Multigroup Constant Calculation with Static α-Eigenvalue Monte Carlo for Time-Dependent Neutron Transport Simulations
Author:
Affiliation:
1. University of Michigan, Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan
2. Oak Ridge National Laboratory, Oak Ridge, Tennessee
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2020.1743578
Reference27 articles.
1. D. E. CULLEN, “TART 2016: An Overview of a Coupled Neutron Photon 3 D, Combinatorial Geometry Time Dependent Monte Carlo Transport Code,” LLNL-SM-704560, Lawrence Livermore National Laboratory (2016).
2. An Overview of the Monte Carlo Application ToolKit (MCATK)
3. New kinetic simulation capabilities for Tripoli-4®: Methods and applications
4. Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark
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