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Homepage>BS Standards>13 ENVIRONMENT. HEALTH PROTECTION. SAFETY>13.280 Radiation protection>BS EN 62387:2016 Radiation protection instrumentation. Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation
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BS EN 62387:2016 Radiation protection instrumentation. Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation

BS EN 62387:2016

Radiation protection instrumentation. Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation

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Standard number:BS EN 62387:2016
Pages:88
Released:2016-03-31
ISBN:978 0 580 86060 7
Status:Standard
DESCRIPTION

BS EN 62387:2016


This standard BS EN 62387:2016 Radiation protection instrumentation. Passive integrating dosimetry systems for individual, workplace and environmental monitoring of photon and beta radiation is classified in these ICS categories:
  • 13.280 Radiation protection

This standard applies to all kinds of passive dosimetry systems that are used for measuring

  • the personal dose equivalent H p(10) (for whole body dosimetry),

  • the personal dose equivalent H p(3) (for eye lens dosimetry),

  • the personal dose equivalent H p(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).

Text deleted

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.

Table 1
Mandatory and maximum energy ranges covered by this standard
Measuring quantity Mandatory energy range for photon radiation Maximum energy range for testing photon radiation Mandatory energy range for beta-particle radiationa Maximum energy range for testing beta-particle radiation a

H p(10),

H*(10)

80 keV to 1,25 MeV 12 keV to 10 MeV
H p(3) 30 keV to 250 keV 8 keV to 10 MeV 0,8 MeV almost equivalent to an E max of 2,27 MeV 0,7 MeV b to 1,2 MeV almost equivalent to E max from 2,27 MeV to 3,54 MeV

H p(0,07),

H’(0,07)

30 keV to 250 keV 8 keV to 10 MeV 0,8 MeV almost equivalent to an E max of 2,27 MeV 0,06 MeV c to 1,2 MeV almost equivalent to E max from 0,225 MeV to 3,54 MeV
a

The following beta radiation source are suggested for the different mean energies: For 0,06 MeV: 147Pm; for 0,8 MeV: 90Sr/ 90Y; for 1,2 Mev: 106Ru/ 106Rh.

b

For beta-particle radiation, an energy of 0,7 MeV is required to reach the radiation sensitive layers of the eye lens in a depth of about 3 mm (approximately 3 mm of ICRU tissue).

c

For beta-particle radiation, an energy of 0,07 MeV is required to penetrate the dead layer of skin of 0,07 mm (approximately 0,07 mm of ICRU tissue).

NOTE 2

In this standard, “dose” means dose equivalent, unless otherwise stated.

NOTE 3

For  H p(10) and  H*(10) no beta radiation is considered. Reasons: 1)  H p(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.