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Titlebook: Civil Engineering Design for Decommissioning of Nuclear Installations; A. A. Paton,P. Benwell,I. Hunter Book 1984 ECSC, EEC, EAEC, Brussel

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書目名稱Civil Engineering Design for Decommissioning of Nuclear Installations
編輯A. A. Paton,P. Benwell,I. Hunter
視頻videohttp://file.papertrans.cn/227/226870/226870.mp4
圖書封面Titlebook: Civil Engineering Design for Decommissioning of Nuclear Installations;  A. A. Paton,P. Benwell,I. Hunter Book 1984 ECSC, EEC, EAEC, Brussel
描述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 e
出版日期Book 1984
關鍵詞Tore; civil engineering; construction; design; engine; engineering design; information; material; materials;
版次1
doihttps://doi.org/10.1007/978-94-009-5632-2
isbn_softcover978-0-86010-614-2
isbn_ebook978-94-009-5632-2
copyrightECSC, EEC, EAEC, Brussels and Luxembourg 1984
The information of publication is updating

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Problems of Decommissioning Gas Cooled Reactor Systems,nced gas cooled reactor system. The magnox reactor systems utilise single cavity pressure vessels, the earlier ones being of steel construction, the later ones of prestressed concrete. The advanced gas cooled reactor systems utilise either single cavity or multicavity pressure vessels of prestressed
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Book 1984ting 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 e
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