Predicting actual reactor conditions: Why timedomain simulation is necessary for BWR stability

Tomasz Kozlowski, Joanna Peltonen, Ivan Gajev, Viet Anh Phung, Sean Roshan

Research output: Contribution to journalArticle

Abstract

Despite two decades of development and successful use of coupled thermal-hydraulics/neutron-kinetics (TH/NK) codes for the analysis of design basis accidents, the application of coupled codes to BWR stability transients remains a formidable challenge. While the issues in physical models and numerical methods can be identified, quantified and managed through special developments and separate-effect tests, other aspects (e.g. coupling, modelling assumptions) can only be addressed through benchmarking on full plant stability tests. However, often incomplete information causes uncertainties, whose significance on the modelling and simulation must be evaluated. The objective of this paper is to define validation data needs that allow prediction of the transient behaviour should an unstable condition occur. It is shown that the confidence in exploiting advantageous features of the coupled TH/NK system codes in dealing with core-plant interaction, transient effects and local perturbations can only be evaluated with well-characterised, well-documented plant stability tests and stability events.

Original languageEnglish (US)
Pages (from-to)319-342
Number of pages24
JournalInternational Journal of Nuclear Energy Science and Technology
Volume7
Issue number4
DOIs
StatePublished - Jun 21 2013

Fingerprint

Neutrons
Hydraulics
Kinetics
Benchmarking
Numerical methods
Accidents
Hot Temperature
Uncertainty

Keywords

  • BWR stability
  • Coupled codes
  • RELAP5/PARCS
  • Reactor simulation
  • TH/NK
  • Time domain
  • Validation

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Predicting actual reactor conditions : Why timedomain simulation is necessary for BWR stability. / Kozlowski, Tomasz; Peltonen, Joanna; Gajev, Ivan; Phung, Viet Anh; Roshan, Sean.

In: International Journal of Nuclear Energy Science and Technology, Vol. 7, No. 4, 21.06.2013, p. 319-342.

Research output: Contribution to journalArticle

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