# SPECTER: neutron damage calculations for materials irradiations

## Abstract

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.

- Authors:

- Publication Date:

- Research Org.:
- Argonne National Lab., IL (USA)

- OSTI Identifier:
- 6022143

- Report Number(s):
- ANL/FPP/TM-197

ON: DE85005791

- DOE Contract Number:
- W-31-109-ENG-38

- Resource Type:
- Technical Report

- Country of Publication:
- United States

- Language:
- English

- Subject:
- 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

### Citation Formats

```
Greenwood, L.R., and Smither, R.K..
```*SPECTER: neutron damage calculations for materials irradiations*. United States: N. p., 1985.
Web. doi:10.2172/6022143.

```
Greenwood, L.R., & Smither, R.K..
```*SPECTER: neutron damage calculations for materials irradiations*. United States. doi:10.2172/6022143.

```
Greenwood, L.R., and Smither, R.K.. Tue .
"SPECTER: neutron damage calculations for materials irradiations". United States.
doi:10.2172/6022143. https://www.osti.gov/servlets/purl/6022143.
```

```
@article{osti_6022143,
```

title = {SPECTER: neutron damage calculations for materials irradiations},

author = {Greenwood, L.R. and Smither, R.K.},

abstractNote = {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.},

doi = {10.2172/6022143},

journal = {},

number = ,

volume = ,

place = {United States},

year = {Tue Jan 01 00:00:00 EST 1985},

month = {Tue Jan 01 00:00:00 EST 1985}

}