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IEC 60515:2007

Current

Current

The latest, up-to-date edition.

Nuclear power plants - Instrumentation important to safety - Radiation detectors - Characteristics and test methods

Available format(s)

Hardcopy , PDF , PDF 3 Users , PDF 5 Users , PDF 9 Users

Language(s)

English - French

Published date

23-02-2007

€280.71
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FOREWORD
INTRODUCTION
1 Scope
2 Normative references
3 Terms and definitions
4 Abbreviations
5 Functions of an ex-core detection system
6 Neutron sensitive materials
7 Description of different types of detectors
   7.1 General
   7.2 Neutron sensitive proportional counters
   7.3 Ionization chambers
8 More detailed factors which influence the use and testing
   of neutron detectors
   8.1 Pulse mode neutron detectors
   8.2 Current mode neutron detectors
9 General principles for detector operation
   9.1 Detection basis conditions
   9.2 Detector operating conditions
   9.3 Limits due to the detector
   9.4 Limits due to the measuring channel
   9.5 Limits due to surrounding gamma radiation
10 Connectors and cables
11 Characteristics of detectors including their cables
   and connectors
   11.1 General
   11.2 Detector mechanical data
   11.3 Detector electrical and nuclear data
   11.4 Connector mechanical data
   11.5 Connector electrical characteristics
   11.6 Cable mechanical data
   11.7 Cable electrical characteristics
12 Test methods - general
13 Factory tests
   13.1 General
   13.2 List of typical factory tests
   13.3 Mechanical tests
   13.4 Specific tests for fission counters
   13.5 Specific tests for proportional counter tubes
   13.6 Specific tests for compensated ionization chambers
   13.7 Specific tests for uncompensated neutron sensitive
        d.c. ionization chambers
   13.8 Specific tests for d.c. ionization chambers for
        gamma radiation
   13.9 Specific test for current fluctuation (Campbelling)
        fission chambers
14 Qualification tests
   14.1 Principles
   14.2 Test sequence on a detector
   14.3 Test for environmental conditions
   14.4 Seismic tests
Bibliography

Describes characteristics and tests methods for gas-filled radiation detectors used for the protection of nuclear reactors. Applies to the radiation detectors which are installed external to the core of nuclear reactors and which provide electrical input signals to the reactor's control and instrumentation system.

Committee
TC 45/SC 45A
DevelopmentNote
Stability Date: 2018. (09/2017)
DocumentType
Standard
Pages
81
PublisherName
International Electrotechnical Committee
Status
Current
Supersedes

Standards Relationship
BS IEC 60515:2007 Identical
IS 11797 : 2018 Identical
CEI 45-19 : 1997 Identical
NEN 10515 : 1977 Identical

04/30078159 DC : DRAFT JUN 2004
IEC 61468:2000 Nuclear power plants - In-core instrumentation - Characteristics and test methods of self-powered neutron detectors
BS IEC 61468:2000 Nuclear power plants. In-core instrumentation. Characteristics and test methods of self-powered neutron detectors
BS IEC 61501:1998 Nuclear reactor instrumentation. Wide range neutron fluence rate meter. Mean square voltage method

IEC 60050-394:2007 International Electrotechnical Vocabulary (IEV) - Part 394: Nuclear instrumentation - Instruments, systems, equipment and detectors
IEC 61468:2000 Nuclear power plants - In-core instrumentation - Characteristics and test methods of self-powered neutron detectors
IEC 61226:2009 Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions
IEC 60980:1989 Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations
IEC 60780:1998 Nuclear power plants - Electrical equipment of the safety system - Qualification
IEC 61501:1998 Nuclear reactor instrumentation - Wide range neutron fluence rate meter - Mean square voltage method
IEC 60050-393:2003 International Electrotechnical Vocabulary (IEV) - Part 393: Nuclear instrumentation - Physical phenomena and basic concepts
IEC 60568:2006 Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors

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