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Average Neutron Cross Sections in the Unresolved Resonance Range

Mendel Beer

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 171-173

Technical Note / dx.doi.org/10.13182/NSE73-A23242

A method is presented for calculating neutron cross sections averaged over the partial width fluctuations in the unresolved resonance range. The N dimensional integral (N ≤ 4) which appears in the averaging procedure is mathematically reduced to integration in a single dimension. The resultant expression is numerically evaluated by a Gaussian quadrature technique.