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Neutron damage reduction in a traveling wave reactor

Abstract

Traveling wave reactors are envisioned to run on depleted or natural uranium with no need for enrichment or reprocessing, and in a manner which requires little to no operator intervention. If feasible, this type of reactor has significant advantages over conventional nuclear power systems. However, a practical implementation of this concept is challenging as neutron irradiation levels many times greater than those in conventional reactors appear to be required for a fission wave to propagate. Radiation damage to the fuel and cladding materials presents a significant obstacle to a practical design. One possibility for reducing damage is to soften the neutron energy spectrum. Here we show that using a uranium oxide fuel form will allow a shift in the neutron spectrum that can result in at least a three fold decrease in dpa levels for fuel cladding and structural steels within the reactor compared with the dpa levels expected when using a uranium metal fuel. (authors)
Authors:
Osborne, A. G.; Deinert, M. R. [1] 
  1. Dept. of Mechanical Engineering, Univ. of Texas at Austin, Austin, TX (United States)
Publication Date:
Jul 01, 2012
Product Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 17 refs.
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BUILDING MATERIALS; CLADDING; COMPARATIVE EVALUATIONS; DAMAGE; DEPLETED URANIUM; DESIGN; ENERGY SPECTRA; FISSION; IRRADIATION; NATURAL URANIUM; NEUTRON SPECTRA; NEUTRONS; NUCLEAR FUELS; RADIATION EFFECTS; REACTOR FUELING; STEELS; TRAVELLING WAVES; URANIUM OXIDES
OSTI ID:
22105673
Research Organizations:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
Country of Origin:
United States
Language:
English
Other Identifying Numbers:
Other: ISBN 978-0-89448-085-9; TRN: US13V0170063494
Submitting Site:
USN
Size:
10 page(s)
Announcement Date:
Jun 20, 2013

Citation Formats

Osborne, A. G., and Deinert, M. R. Neutron damage reduction in a traveling wave reactor. United States: N. p., 2012. Web.
Osborne, A. G., & Deinert, M. R. Neutron damage reduction in a traveling wave reactor. United States.
Osborne, A. G., and Deinert, M. R. 2012. "Neutron damage reduction in a traveling wave reactor." United States.
@misc{etde_22105673,
title = {Neutron damage reduction in a traveling wave reactor}
author = {Osborne, A. G., and Deinert, M. R.}
abstractNote = {Traveling wave reactors are envisioned to run on depleted or natural uranium with no need for enrichment or reprocessing, and in a manner which requires little to no operator intervention. If feasible, this type of reactor has significant advantages over conventional nuclear power systems. However, a practical implementation of this concept is challenging as neutron irradiation levels many times greater than those in conventional reactors appear to be required for a fission wave to propagate. Radiation damage to the fuel and cladding materials presents a significant obstacle to a practical design. One possibility for reducing damage is to soften the neutron energy spectrum. Here we show that using a uranium oxide fuel form will allow a shift in the neutron spectrum that can result in at least a three fold decrease in dpa levels for fuel cladding and structural steels within the reactor compared with the dpa levels expected when using a uranium metal fuel. (authors)}
place = {United States}
year = {2012}
month = {Jul}
}