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IEC TR 62235 : 1.0

IEC TR 62235 : 1.0

NUCLEAR FACILITIES - INSTRUMENTATION AND CONTROL SYSTEMS IMPORTANT TO SAFETY - SYSTEMS OF INTERIM STORAGE AND FINAL REPOSITORY OF NUCLEAR FUEL AND WASTE

International Electrotechnical Committee

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Table of Contents

FOREWORD<br>INTRODUCTION<br>1 Scope<br>2 Terms and definitions <br>3 General survey of existing practices<br>4 Description of the different applications<br>&nbsp;&nbsp;4.1 Storage at nuclear power plants<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.1.1 Dry storage of spent nuclear fuel<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.1.2 Storage of radioactive operational and <br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;decommissioning waste<br>&nbsp;&nbsp;4.2 Storage at interim storage facilities<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.2.1 Wet storage of spent nuclear fuel (examples <br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;from Sweden)<br>&nbsp;&nbsp;4.3 Storage at reprocessing facilities<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.3.1 Wet storage of spent nuclear fuel <br>&nbsp;&nbsp;4.4 Final repositories for radioactive operational and <br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;decommissioning waste<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.4.1 Example of Sweden: Description of the facility<br>&nbsp;&nbsp;4.5 Packaging<br>&nbsp;&nbsp;4.6 Retrievable repositories for spent nuclear fuel<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.6.1 Deep repositories in granite<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.6.2 Repository in a volcanic mountain<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.6.3 Repository in clay <br>&nbsp;&nbsp;4.7 Transportation<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.7.1 Land carriage of spent nuclear fuel<br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;4.7.2 Sea carriage of spent nuclear fuel and <br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;radioactive operational waste (for example, <br>&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;from Sweden)<br>5 Conclusions<br>Bibliography

Abstract

Provides guidelines for the instrumentation and control (I&C) systems of interim storage and final repository of nuclear fuel and waste, regardless of the origin of the stored material.

General Product Information

Document Type Standard
Status Current
Publisher International Electrotechnical Committee
Committee TC 45

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