15 citations · 24 across the 4 of their papers we have counts for
4 papers
A comparison between two evaluations of neutron multiplicity distributions
J. P. Lestone
Within MCNP6, users can use multiplicity distributions for spontaneous and neutron-induced fission from an evaluation performed by Lestone (LA-UR-05-0288). This evaluation assumes…
Watt parameters for the Los Alamos Model : Subroutine getab
J. P. Lestone
Many neutron transport Monte-Carlo codes can randomly sample fission neutron energies from a Watt spectrum. The quality of simulations depends on how well the Watt spectrum represe…
Energy and Isotope Dependence of Neutron Multiplicity Distributions
J. P. Lestone
Fission neutron multiplicity distributions are known to be well reproduced by simple Gaussian distributions. Many previous evaluations of multiplicity distributions have adjusted t…
Subroutines to Simulate Fission Neutrons for Monte Carlo Transport Codes
J. P. Lestone
Fortran subroutines have been written to simulate the production of fission neutrons from the spontaneous fission of 252Cf and 240Pu, and from the thermal neutron induced fission o…