Table of Contents

FOREWORD<br>PREFACE<br>1 Introduction<br>&nbsp;&nbsp;1.1 General<br>&nbsp;&nbsp;1.2 Scope<br>&nbsp;&nbsp;1.3 General characteristics<br>2 Neutron fluence rate (flux) measurement<br>3 Temperature measurement<br>4 Coolant measurement<br>5 Protection system

Abstract

Applicable more particularly to instrumentation for gas-cooled graphite-moderated reactors. Type 1: reactors having metallic natural uranium fuel clad with magnesium alloy, and Type 2: reactors having enriched uranium oxide fuel clad with stainless steel.

General Product Information

Published
Document Type	Standard
Status	Current
Publisher	International Electrotechnical Committee
Pages
ISBN
Committee	SC 45A