Abstract
MCNP6 has been Validated and Verified against intermediate- and high-energy fission cross-section experimental data. Recent improvements contained in CEM03.03F and MCNP6-F to consider precompound emission of heavy clusters up to 28 Mg has necessitated a re-calculation of fission cross sections. With our re-calculation, we find that CEM03.03F, which is used in MCNP6-F, predicts fission cross sections in good agreement with available experimental data for reactions induced by protons on both subactinide and actinide nuclei at incident energies from several tens of MeV to several GeV.
Highlights
The Monte Carlo Methods, Codes, and Applications group within the Computational Physics Division at Los Alamos National Laboratory has led the development of the transport code MCNP6 (Monte Carlo N-Particle transport code, version 6) [1]
MCNP6 is a generalpurpose, continuous-energy, generalized-geometry, timedependent, Monte-Carlo radiation-transport code designed to track many particle types over broad ranges of energies. It is used around the world in applications ranging from radiation protection and dosimetry, nuclear-reactor design, nuclear criticality safety, detector design and analysis, decontamination and decommissioning, accelerator applications, medical physics, space research, and beyond
MCNP6 with only the GENXS expansion contains none of the heavy cluster upgrades in CEM03.03F; MCNP6 with npreqtyp=6 contains the cross section and γ j upgrades but not the preequilibrium or a e-mail: kerblesl@isu.edu coalescence expansions; and MCNP6 with npreqtyp=66 contains all four CEM03.03F heavy cluster upgrades. These improvements in the precompound stages of our codes lead to changes in the distributions of Z, A, and E* at the beginning of the equilibrium decay phase, and mandated a refitting of the fission parameters. This paper addresses these new fission cross section calculations
Summary
The Monte Carlo Methods, Codes, and Applications group within the Computational Physics Division at Los Alamos National Laboratory has led the development of the transport code MCNP6 (Monte Carlo N-Particle transport code, version 6) [1]. CEM03.03 utilizes the Generalized Evaporation Model as implemented in the code GEM2 by Furihata [9] to calculate fission cross sections.
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