Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations
Author:
Affiliation:
1. University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104
2. Naval Nuclear Laboratory, P.O. Box 79, West Mifflin, Pennsylvania 15122-007 9
Funder
U.S. Department of Energy
U.S. Nuclear Regulatory Commission
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2023.2270740
Reference43 articles.
1. H. G. JOO et al., “Methods and Performance of a Three-Dimensional Whole-Core Transport Code DeCART,” Proc. Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments (PHYSOR 2004), Chicago, Illinois, April 25–29, 2004, p. 21, American Nuclear Society (2004).
2. High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor
3. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
4. VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion
5. MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7
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