Fission Matrix Capability for MCNP Monte Carlo

Event Date: January 22, 2014
Speaker: Forrest Brown
Speaker Affiliation: Senior Research Scientist with the Monte Carlo Codes group in the X Computational Physics Division at LANL
Type: Seminar cancelled

 

This talk describes the initial experience and results from implementing a fission matrix capability into the MCNP Monte Carlo code. The fission matrix is obtained at essentially no cost during the normal simulation for criticality calculations. It can be used to provide estimates of the fundamental mode fission distribution, the dominance ratio, the eigenvalue spectrum, and higher mode spatial eigenfunctions. It can also be used to accelerate the convergence of the power method iterations and to provide basis functions for higher-order perturbation theory.  The new fission matrix capabilities  provide a significant advance in the state-of-the-art for Monte Carlo criticality calculations.

 

 

Dr. Forrest Brown is a Senior Research Scientist with the Monte Carlo Codes group in the X Computational Physics Division at LANL. He has extensive experience and expertise in reactor physics, criticality safety, radiation transport, and high-performance computing. He has been the lead developer for the MCNP, RACER, and VIM Monte Carlo codes at LANL, KAPL, and ANL. Dr. Brown is a Fellow of the American Nuclear Society with over 350 technical publications.  He is a Research Professor at the University of New Mexico, and an Adjunct Professor at the University of Michigan and RPI. Honors awarded to Dr. Brown include: ANS Gerald C. Pomraning Award, ANS Distinguished Service award, Los Alamos Achievement awards, Defense Programs of Excellence award, GE Outstanding Technical Achievement Award, and others.