SUMMARY
14MeV neutrons in MCNP interact with carbon without producing alpha particles or protons, as confirmed by user experiences with various cross-section data sources including ENDFB8/B7.1, JEFF3.3, JENDL5, and CENDL3.2. The correct configuration requires setting the 7th parameter of the “phys:n” and “phys:p” cards to 1 for proper recoil and proton transport. Additionally, to enhance secondary alpha release, the INCL4/ABLA model must be activated with the LCA card, specifically setting the 9th entry “icem” to 2. Users have reported discrepancies between MCNP and PHITS results, indicating potential issues with model settings or missing cross-section tables.
PREREQUISITES
- Familiarity with MCNP (Monte Carlo N-Particle Transport Code) version 6.1
- Understanding of neutron interaction physics and cross-section data
- Knowledge of the INCL4/ABLA model for nuclear reactions
- Experience with configuring MCNP input cards, specifically “phys:n”, “phys:p”, and “cut:h”
NEXT STEPS
- Investigate the configuration of the “phys:n” and “phys:p” cards in MCNP for neutron and photon transport
- Learn how to plot cross-section data to identify potential issues in MCNP simulations
- Explore the differences between MCNP and PHITS results to understand discrepancies in alpha particle transport
- Review the documentation for the INCL4/ABLA model to optimize its implementation in MCNP
USEFUL FOR
Researchers and practitioners in nuclear physics, radiation transport simulation, and those specifically working with MCNP for neutron interactions and alpha particle generation.