61031-1990
Design@ Location and Application Criteria for Installed Area Gamma Radiation Dose Rate Monitoring Equipment for Use in Nuclear Power Plants During Normal Operation and Anticipated Operational Occurrences (Edition 1.0)

Critères de conception@ d?implantation et d?application pour les matériels de surveillance du débit de dose de rayonnement gamma à poste fixe@ utilisés dans les centrales nucléaires pendant le fonctionnement normal et lors d?incidents de fonctionnement pr

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标准号

61031-1990

发布日期

1990年06月01日

实施日期

1969年12月31日

废止日期

无

中国标准分类号

/

国际标准分类号

/

发布单位

IEC - International Electrotechnical Commission

引用标准

26

适用范围

This International Standard applies to the design@ location and application of installed equipment for monitoring local gamma radiation dose rates within nuclear power plants during normal operation and anticipated operational occurrences. High range area gamma radiation dose rate monitoring equipment for accident conditions currently addressed by IEC 951-3 is not within the scope of this standard. This standard is intended to be used in conjunction with IEC 532 (second edition)* NOTE - This standard does not apply to the measurement of neutron dose rate. Additional equipment for neutron monitoring may be required@ depending on the plant design@ if the neutron dose rate makes a substantial contribution to the total dose equivalent to personnel. This standard provides guidelines for the design principles@ the location@ the application@ the calibration@ the operation@ and the testing of installed equipment for continuously monitoring local gamma radiation dose rates in nuclear power plants under normal operation conditions and anticipated operational occurrences. These instruments are normally referred to as area radiation monitors. Radiation monitors utilized in area radiation monitoring equipment are dealt with IEC 532. As discussed in that standard@ measurement of gamma radiation may be expressed by a number of alternative quantities depending on national regulations. However@ for this type of instrument@ the most likely quantity to be measured is the absorbed dose in air (Gy)@ or the ambient dose equivalent (Sv). * References to IEC 532 appearing in this standard concern the 2nd edition@ which is in preparation.