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<p>This part of ISO 8529 specifies the reference neutron radiations, in the energy range from thermal up to 20 MeV,</p>
<p>for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response</p>
<p>as a function of neutron energy. Reference radiations are given for neutron fluence rates of up to 1 _ 109 m?2_s?1,</p>
<p>corresponding, at a neutron energy of 1 MeV, to dose-equivalent rates of up to 100 mSv_h?1.</p>
<p>This part of ISO 8529 is concerned only with the methods of producing and characterizing the neutron reference</p>
<p>radiations. The procedures for applying these radiations for calibrations are described in ISO 8529-2 and</p>
<p>ISO 8529-3.</p>
<p>The reference radiations specified are the following:</p>
<p>_ neutrons from radionuclide sources, including neutrons from sources in a moderator;</p>
<p>_ neutrons produced by nuclear reactions with charged particles from accelerators;</p>
<p>_ neutrons from reactors.</p>
<p>In view of the methods of production and use of them, these reference radiations are divided, for the purposes of</p>
<p>this part of ISO 8529, into the following two separate sections.</p>
<p>_ In clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutronmeasuring</p>
<p>devices. These sources should be used by laboratories engaged in the routine calibration of</p>
<p>neutron-measuring devices, the particular design of which has already been type tested.</p>
<p>_ In clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasi</p>
<p>monoenergetic spectra are specified for determining the response of neutron-measuring devices as a function</p>
<p>of neutron energy. Since these reference radiations are produced at specialized and well equipped</p>
<p>laboratories, only the minimum of experimental detail is given.</p>
<p>For the conversion of neutron fluence into the quantities recommended for radiation protection purposes,</p>
<p>conversion coefficients have been calculated based on the spectra presented in normative annex A and using the</p>
<p>fluence-to-dose-equivalent conversion coefficients as a function of neutron energy as given in ICRP Publication 74</p>
<p>and ICRU Report 57.</p>
Reģistrācijas numurs (WIID)
25666
Darbības sfēra
<p>This part of ISO 8529 specifies the reference neutron radiations, in the energy range from thermal up to 20 MeV,</p>
<p>for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response</p>
<p>as a function of neutron energy. Reference radiations are given for neutron fluence rates of up to 1 _ 109 m?2_s?1,</p>
<p>corresponding, at a neutron energy of 1 MeV, to dose-equivalent rates of up to 100 mSv_h?1.</p>
<p>This part of ISO 8529 is concerned only with the methods of producing and characterizing the neutron reference</p>
<p>radiations. The procedures for applying these radiations for calibrations are described in ISO 8529-2 and</p>
<p>ISO 8529-3.</p>
<p>The reference radiations specified are the following:</p>
<p>_ neutrons from radionuclide sources, including neutrons from sources in a moderator;</p>
<p>_ neutrons produced by nuclear reactions with charged particles from accelerators;</p>
<p>_ neutrons from reactors.</p>
<p>In view of the methods of production and use of them, these reference radiations are divided, for the purposes of</p>
<p>this part of ISO 8529, into the following two separate sections.</p>
<p>_ In clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutronmeasuring</p>
<p>devices. These sources should be used by laboratories engaged in the routine calibration of</p>
<p>neutron-measuring devices, the particular design of which has already been type tested.</p>
<p>_ In clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasi</p>
<p>monoenergetic spectra are specified for determining the response of neutron-measuring devices as a function</p>
<p>of neutron energy. Since these reference radiations are produced at specialized and well equipped</p>
<p>laboratories, only the minimum of experimental detail is given.</p>
<p>For the conversion of neutron fluence into the quantities recommended for radiation protection purposes,</p>
<p>conversion coefficients have been calculated based on the spectra presented in normative annex A and using the</p>
<p>fluence-to-dose-equivalent conversion coefficients as a function of neutron energy as given in ICRP Publication 74</p>
<p>and ICRU Report 57.</p>
