Analysis of Population Control Techniques for Time-Dependent and Eigenvalue Monte Carlo Neutron Transport Calculations
Author:
Affiliation:
1. University of Notre Dame, Department of Aerospace and Mechanical Engineering, Notre Dame, Indiana 46556
Funder
Department of Energy
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2091906
Reference32 articles.
1. D. E. CULLEN, “An Overview of a Coupled Neutron Photon 3-D, Combinatorial Geometry Time Dependent Monte Carlo Transport Code,” Technical Report LLNL-SM-704560, Lawrence Livermore National Laboratory (2016).
2. Dynamic Monte Carlo Method for Nuclear Reactor Kinetics Calculations
3. A Particle Population Control Method for Dynamic Monte Carlo
4. G4-STORK: A Monte Carlo Reactor Kinetics Simulation Code
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