SPECTER: Neutron damage calculations for materials irradiations
Abstract
Neutron displacement damageenergy cross sections were calculated for 41 isotopes in the energy range from 10(10) to 20 MeV. Elastic scattering is treated exactly including angular distributions from ENDF/BV. Inelastic scattering calculations consider both discrete and continuous nuclear level distributions. Multiple (n,xn) reactions use a Monte Carlo technique to derive the recoil distributions. The (n,d) and (n,t) reactions are treated as (n,p) and (n(3)He) as (n,(4)He). The (n,(GAMMA)) reaction and subsequent (BETA)decay are also included, using a new treatment of (GAMMA)(GAMMA) coincidences, angular correlations, (BETA)neutrino correlations, and the incident neutron energy. The Lindhard model was used to compute the energy available for nuclear displacement at each recoil energy. The SPECTER computer code was developed to simplify damage calculations. The user need only specify a neutron energy spectrum. SPECTER will then calculate spectralaveraged displacements, recoil spectra, gas production, and total damage energy (Kerma).
 Publication:

Unknown
 Pub Date:
 January 1985
 Bibcode:
 1985sndc.rept.....G
 Keywords:

 Angular Distribution;
 Inelastic Scattering;
 Monte Carlo Method;
 Neutron Cross Sections;
 Thermonuclear Power Generation;
 Computation;
 Computer Techniques;
 Data Processing;
 Scattering Cross Sections;
 Atomic and Molecular Physics