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Safety of Thermal Water Reactors

Proceedings of a Seminar on the Results of the European Communities’ Indirect Action Research Programme on Safety of Thermal Water Reactors, Held in Brussels, 1–3 October 1984

  • E. Skupinski
  • B. Tolley
  • J. Vilain

Table of contents

  1. Front Matter
    Pages i-xi
  2. Introduction

    1. E. Skupinski, B. Tolley, J. Vilain
      Pages 1-1
  3. Abbreviations

    1. E. Skupinski, B. Tolley, J. Vilain
      Pages 3-4
  4. Opening plenary session

  5. Parallel sessions Research Area A

    1. Front Matter
      Pages 21-21
    2. Session A1

    3. Session A2

    4. Session A3

    5. Session A4

  6. Parallel sessions Research Area B

    1. Front Matter
      Pages 201-201
    2. Session B1

      1. J. McQuaid, B. Roebuck, D. G. Wilde
        Pages 179-189
    3. Session B2

    4. Session B3

    5. Session B4

  7. Parallel Sessions Research Area C

    1. Front Matter
      Pages 351-351
    2. Session C1

      1. B. Y. Underwood, P. J. Cooper, N. J. Holloway, G. D. Kaiser, W. Nixon
        Pages 353-367
      2. P. M. Foster, A. G. Robins
        Pages 369-382
    3. Session C2

    4. Session C3

    5. Session C4

About these proceedings

Introduction

The European Community's Indirect Action Research Programme on the Safety of Thermal Water Reactors had as main obj ectives to execute useful fundamental research, complementary and confirmatory to on-going work in national programmes, and to improve collaboration and exchange of inform­ ation between laboratories in the Member States. The Seminar was aimed to report on work performed during the last five years and to identify useful further research areas with a tentative assessment of the state of the art for future work in certain issues of LWR-safety. The results obtained in 33 research projects executed in different national laboratories of the European Community were presented, evaluated and discussed, together with a number of invited papers on topics related to the research programme. Topics covered mainly within 3 distinct research areas or sub-programmes: Research Area A: The loss of coolant accident (LOCA) and the func­ tioning and performance of the emergency core cooling system (ECCS). Fundamental work on thermalhydraulics and heat transfer during refill and reflood of an uncovered core after a LOCA. Research Area B: The protection of nuclear power plants against external gas cloud explosions. Study of the impact on plant structure and systems of external explosions of dense combustible gas clouds due to accidental releases of hydro­ carbons in the vicinity of the plant. Research Area C: The release and distribution of radioactive fission products in the atmosphere following a reactor accident.

Keywords

Simulation element fission nuclear reactor

Editors and affiliations

  • E. Skupinski
    • 1
  • B. Tolley
    • 1
  • J. Vilain
    • 1
  1. 1.Directorate-General Science, Research and DevelopmentCommission of the European CommunitiesBrusselsBelgium

Bibliographic information

  • DOI https://doi.org/10.1007/978-94-009-4972-0
  • Copyright Information Springer Science+Business Media B.V. 1985
  • Publisher Name Springer, Dordrecht
  • eBook Packages Springer Book Archive
  • Print ISBN 978-94-010-8701-8
  • Online ISBN 978-94-009-4972-0
  • Buy this book on publisher's site