GSO IEC 62387:2017
辐射防护仪器 用于个人和环境光子和 β 辐射监测的无源积分剂量测定系统

Radiation protection instrumentation - Passive integrating dosimetry systems for personal and environmental monitoring of photon and beta radiation

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标准号

GSO IEC 62387:2017

发布

2017年

发布单位

GSO

当前最新

GSO IEC 62387:2017

 

 

适用范围

This standard applies to all kinds of passive dosimetry systems that are used for measuring – the personal dose equivalent Hp(10) (for whole body dosimetry), – the personal dose equivalent Hp(3) (for eye lens dosimetry), – the personal dose equivalent Hp(0,07) (for both whole body and extremity dosimetry), – the ambient dose equivalent H*(10) (for environmental dosimetry), or – the directional dose equivalent H ’(0,07) (for environmental dosimetry). NOTE 1 The term “environmental dosimetry” means ambient, area, and environmental monitoring in this standard. This standard applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv and in the energy ranges given in Table 1. All the energy values are mean energies with respect to the prevailing dose quantity. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled. NOTE 2 In this standard, “dose” means dose equivalent, unless otherwise stated. NOTE 3 For Hp(10) and H*(10) no beta radiation is considered. Reasons: 1) Hp(10) and H*(10) are a conservative estimate for the effective dose which is not a suitable quantity for beta radiation. 2) No conversion coefficients are available in ICRU 56, ICRU 57 or ISO 6980-3. NOTE 4 The maximum energy ranges are the energy limits within which type tests according to this standard are possible. The test methods concerning the design (Clause 8), the instruction manual (Clause 9), the software (Clause 10), environmental influences (Clause 13), electromagnetic influences (Clause 14), mechanical influences (Clause 15), and the documentation (Clause 16) are independent of the type of radiation. Therefore, they can also be applied to other dosimetry systems, e.g. for neutrons, utilizing the corresponding type of radiation for testing. This standard is intended to be applied to dosimetry systems that are capable of evaluating doses in the required quantity and unit (Sv) from readout signals in any quantity and unit. The only correction that may be applied to the evaluated dose (indicated value) is the one resulting from natural background radiation using extra dosemeters. NOTE 5 The correction due to natural background can be made before or after the dose calculation.

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