The ENEA fast neutron dosemeter is based on a planar PADC (Poly Allyl Diglicol Carbonate)placed in a polyethylene holder. The present paper reports the results of an experimental study of a CR-39 material with the addition of 0.l% of DOP (Dioctylphthalate) produced by the Italian company Intercast Europe S.p.A.The etching procedure is: pre-etching with 40% KOH water solution 6.25 N and 60% ethyl a1coholat 70°C followed by 12 hours of etching in 6.25 N KOH water solution. For the energy dependenceof response, dosemeters have been irradiated with neutron sources (241Am-Be, 252Cf, Pu-Li) andl4.9 MeV monoenergetic neutrons. The dosimetric performance of the material for fast neutrons isexpressed in terms of sensitivity, background value, lowest detectable dose and energy dependence of response. Moreover, the results of a quality acceptance test of the material, performed on 1l sheets (980x980 mm2, 1.4 mm thick) of the same production batch, are given. Therefore, the homogeneity of the neutron sensitivity and of the background signal within a sheet and the whole batch is considered. The results are compared with the acceptance test outcome for a CR39 standard material batch.

Performance of CR-39 with Addition of DOP (Dioctylphthalate) for Fast Neutron Dosimetry

Falangi, G.;Mariotti, F.;Fantuzzi, E.
2003

Abstract

The ENEA fast neutron dosemeter is based on a planar PADC (Poly Allyl Diglicol Carbonate)placed in a polyethylene holder. The present paper reports the results of an experimental study of a CR-39 material with the addition of 0.l% of DOP (Dioctylphthalate) produced by the Italian company Intercast Europe S.p.A.The etching procedure is: pre-etching with 40% KOH water solution 6.25 N and 60% ethyl a1coholat 70°C followed by 12 hours of etching in 6.25 N KOH water solution. For the energy dependenceof response, dosemeters have been irradiated with neutron sources (241Am-Be, 252Cf, Pu-Li) andl4.9 MeV monoenergetic neutrons. The dosimetric performance of the material for fast neutrons isexpressed in terms of sensitivity, background value, lowest detectable dose and energy dependence of response. Moreover, the results of a quality acceptance test of the material, performed on 1l sheets (980x980 mm2, 1.4 mm thick) of the same production batch, are given. Therefore, the homogeneity of the neutron sensitivity and of the background signal within a sheet and the whole batch is considered. The results are compared with the acceptance test outcome for a CR39 standard material batch.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/154
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