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Title: Coupled field-structural analysis of HGTR fuel brick using ABAQUS

Abstract

High-temperature, gas-cooled reactors (HTGRs) are usually helium-gas cooled, with a graphite core that can operate at reactor outlet temperatures much higher than can conventional light water reactors. In HTGRs, graphite components moderate and reflect neutrons. During reactor operation, high temperature and high irradiation cause damage to the graphite crystal and grains and create other defects. This cumulative structural damage during the reactor lifetime leads to changes in graphite properties, which can alter the ability to support the designed loads. The aim of the present research is to develop a finite-element code using commercially available ABAQUS software for the structural integrity analysis of graphite core components under extreme temperature and irradiation conditions. In addition, the Reactor Geometry Generator tool-kit, developed at Argonne National Laboratory, is used to generate finite-element mesh for complex geometries such as fuel bricks with multiple pin holes and coolant flow channels. This paper presents the proposed concept and discusses results of stress analysis simulations of a fuel block with H-451 grade material properties. (authors)

Authors:
; ; ;  [1];  [2]
  1. Argonne National Laboratory, Argonne, IL (United States)
  2. U.S. Nuclear Regulatory Commission, Washington, DC (United States)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22105960
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 12 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; A CODES; ANL; BURNUP; COOLANT LOOPS; CRYSTALS; DAMAGE; FINITE ELEMENT METHOD; FLUID FLOW; FUEL ELEMENTS; GRAPHITE; HTGR TYPE REACTORS; NEUTRON REFLECTORS; REACTOR OPERATION; STRESS ANALYSIS

Citation Formats

Mohanty, S., Jain, R., Majumdar, S., Tautges, T. J., and Srinivasa, M. Coupled field-structural analysis of HGTR fuel brick using ABAQUS. United States: N. p., 2012. Web.
Mohanty, S., Jain, R., Majumdar, S., Tautges, T. J., & Srinivasa, M. Coupled field-structural analysis of HGTR fuel brick using ABAQUS. United States.
Mohanty, S., Jain, R., Majumdar, S., Tautges, T. J., and Srinivasa, M. Sun . "Coupled field-structural analysis of HGTR fuel brick using ABAQUS". United States.
@article{osti_22105960,
title = {Coupled field-structural analysis of HGTR fuel brick using ABAQUS},
author = {Mohanty, S. and Jain, R. and Majumdar, S. and Tautges, T. J. and Srinivasa, M.},
abstractNote = {High-temperature, gas-cooled reactors (HTGRs) are usually helium-gas cooled, with a graphite core that can operate at reactor outlet temperatures much higher than can conventional light water reactors. In HTGRs, graphite components moderate and reflect neutrons. During reactor operation, high temperature and high irradiation cause damage to the graphite crystal and grains and create other defects. This cumulative structural damage during the reactor lifetime leads to changes in graphite properties, which can alter the ability to support the designed loads. The aim of the present research is to develop a finite-element code using commercially available ABAQUS software for the structural integrity analysis of graphite core components under extreme temperature and irradiation conditions. In addition, the Reactor Geometry Generator tool-kit, developed at Argonne National Laboratory, is used to generate finite-element mesh for complex geometries such as fuel bricks with multiple pin holes and coolant flow channels. This paper presents the proposed concept and discusses results of stress analysis simulations of a fuel block with H-451 grade material properties. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jul 01 00:00:00 EDT 2012},
month = {Sun Jul 01 00:00:00 EDT 2012}
}

Conference:
Other availability
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