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New Neutron Cross-Section Measurements on 19F, 39,41K, 55Mn, and 103Rh for Improved Nuclear Criticality Safety

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A series of new measurements has been undertaken in response to deficiencies identified in nuclear data libraries of crucial importance to the Nuclear Criticality Safety Program as well as for burnup credit studies involving the transportation of spent nuclear fuel. New data and evaluations including covariances are required for several stable fission products as well as for materials found in mixtures with uranium.
2007-01-29
American Nuclear Society
JRC36254
https://publications.jrc.ec.europa.eu/repository/handle/JRC36254,   
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