Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility

A. Bucalossi, A. Del Nevo, F. Moretti, F. D'Auria, I.V. Elkin, O.I. Melikhov

Research output: Contribution to journalArticle

7 Citations (Scopus)

Abstract

VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side fluid inventory, horizontal steam generators, core design) that require dedicated experimental and analytical analyses in order to assess the performance of safety systems and the effectiveness of possible accident management strategies. The European Commission funded project "TACIS 2.03/97", Part A, provided valuable experimental data from the large-scale (1:300) PSB-VVER test facility, investigating accident management procedures in VVER-1000 reactor. A test matrix was developed at University of Pisa (responsible of the project) with the objective of obtaining the experimental data not covered by the OECD VVER validation matrix and with main focus on accident management procedures. Scenarios related to total loss of feed water and station blackout are investigated by means of four experiments accounting for different countermeasures, based on secondary cooling strategies and primary feed and bleed procedures. The transients are analyzed thoroughly focusing on the identification of phenomena that will challenge the code models during the simulations. © 2012 Elsevier B.V.
Original languageEnglish
Pages (from-to)633 - 645
Number of pages13
JournalNuclear Engineering and Design
Volume250
DOIs
Publication statusPublished - Sep 2012
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

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