Spectrum-Averaged Neutron Fluence-to-Dose Conversion Coefficients of 252Cf, 252Cf/D2O, 241AmB, 241AmBe and 239PuBe Neutron Sources, Using the New Dosimetric Quantities of ICRP/ICRU

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The spectrum-averaged neutron fluence-to-ambient dose conversion coefficient for 252Cf, 252Cf/D2O, 241AmB, 241AmBe and 239PuBe neutron sources were calculated using the neutron fluence-to-dose conversion coefficients for the personal dose and the ambient dose which are the new dosimetric quantities, defined in the ICRP/ICRU joint report. One of the goals of defining these new dosimetric quantities is to harmonize the operational quantities with the protection quantities. By using Monte Carlo methods the spectra of the neutron sources and the total fluences were estimated, with the spectra and the neutron fluence-to- dose conversion coefficients the ambient and the personal dose were estimated. These values where normalized to the total neutron fluence to obtain the spectrum-averaged neutron fluence-to-dose conversion coefficients that were compared with those obtained for the H*(10), Hp,s(10,0°) and EAP using the coefficients from the ICRP 74 and the ICRP 116. For 10-9 to 20 MeV neutrons, the new dosimetric quantities the operational and the protection quantities are harmonized.

​The spectrum-averaged neutron fluence-to-ambient dose conversion coefficient for 252Cf, 252Cf/D2O, 241AmB, 241AmBe and 239PuBe neutron sources were calculated using the neutron fluence-to-dose conversion coefficients for the personal dose and the ambient dose which are the new dosimetric quantities, defined in the ICRP/ICRU joint report. One of the goals of defining these new dosimetric quantities is to harmonize the operational quantities with the protection quantities. By using Monte Carlo methods the spectra of the neutron sources and the total fluences were estimated, with the spectra and the neutron fluence-to- dose conversion coefficients the ambient and the personal dose were estimated. These values where normalized to the total neutron fluence to obtain the spectrum-averaged neutron fluence-to-dose conversion coefficients that were compared with those obtained for the H*(10), Hp,s(10,0°) and EAP using the coefficients from the ICRP 74 and the ICRP 116. For 10-9 to 20 MeV neutrons, the new dosimetric quantities the operational and the protection quantities are harmonized. Read More