Neutronics and Thermal-Hydraulics Coupling Analysis of Integral Inherently Safe Fluoride-Salt-Cooled High-Temperature Advanced Reactor - Fustar

  • Xingguang Zhou
  • , Dalin Zhang
  • , Xinyu Li
  • , Xin Min
  • , Wenqiang Wu
  • , Lei Zhou
  • , Wenxi Tian
  • , Suizheng Qiu

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

1 Scopus citations

Abstract

The integral inherently safe fluoride salt cooled high-temperature advanced reactor – FuSTAR is designed by Xi’an Jiaotong University with the support of the National Key Research and Development Program of China. To capture the thermal-hydraulics feedback and neutronics response of the FuSTAR under the steady-state and near-critical conditions. A three-dimensional core neutronics and thermal-hydraulics coupling simulation and analysis for FuSTAR based on STAR-CCM+ and MCNP are carried out. High fidelity modeling is used to carry out core neutronics calculation, and the thermal non-equilibrium porous media is used to carry out the core thermal-hydraulics calculation. The coupling computation and data transmission are completed automatically through the user code in STAR-CCM+. The coupling analysis shows that the overall temperature rise of coolant in FuSTAR is 50K, and the maximum fuel temperature is 1041.2K, which is lower than the thermal limitation. The feedback coefficient of coolant is negative, yet the effect is not significant. The feedback coefficient of fuel is negative because of the Doppler effect, which improves the inherent safety of the reactor. This analysis can provide the calculation reference for FuSTAR design and other deterministic method codes coupling analysis.

Original languageEnglish
Title of host publicationProceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3 - PBNC 2022
EditorsChengmin Liu
PublisherSpringer Science and Business Media Deutschland GmbH
Pages73-87
Number of pages15
ISBN (Print)9789811988981
DOIs
StatePublished - 2023
Event23rd Pacific Basin Nuclear Conference, PBNC 2022 - Chengdu, China
Duration: 1 Nov 20224 Nov 2022

Publication series

NameSpringer Proceedings in Physics
Volume285 SPPHY
ISSN (Print)0930-8989
ISSN (Electronic)1867-4941

Conference

Conference23rd Pacific Basin Nuclear Conference, PBNC 2022
Country/TerritoryChina
CityChengdu
Period1/11/224/11/22

Keywords

  • Coupling analysis
  • Neutronics
  • Porous media
  • Thermal-hydraulics

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