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Title: Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel

Abstract

The development of new cladding materials to replace Zr-based cladding for light water reactors (LWRs) has been actively pursued with improved high-temperature oxidation resistance to significantly suppress hydrogen production from an accident such as a loss of coolant event. FeCrAl alloy with a typical composition of approximately Fe-15Cr-5Al has been selected as a candidate material because of its improved high-temperature oxidation resistance over the present LWR zircaloy cladding. As a result of higher thermal neutron absorption for FeCrAl alloy, the cladding wall thickness needs to be reduced by approximately half compared to that of Zircaloy cladding to be comparable to the current LWR fuel performance under the normal operating condition. New weld techniques for joining the endplug to thin-walled cladding need to be developed. Both laser beam weld and pressure resistance weld were employed. This paper summarizes the recent progress on the laser weld development for FeCrAl cladding with 350 µm wall thickness. The results of microstructural characterization and mechanical property testing of the weld for the cladding-endplug set are discussed.

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1];  [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1471570
Report Number(s):
INL/CON-17-40835-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: 2017 Water Reactor Fuel Performance Meeting, Ramada Plaza Jeju • Jeju Island, South Korea, 09/10/2017 - 09/14/2017
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 - MATERIALS SCIENCE; Laser beam weld; pressure resistance weld; FeCrAl; thin-walled cladding; characterization

Citation Formats

Gan, Jian, Jerred, Nathan D., Perez, Emmanuel, Haggard, DC, and Wen, Haiming. Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel. United States: N. p., 2017. Web.
Gan, Jian, Jerred, Nathan D., Perez, Emmanuel, Haggard, DC, & Wen, Haiming. Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel. United States.
Gan, Jian, Jerred, Nathan D., Perez, Emmanuel, Haggard, DC, and Wen, Haiming. Fri . "Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel". United States. https://www.osti.gov/servlets/purl/1471570.
@article{osti_1471570,
title = {Weld Development of FeCrAl Thin-Wall Cladding for LWR Accident Tolerant Fuel},
author = {Gan, Jian and Jerred, Nathan D. and Perez, Emmanuel and Haggard, DC and Wen, Haiming},
abstractNote = {The development of new cladding materials to replace Zr-based cladding for light water reactors (LWRs) has been actively pursued with improved high-temperature oxidation resistance to significantly suppress hydrogen production from an accident such as a loss of coolant event. FeCrAl alloy with a typical composition of approximately Fe-15Cr-5Al has been selected as a candidate material because of its improved high-temperature oxidation resistance over the present LWR zircaloy cladding. As a result of higher thermal neutron absorption for FeCrAl alloy, the cladding wall thickness needs to be reduced by approximately half compared to that of Zircaloy cladding to be comparable to the current LWR fuel performance under the normal operating condition. New weld techniques for joining the endplug to thin-walled cladding need to be developed. Both laser beam weld and pressure resistance weld were employed. This paper summarizes the recent progress on the laser weld development for FeCrAl cladding with 350 µm wall thickness. The results of microstructural characterization and mechanical property testing of the weld for the cladding-endplug set are discussed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {9}
}

Conference:
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