SPECTER: neutron damage calculations for materials irradiations

Technical Report · Tue Jan 01 00:00:00 EST 1985

DOI:https://doi.org/10.2172/6022143· OSTI ID:6022143

Greenwood, L R; Smither, R K

Neutron displacement damage-energy cross sections have been calculated for 41 isotopes in the energy range from 10/sup -10/ to 20 MeV. Calculations were performed on a 100-point energy grid using nuclear cross sections from ENDF/B-V and the DISCS computer code. Elastic scattering is treated exactly including angular distributions from ENDF/B-V. 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,/sup 3/He) as (n,/sup 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 has been developed to simplify damage calculations. The user need only specify a neutron energy spectrum. SPECTER will then calculate spectral-averaged displacements, recoil spectra, gas production, and total damage energy (Kerma). The SPECTER computer code package is readily accessible to the fusion community via the National Magnetic Fusion Energy Computer Center (NMFECC) at Lawrence Livermore National laboratory.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6022143
• Report Number(s): ANL/FPP/TM-197; ON: DE85005791
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
THERMONUCLEAR REACTOR MATERIALS
NEUTRON REACTIONS
ANGULAR DISTRIBUTION
COMPUTER CALCULATIONS
CROSS SECTIONS
DATA COMPILATION
GAS PRODUCTION RATES
INELASTIC SCATTERING
MONTE CARLO METHOD
S CODES
THEORETICAL DATA
BARYON REACTIONS
COMPUTER CODES
DATA
DISTRIBUTION
HADRON REACTIONS
INFORMATION
MATERIALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
SCATTERING
700209* - Fusion Power Plant Technology- Component Development & Materials Testing