Analysis of Stabilization Techniques for CMFD Acceleration of Neutron Transport Problems

Author:

Jarrett M.1,Kochunas B.1,Zhu A.1,Downar T.1

Affiliation:

1. CEA, DEN, SPRC, CEA-Cadarache, 13108 Saint Paul lez Durance, France

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference6 articles.

1. J. WILLERT, “Hybrid Deterministic/Monte Carlo Methods for Solving the Neutron Transport Equation and k-Eigenvalue Problem,” PhD Thesis, North Carolina State University (2013).

2. “Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation: A 2-D/3-D MOX Fuel Assembly Benchmark,” Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2003).

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