Design space exploration studies of an FHR concept leveraging AGR technologies

Zhiyao Xing, Eugene Shwageraus

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

7 Scopus citations

Abstract

It has been suggested that the prismatic block type Fluoride-salt-cooled High temperature Reactors (FHRs) can benefit from Advanced Gas-cooled Reactors (AGRs) technologies.1 This paper contributes to the global FHR development effort by investigating an AGR-like FHR concept. A reference FHR assembly design is proposed by replacing the CO2 coolant in a generic AGR with 2LiF-BeF2 (FLiBe). An alternative design studied uses UC instead of UO2 fuel due to its higher thermal conductivity and heavy metal density. Three alternative assembly configurations are proposed using annular internally cooled fuel designs to reduce maximum temperature, which, in some cases, is a limiting factor and thus increase safety margin and allow power uprate. Three different coolants, namely FLiBe, LiF-NaF-KF (FLiNaK) and NaF-ZrF4, and both UO2 and UC fuel types were considered for each design. By performing operating conditions domain search using sub-channel thermal-hydraulics solvers developed in this study, four designs were chosen out of the 20 proposed to proceed with future neutronics analyses and power system design. The four selected designs can deliver 5.6 GWth to 18.9 GWth power when operating at the same nominal condition as a generic AGR, increasing its power density by up to a factor of 12.

Original languageEnglish
Title of host publication2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PublisherInternational Congress on Advances in Nuclear Power Plants, ICAPP
ISBN (Electronic)9784890471676
StatePublished - 1 Jan 2017
Externally publishedYes
Event2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 - Fukui and Kyoto, Japan
Duration: 24 Apr 201728 Apr 2017

Publication series

Name2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings

Conference

Conference2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Country/TerritoryJapan
CityFukui and Kyoto
Period24/04/1728/04/17

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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