Civil Engineering Design for Decommissioning of Nuclear Installations

Erscheinungsjahr 1984
ISBN: 978-0-86010-614-2
Verlag: Springer

Buch, Englisch, 104 Seiten, Format (B × H): 210 mm x 297 mm, Gewicht: 304 g

35 9.2 TYpical PWR Station Layout 36 9.3 Regions of Highest Radiological Hazard 38 9.4 Decommissioning Scenarios 40 9.5 Existing Structural Features of a PWR which may aid Decommissioning 42 9.6 Structural Features that might be introduced into Future PWR Stations to aid Decommissioning 43 10. REFERENCES 44 11. ACKNOWLEDGEMENTS 45 12. TABLES AND FIGURES 45 APPENDIX A - SUPPLEMENTARY INFORMATION 98 1 1. INTRODUCTION 1.1 This report describes the work carried out by Taylor Woodrow Construction Limited (!WC) in a study aimed at identifying features Which may be incorporated at the design stage of future nuclear power plants to facilitate their eventual decommissioning and, in so dOing, promote economic and radiological benefits at the decommissioning stage. 1.2 For the purposes of this study, decommissioning of a nuclear facility means those measures taken at the end of the facility's operating life to remove it from the site and restore the site to green field conditions, and, While so doing, ensure the continued protection of the public from any residual radioactivity or other potential hazards present in or emanating from the facility. The overall decommissioning process involves eventual dismantling and demolition and may also include, Where possible and appropriate, the intermediate steps of renewal and refurbishing.

Zielgruppe

Research

Autoren/Hrsg.

Paton, A.A.

Benwell, P.

Irwin, T.F.

Hunter, I.

Inhaltsverzeichnis

1. Introduction.- 2. Conclusions and Recommendations.- 2.1 Introduction.- 2.2 Gas Cooled Reactor Systems.- 2.3 Light Water Cooled Reactor Systems.- 2.4 Summary of Recommendations.- 3. Literature Review.- 4. Refurbishing.- 5. Problems of Decommissioning Gas Cooled Reactor Systems.- 5.1 Introduction.- 5.2 Technical Problems.- 5.3 Philosophical Problems.- 6. Possible Features to Aid Decommissioning of Gas Cooled Reactor Systems.- 6.1 Introduction.- 6.2 Reactor Core Shielding.- 6.3 Planes of Weakness.- 6.4 Features to Facilitate Forceful Break-up.- 6.5 Selective Use and Location of Materials.- 6.6 Removal of Liner and Penetrations.- 7. Planes of Weakness.- 7.1 Introduction.- 7.2 Service Load Conditions.- 7.3 Seismic Loading.- 7.4 Ultimate Load Conditions.- 7.5 Attachment of Liners.- 7.6 Formation of Planes of Weakness.- 8. Removal of Liner and Penetrations.- 8.1 Introduction.- 8.2 Freestanding Liners.- 8.3 Grouted Liners.- 8.4 Liner Insulation.- 8.5 Removal of Standpipes.- 9. Decommissioning of Light Water Cooled Reactor Systems.- 9.1 Introduction.- 9.2 Typical PWR Station Layout.- 9.3 Regions of Highest Radiological Hazard.- 9.4 Decommissioning Scenarios.- 9.5 Existing Structural Features of a PWR which may aid Decommissioning.- 9.6 Structural Features that might be introduced into Future PWR Stations to aid Decommissioning.- 10. References.- 11. Acknowledgements.- 12. Tables and Figures.- Appendix A — Supplementary Information.