Physics Features of TRU-Fueled VHTRs

The current waste management strategy for spent nuclear fuel (SNF) mandated by the US Congress is the disposal of high-level waste (HLW) in a geological repository at Yucca Mountain. Ongoing efforts on closed-fuel cycle options and difficulties in opening and safeguarding such a repository have led...

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Main Authors: Tom G. Lewis, Pavel V. Tsvetkov
Format: Article
Language:English
Published: Wiley 2009-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2009/214285
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author Tom G. Lewis
Pavel V. Tsvetkov
author_facet Tom G. Lewis
Pavel V. Tsvetkov
author_sort Tom G. Lewis
collection DOAJ
description The current waste management strategy for spent nuclear fuel (SNF) mandated by the US Congress is the disposal of high-level waste (HLW) in a geological repository at Yucca Mountain. Ongoing efforts on closed-fuel cycle options and difficulties in opening and safeguarding such a repository have led to investigations of alternative waste management strategies. One potential strategy for the US fuel cycle would be to make use of fuel loadings containing high concentrations of transuranic (TRU) nuclides in the next-generation reactors. The use of such fuels would not only increase fuel supply but could also potentially facilitate prolonged operation modes (via fertile additives) on a single fuel loading. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units as nuclear batteries for worldwide deployment. Studies have already shown that high-temperature gas-cooled reactors (HTGRs) and their Generation IV (GEN IV) extensions, very-high-temperature reactors (VHTRs), have encouraging performance characteristics. This paper is focused on possible physics features of TRU-fueled VHTRs. One of the objectives of a 3-year U.S. DOE NERI project was to show that TRU-fueled VHTRs have the possibility of prolonged operation on a single fuel loading. A 3D temperature distribution was developed based on conceivable operation conditions of the 600 MWth VHTR design. Results of extensive criticality and depletion calculations with varying fuel loadings showed that VHTRs are capable for autonomous operation and HLW waste reduction when loaded with TRU fuel.
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spelling doaj-art-bf4fcd59312940639c5e61b729b8a5602025-02-03T01:09:11ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832009-01-01200910.1155/2009/214285214285Physics Features of TRU-Fueled VHTRsTom G. Lewis0Pavel V. Tsvetkov1Department of Nuclear Engineering, Texas A&M University, 129 Zachry Engineering Center, 3133 TAMU, College Station, TX 77843-3133, USADepartment of Nuclear Engineering, Texas A&M University, 129 Zachry Engineering Center, 3133 TAMU, College Station, TX 77843-3133, USAThe current waste management strategy for spent nuclear fuel (SNF) mandated by the US Congress is the disposal of high-level waste (HLW) in a geological repository at Yucca Mountain. Ongoing efforts on closed-fuel cycle options and difficulties in opening and safeguarding such a repository have led to investigations of alternative waste management strategies. One potential strategy for the US fuel cycle would be to make use of fuel loadings containing high concentrations of transuranic (TRU) nuclides in the next-generation reactors. The use of such fuels would not only increase fuel supply but could also potentially facilitate prolonged operation modes (via fertile additives) on a single fuel loading. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units as nuclear batteries for worldwide deployment. Studies have already shown that high-temperature gas-cooled reactors (HTGRs) and their Generation IV (GEN IV) extensions, very-high-temperature reactors (VHTRs), have encouraging performance characteristics. This paper is focused on possible physics features of TRU-fueled VHTRs. One of the objectives of a 3-year U.S. DOE NERI project was to show that TRU-fueled VHTRs have the possibility of prolonged operation on a single fuel loading. A 3D temperature distribution was developed based on conceivable operation conditions of the 600 MWth VHTR design. Results of extensive criticality and depletion calculations with varying fuel loadings showed that VHTRs are capable for autonomous operation and HLW waste reduction when loaded with TRU fuel.http://dx.doi.org/10.1155/2009/214285
spellingShingle Tom G. Lewis
Pavel V. Tsvetkov
Physics Features of TRU-Fueled VHTRs
Science and Technology of Nuclear Installations
title Physics Features of TRU-Fueled VHTRs
title_full Physics Features of TRU-Fueled VHTRs
title_fullStr Physics Features of TRU-Fueled VHTRs
title_full_unstemmed Physics Features of TRU-Fueled VHTRs
title_short Physics Features of TRU-Fueled VHTRs
title_sort physics features of tru fueled vhtrs
url http://dx.doi.org/10.1155/2009/214285
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