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Within MCNP6, users can use multiplicity distributions for spontaneous andneutron-induced fission from an evaluation performed by Lestone(LA-UR-05-0288). This evaluation assumes the multiplicity distributions areGaussian and adjusts the standard deviations to reproduce measured 2nd and 3rdfactorial moments. In MCNPX, users have the option of using multiplicitydistributions for spontaneous fission using an evaluation of the availableexperimental data by Santi and Miller (LA-UR-07-6229). The spontaneous fissionmultiplicity distributions and corresponding factorial moments from these twoevaluations are compared in the present paper. The differences are minor orwithin experimental errors for all but the spontaneous fission of 238Pu. The238Pu evaluations are based on data obtained in 1956. We recommend that the238Pu multiplicity distribution be re-measured. Given the good agreementbetween the two evaluations, the choice of evaluation will make littledifference for the modeling of spontaneous fission. However, we suggest thatthe evaluation in LA-UR-05-0288 be adopted as the MCNP default because it alsoincludes recommended distributions for neutron induced fission.

A comparison between two evaluations of neutron multiplicity distributions