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Title: Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation

Abstract

SiC-SiC composites are being considered for applications in the core components, including BWR channel box and fuel rod cladding, of light water reactors to improve accident tolerance. In the extreme nuclear reactor environment, core components like the BWR channel box will be exposed to neutron damage and a corrosive environment. To ensure reliable and safe operation of a SiC channel box, it is important to assess its deformation behavior under in-reactor conditions including the expected neutron flux and temperature distributions. In particular, this work has evaluated the effect of non-uniform dimensional changes caused by spatially varying neutron flux and temperatures on the deformation behavior of the channel box over the course of one cycle of irradiation. These analyses have been performed using the fuel performance modeling code BISON and the commercial finite element analysis code Abaqus, based on fast flux and temperature boundary conditions have been calculated using the neutronics and thermal-hydraulics codes Serpent2 and COBRA-TF, respectively. The dependence of dimensions and thermophysical properties on fast flux and temperature has been incorporated into the material models. These initial results indicate significant bowing of the channel box with a lateral displacement greater than 6.5mm. The channel box bowing behavior is timemore » dependent, and driven by the temperature dependence of the SiC irradiation-induced swelling and the neutron flux/fluence gradients. The bowing behavior gradually recovers during the course of the operating cycle as the swelling of the SiC-SiC material saturates. However, the bending relaxation due to temperature gradients does not fully recover and residual bending remains after the swelling saturates in the entire channel box.« less

Authors:
 [1]; ORCiD logo [1];  [2];  [3];  [2]; ORCiD logo [1]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Pennsylvania State Univ., University Park, PA (United States)
  3. Univ. of Tennessee, Knoxville, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1439933
Report Number(s):
ORNL/TM-2018/854
TRN: US1901713
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats

Wirth, Brian, Singh, Gyanender P., Gorton, Jacob, Schappel, Daniel, Brown, N., Katoh, Yutai, and Terrani, Kurt A. Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation. United States: N. p., 2018. Web. doi:10.2172/1439933.
Wirth, Brian, Singh, Gyanender P., Gorton, Jacob, Schappel, Daniel, Brown, N., Katoh, Yutai, & Terrani, Kurt A. Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation. United States. doi:10.2172/1439933.
Wirth, Brian, Singh, Gyanender P., Gorton, Jacob, Schappel, Daniel, Brown, N., Katoh, Yutai, and Terrani, Kurt A. Tue . "Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation". United States. doi:10.2172/1439933. https://www.osti.gov/servlets/purl/1439933.
@article{osti_1439933,
title = {Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation},
author = {Wirth, Brian and Singh, Gyanender P. and Gorton, Jacob and Schappel, Daniel and Brown, N. and Katoh, Yutai and Terrani, Kurt A.},
abstractNote = {SiC-SiC composites are being considered for applications in the core components, including BWR channel box and fuel rod cladding, of light water reactors to improve accident tolerance. In the extreme nuclear reactor environment, core components like the BWR channel box will be exposed to neutron damage and a corrosive environment. To ensure reliable and safe operation of a SiC channel box, it is important to assess its deformation behavior under in-reactor conditions including the expected neutron flux and temperature distributions. In particular, this work has evaluated the effect of non-uniform dimensional changes caused by spatially varying neutron flux and temperatures on the deformation behavior of the channel box over the course of one cycle of irradiation. These analyses have been performed using the fuel performance modeling code BISON and the commercial finite element analysis code Abaqus, based on fast flux and temperature boundary conditions have been calculated using the neutronics and thermal-hydraulics codes Serpent2 and COBRA-TF, respectively. The dependence of dimensions and thermophysical properties on fast flux and temperature has been incorporated into the material models. These initial results indicate significant bowing of the channel box with a lateral displacement greater than 6.5mm. The channel box bowing behavior is time dependent, and driven by the temperature dependence of the SiC irradiation-induced swelling and the neutron flux/fluence gradients. The bowing behavior gradually recovers during the course of the operating cycle as the swelling of the SiC-SiC material saturates. However, the bending relaxation due to temperature gradients does not fully recover and residual bending remains after the swelling saturates in the entire channel box.},
doi = {10.2172/1439933},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {5}
}

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