SOME NEUTRON CROSS SECTIONS FOR MULTI-GROUP CALCULATIONS
Chapters 1 through 4 deal, respectively, with neutron diffusion data, neutron sensor data, inelastic scattering data, and photon activation data. Chapter 5 consists of a list of the references to the literature cited in the first four chapters. The neutron diffusion data consist of the absorption, scattering, transport, and slowing-down cross sections. The neutron sensor data are concerned with the activation cross section sigma /sub n, BETA -/ for the production of negative beta particles. The inelastic scattering data consist of the neutron inelastic scattering cross section, the spectrum of the inelastically scattered neutrons and the inelastic slowing-down cross section. The photon activation data consist of the neutron cross section for photon production sigma /sub n, gamma /, the total photon energy release and the photon energy distribution spectrum. All cross sections are reported as obtained and as group- averaged and digitalized cross sections. The group-averaged and digitalized cross sections are defined. The groups over which the cross sections were to be averaged, the averaging procedure, and the digitalization procedure were specified so that the results obtained would be readily usable in the GE reactor calculation procedure. In addition, therinal averages of the neutron diffusion cross sections are reported. (auth)
- Research Organization:
- Nuclear Development Corp. of America, White Plains, N.Y.
- DOE Contract Number:
- AF33(600)-38062; AND AT(11-1)-171; SUBCONTRACT AT-70
- NSA Number:
- NSA-13-009258
- OSTI ID:
- 4277189
- Report Number(s):
- APEX-467
- Resource Relation:
- Other Information: For General Electric Co. Aircraft Nuclear Propulsion Dept. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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