BS EN 61005-2004 pdf download.Radiation protection instrumentation Neutron ambient dose equivalent ( rate ) meters.
For assemblies with a substantially logarithmic graduation or with a digital presentation, the test shall be performed for at least three values in each decade of dose equivalent rate indicated. This shall be at about 20 %. 40 % and 80 % of each decade. A type test shall be carried out on at least one assembly of the series.
6.1.2.2 Routine test
For assemblies provided with substantially linear output, the routine test shall be performed at one point on each scale range between 50 % and 75 % of the scale maximum.
For assemblies with a substantially logarithmic output or a digital display, the routine test shall be performed for one value in each decade of the dose equivalent rate measured. A routine test shall be performed on each assembly of a series.
6.1.3 Use of reference neutron radiation sources
The tests shall be performed with one of the reference neutron radiation fields specified in 5.5.1. The conditions of use of these reference radiations shall be as specified by ISO 8529-1, ISO 8529-2, and ISO 8529-3. The conventional true value of the ambient dose equivalent at the point of test shall be known to within the uncertainty U = ±10 % (coverage factor 2) for each source used.
For this test, any uncertainty in the values of the fluence to ambient dose equivalent conversion coefficients listed in Annex A shall be ignored.
6.1.4 Test procedure with variation of the calibration distance
Several practical procedures are established in ISO 8529-2 to determine the response employing the reference neutron radiation source, taking into account the characteristic contribution of the scattered radiation to the indication, and the position of the reference point of the device. The procedures include the determination of indicated values at a series of calibration distances, where the indicated values may range over one or more orders of magnitude. Response, scatter contribution and geometry parameters are determined by data analytical fitting methods. In this case, any indicated value may count as a point in the respective scale ranges given in 6.1.2.1 and 6.1.2.2. For the determination of the intrinsic error in the respective scale range, the fitted indicated values may be employed, If the fitted values for the scatter and geometry parameters are in agreement with calculated andior experimentally determined experience values.
6.1.5 Equivalent electrical test method
In the event that the full range of ambient dose equivalent rates required for the above tests cannot be provided by the sources of neutron radiation available.
6.2.3.1 Dose equivalent rate alarm
At least two tests shall be carried out, one with the alarm set near to the maximum effective indicated value and one with the alarm set near to the maximum of the second least significant decade. Allowance shall be made for the uncertainty in the conventional true dose equivalent rate to which the dose equivalent (rate) meter is subjected. Where this is U %, the dose rates used shall be: 0,8(1 — 11/100) and 1,2(1 + U/i 00) of the dose equivalent alarm rate set point.
6.2.3.2 Dose equivalent alarm
At least two tests shall be carried out, one with the alarm set near to the maximum effective indicated value and one with the alarm set near to the maximum of the second least significant decade. The alarm shall be reset and then the dose equivalent meter shall be subjected to a conventionally true dose equivalent rate such that the alarm will not occur for at least 100 s. The time of exposure of the dose equivalent meter shall be measured and the following criteria shall be met: the quotient of the alarm set point by the product of the dose equivalent rate used and the measured time shall lie within the range 0,8(1 — U/100) to 1,2(1 + 11/100). where U is the percentage uncertainty in the conventionally true dose equivalent rate.
6.3 VarIation of response with neutron radiation energy
6.3.1 Requirements
For radiological protection purposes, it would be desirable for the variation of response with neutron energy over the defined energy range not to exceed 50 %. However, at the time of publication, it is not practicable to achieve this performance. Therefore, the manufacturer shall try to achieve the best practicable energy response and shall specify the energy response for at least the following energies.
As all existing devices and those being developed are essentially based on appropriate response calculations, the results of these calculations shall be made available for the entire energy range with data at least at two energy points per decade of radiation energy
Since it is impracticable to investigate the performance of an assembly and to validate the calculated data over nine decades of radiation energy from thermal neutrons up to 16 MeV, the following shall be used:
a) thermal neutrons;
b) at least one neutron energy in the energy range between 1 keV and 50 keV;
c) at least one neutron energy in the energy range between 50 keV and 600 key;
d) at least one neutron energy in the energy range between 1 MeV and 5 MeV;BS EN 61005-2004 pdf download.
BS EN 61005-2004 pdf download
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