title: Brazilian gamma-neutron dosemeter: response to 241AmBe and 252Cf neutron sources.
abstract: With the aim of improving the monitoring of workers potentially exposed to neutron radiation in Brazil, the IPEN/CNEN-SP in association with PRO-RAD designed and developed a passive individual gamma-neutron mixed-field dosemeter calibrated to be used to (241)AmBe sources. To verify the dosimetry system response to different neutron spectra, prototypes were irradiated with a (252)Cf source and evaluated using the dose-calculation algorithm developed for (241)AmBe sources.
authors.affiliation: Instituto de Pesquisas Energéticas e Nucleares, CNEN-SP, Av Lineu Prestes 2242, 05508-000 São Paulo, Brazil. ebsouto@prorad.com.br
authors.forename: E B
authors.initials: EB
authors.lastname: Souto
authors.forename: L L
authors.initials: LL
authors.lastname: Campos
mesh_terms: D000465:Algorithms; D000576:Americium / Q000032:analysis*; D001608:Beryllium / Q000032:analysis*; D001938:Brazil; D002138:Calibration; D002142:Californium / Q000032:analysis*; D003627:Data Interpretation, Statistical; D005720:Gamma Rays; D006801:Humans; D009502:Neutrons; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000295:instrumentation* / Q000379:methods; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D011874:Radiometry / Q000295:instrumentation* / Q000379:methods; D013696:Temperature
chemical_list: D002142:Californium; D001608:Beryllium; D000576:Americium