Calculation procedures for the analysis of integral experiments for fusion-reactor design [electronic resource].
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 48 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory
United States. Department of Energy. Office of Scientific and Technical Information
- The calculational models, nuclear data, and radiation transport codes that are used in the analysis of integral measurements of the transport of approx. 14 MeV neutrons through laminated slabs of materials typical of those found in fusion reactor shields are described. The two-dimensional discrete ordinates calculations to optimize the experimental configuration for reducing the neutron and gamma ray background levels and for obtaining an equivalent, reduced geometry of the calculational model to reduce computer core storage and running times are also presented. The equations and data to determine the energy-angle relations to neutrons produced in the reactions of 250 keV deuterons in a titanium-tritide target are given. The procedures used to collapse the 17ln-36..gamma.. VITAMIN C cross section data library to a 53n-21..gamma.. broad group library are described. Finally, a description of the computer code network used to obtain neutron and gamma ray energy spectra for comparison with measured data is included.
- Published through SciTech Connect.
Barnes, J.M.; Alsmiller, R.G. Jr.; Oblow, E.M.; Santoro, R.T.
- Funding Information:
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