditions indicate that the supporting structural materials for the cladding candidates of accident-tolerant fuels need to be replaced with the same cladding materials instead of using conventional Zirconium-based alloys.},
doi = {10.1016/j.jnucmat.2015.05.017},
journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = C,
volume = 465,
place = {United States},
year = {2015},
month = {10}
}