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Physics analysis of the LS-VHTR: Salt coolant and fuel block design

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

The Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR), also known as the Advanced High Temperature Reactor (AHTR), is a new, large [>2400 MW(t)], passively safe, high-temperature reactor concept. It uses a graphite-matrix coated-particle fuel and a graphite moderator similar to the fuel used in modular high-temperature gas-cooled reactors, but with a clean liquid-fluoride salt coolant. The neutronics properties of various salt coolant options are considered with respect to their coefficients of reactivity for various reactor configurations. In addition, several variations on the basic graphite block design of the AHTR are considered that would simplify refueling. The results show that the coolant coefficients of reactivity are negative or very small relative to other reactivity feedbacks, such as the fuel Doppler feedback. This allows several salt-coolants, even some with a positive coolant density coefficient, to be considered for use in the AHTR. In addition, parametric studies of assembly-type clusteredrod configurations show that there is minimal impact on the reactivity coefficients and multiplication factors with appropriate cluster design choices.

Original languageEnglish
Title of host publicationPHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
StatePublished - 2006
EventPHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics - Vancouver, BC, Canada
Duration: Sep 10 2006Sep 14 2006

Publication series

NamePHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
Volume2006

Conference

ConferencePHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
Country/TerritoryCanada
CityVancouver, BC
Period09/10/0609/14/06

Keywords

  • AHTR
  • Gen-IV
  • Liquid salt
  • Reactivity coefficients
  • VHTR

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