The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations
Author:
Affiliation:
1. The Pennsyslvania State University, Mechanical and Nuclear Engineering Department, University Park, Pennsylvania
2. Virginia Tech, Nuclear Engineering Program, Mechanical Engineering Department, Arlington, Virginia
Funder
U.S. Nuclear Regulatory Commission
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2018.1497395
Reference26 articles.
1. Fission Source Convergence of Monte Carlo Criticality Calculations in Weakly Coupled Fissile Arrays
2. Autocorrelation and Dominance Ratio in Monte Carlo Criticality Calculations
3. Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT
4. E. R. SHEMON, M. A. SMITH, and C. H. LEE, “Proteus-SN Methodology Manual,” ANL/NE-14/5, Argonne National Laboratory (2014).
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