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Progress in Integral Data and Their Accuracy: Average Neutron Cross Sections in the Californium-252 Benchmark Field

W. Mannhart

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 40-50

Technical Paper / dx.doi.org/10.13182/NSE81-A21337

A summary of measurements and calculations of spectrum-averaged neutron cross sections in the benchmark field of 252Cf spontaneous fission neutrons is given. The need for and the concept of a reliable treatment of uncertainties in comparing measurements and calculations with the objective of neutron cross-section validation is discussed.