A model of the 14MeV neutrons source term, for numerical solution of the transport equation to be used in BNCT simulation

• Published in: Annals of nuclear energy Vol. 42; pp. 161 - 164
• Main Authors: Orengo, Gilberto, de Oliveira Graça, Claudio
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.04.2012
• Subjects: ANISN; D–T reaction; Neutron generator; Neutron transport; Neutron generator; Neutron transport; D–T reaction; ANISN
• ISSN: 0306-4549; 1873-2100
• DOI: 10.1016/j.anucene.2011.12.008

[Display omitted] ► We model a neutrons source term to use in neutron transport calculation. ► This model is important to simulate the neutron source in neutron generator. ► The neutron generators are important to produce neutrons of 14MeV to use in a medical center. The use of neutron generators has been growing with the development of Neutron Capture Therapies (NCTs), mainly in Boron Neutron Capture Therapy (BNCT). In the absence of nuclear reactors in Brazil the neutron generators plays an important role for medical application. So the neutron transport calculation and neutron generators experiment analysis is very important to implement BNCT in Brazil. The aim of this work was to develop a method of calculating the 14MeV neutron angular and energetic distribution for the D–T reaction in realistic conditions to compare with experimental data produced in our Neutron Generator Laboratory. The angular and energetic spectrum is obtained in a format as input for the discrete ordinates method used to solve the neutron transport equations, ANISN, DORT and TORT are the codes that will be used for this purpose.