Experimental and Monte Carlo evaluation of the neutron flux of an assembly with two AmBe sources.
This work aimed to determine the irradiator thermal (under-cadmium) and fast (over-cadmium) neutron fluxes, of the Nuclear Experimental Laboratory of the Nuclear Engineering Center (CNEN-IPEN, São Paulo, Brazil), and the possibility of this irradiator use for Neutron Activation Analysis (NAA), by the absolute method. To establish the facility specifications, the neutron flux values along the irradiator axis were determined experimentally and calculated by Monte Carlo method. The irradiator presents the advantage of supplying a stable neutron flux for a long period, eliminating the need to use standard material (comparative method), so that the process becomes agile, practical and economical.
Filho
Tufic Madi
TM
Instituto de Pesquisas Energéticas e Nucleares, IPEN/CNEN-SP, Cidade Universitária, Travessa R, 400 CEP 05508-900, São Paulo, SP, Brasil. tmfilho@ipen.br
de Lima
Ruy Barros
RB
Yoriyaz
Hélio
H
Hernandes
Antonio Carlos
AC
D000576:Americium / Q000032:analysis*; D001608:Beryllium / Q000032:analysis*; D017076:Computer-Aided Design; D004867:Equipment Design / Q000379:methods; D019544:Equipment Failure Analysis / Q000379:methods; D015233:Models, Statistical; D009010:Monte Carlo Method; D009502:Neutrons; D010315:Particle Accelerators / Q000295:instrumentation*; D011786:Quality Control; D011829:Radiation Dosage; D011868:Radioisotopes / Q000032:analysis*; D011874:Radiometry / Q000295:instrumentation / Q000379:methods*; D012542:Scattering, Radiation; D012984:Software
D011868:Radioisotopes; D001608:Beryllium; D000576:Americium