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Author Rammsy, J. M. ♦ Leal, L. C. ♦ Greene, N. M.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR REACTOR TECHNOLOGY ♦ PHYSICS ♦ NEUTRON SPECTRA ♦ ENERGY DEPENDENCE ♦ NUCLEAR DATA COLLECTIONS ♦ NEUTRON TRANSPORT ♦ CROSS SECTIONS ♦ REACTOR PHYSICS ♦ RESONANCE ABSORPTION ♦ RESONANCE INTEGRALS ♦ DOPPLER BROADENING
Abstract As accurate representation of the energy dependence of the neutron cross sections in the resolved resonance range is a fundamental issue in reactor physics and criticality safety applications. The prediction of the neutron population in a nuclear system such as a nuclear reactor, or the treatment of fissile material outside reactors, depends on how well the resonance absorption effect, determined by the resonance integral, is taken into account. In general, the resonance integral is calculated as where {sigma}(E) is the neutron cross section and {var_theta}(E) represents the energy dependence of the neutron spectrum. The evaluation of the resonance integral is usually performed by assuming that the resonance cross sections are isolated and represented by the single-level Breit-Wigner (SLBW) formalism. It is well known that the SLBW representation has limitations, as in the case of fission cross-section representations for fissile nuclides. Nevertheless, a feature that makes the SLBW formalism attractive for evaluating resonance integrals is that the temperature effect (Doppler effect) on the cross section can be described by a linear combination of the Voigt profiles, that is, the {phi} and x functions.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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