An evaluation model to predict steam concentration in a BWR reactor building

Masahiro Kondo, Kimitoshi Yoneda, Masahiro Furuya, Yoshihisa Nishi

Research output: Contribution to journalArticle

3 Citations (Scopus)

Abstract

When there is no power for cooling the spent fuel pool and conditioning the air in a boiling water reactor (BWR) reactor building, water vapor is generated from the pool and it affects the atmosphere in the building. To consider the impact of the steam in preparing emergency operation procedures, the building atmosphere under various conditions is to be evaluated with reasonably low computational cost. A lumped parameter model to predict the transient behavior of the building atmosphere was developed, in which the evaporation from the spent fuel pool and the condensation to the wall were taken into consideration. A transient behavior of temperature and vapor concentration in a BWR operating floor was predicted with the model. The results and the prediction speed were compared to those of a three-dimensional computational fluid dynamic calculation, and it was confirmed that the model could obtain almost the same results about 280,000 times faster. Parameter studies are conducted with the model, and dominant parameters to the evaporation and the condensation were clarified.

Original languageEnglish
Pages (from-to)1369-1382
Number of pages14
JournalJournal of Nuclear Science and Technology
Volume52
Issue number11
DOIs
Publication statusPublished - 2015 Nov 2
Externally publishedYes

Fingerprint

boiling water reactors
Boiling water reactors
steam
Steam
reactors
spent fuels
evaluation
Spent fuels
atmospheres
Condensation
Evaporation
condensation
evaporation
emergencies
conditioning
computational fluid dynamics
Water vapor
water vapor
Computational fluid dynamics
Vapors

Keywords

  • computational fluid dynamics
  • evaporation/condensation
  • lumped parameter
  • nuclear power plant
  • numerical analysis
  • reactor building
  • severe accident
  • spent fuel pool
  • station blackout
  • thermal hydraulics

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

An evaluation model to predict steam concentration in a BWR reactor building. / Kondo, Masahiro; Yoneda, Kimitoshi; Furuya, Masahiro; Nishi, Yoshihisa.

In: Journal of Nuclear Science and Technology, Vol. 52, No. 11, 02.11.2015, p. 1369-1382.

Research output: Contribution to journalArticle

Kondo, Masahiro ; Yoneda, Kimitoshi ; Furuya, Masahiro ; Nishi, Yoshihisa. / An evaluation model to predict steam concentration in a BWR reactor building. In: Journal of Nuclear Science and Technology. 2015 ; Vol. 52, No. 11. pp. 1369-1382.
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