Core design study for a small modular boiling water reactor

Andhika Feri Wibisono, Eugene Shwageraus

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

Abstract

The hybrid Small Modular Boiling Water Reactor (SMBWR) is a new conceptual design of BWR-type SMR. The main features of SMBWR include a natural circulation loop in its coolant recirculation system and external superheaters system integrated into the steam cycle. A full core analysis of SMBWR is performed with the nodal diffusion code PANTHER using homogenised constant libraries generated by WIMS. The study compared a number of core geometry configurations and fuel management schemes to suppress excess reactivity throughout fuel depletion. Three options for SMBWR core aspect ratio using the same power density are investigated with the aim to assess the effect on the neutronic and thermal-hydraulic performance of the SMBWR. It is found that the thin and tall core configuration (192 fuel assemblies and 3.60 m) showed the least favourable performance out of the three options as it has the largest core pressure drop and thus requires taller chimney to develop natural circulation.

Original languageEnglish
Title of host publicationInternational Conference on Physics of Reactors
Subtitle of host publicationTransition to a Scalable Nuclear Future, PHYSOR 2020
EditorsMarat Margulis, Partrick Blaise
PublisherEDP Sciences - Web of Conferences
Pages2809-2817
Number of pages9
ISBN (Electronic)9781713827245
DOIs
StatePublished - 1 Jan 2020
Externally publishedYes
Event2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 - Cambridge, United Kingdom
Duration: 28 Mar 20202 Apr 2020

Publication series

NameInternational Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
Volume2020-March

Conference

Conference2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
Country/TerritoryUnited Kingdom
CityCambridge
Period28/03/202/04/20

Keywords

  • Excess reactivity
  • Full core analysis
  • Moderator temperature variation
  • Small modular boiling water reactor

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Nuclear and High Energy Physics
  • Radiation

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