Accurate calculations of neutron kerma (Kinetic Energy Released in MAterials) and damage from ENDF/B-VI evaluations for silicon, chromium, iron and nickel, and comparison with ENDF/B-V results [electronic resource].
- Washington, D.C : United States. Dept. of Energy. Office of Energy Research, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: (11 pages) : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory
United States. Department of Energy. Office of Energy Research
United States. Department of Energy. Office of Scientific and Technical Information
- Accurate calculations of kerma (Kinetic Energy Released in MAterials) factors and displacement cross sections are fundamental to studies of neutron heating and neutron radiation damage. Damage and heating studies are important elements in both fission and fusion reactor design. For fusion reactor studies, heating in the blanket helps determine the efficiency, and heating studies in the superconducting magnet regions determine properties of the blanket and shield, thereby affecting the economics of the reactor. Radiation damage is important for reactor core lifetime studies and is related directly to the economy and safety of both fusion and fission reactors. Calculation of kerma factors and displacement cross sections require nuclear data for neutron-induced reactions. These data are normally obtained from evaluated nuclear data libraries, such as ENDF/B (US), JENDL (Japan), JEF/EFF (Europe) and BROND (USSR). Unfortunately, most of these evaluated libraries do not contain sufficient information for a direct calculation of these quantities, and various approximations must be employed. The accuracy of the kerma factors and displacement cross sections, and thus the heating and damage functions, are directly related to the available information from the data libraries. In this paper we describe improvements incorporated in the latest version of the US library, ENDF/B-VI, which allow exact calculations of these quantities for many of the structural materials included in the library. 11 refs., 6 figs.
- Published through SciTech Connect.
7. ASTM-EURATOM symposium on reactor dosimetry, Strasbourg (France), 27-31 Aug 1990.
MacFarlane, R.E.; Larson, D.C.; Fu, C.Y.; Hetrick, D.M.; Epperson, S.J.
- Funding Information:
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