A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations

Author:

Chen Jiahao,Hou JasonORCID,Ivanov KostadinORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Iterative Acceleration Methods for Monte Carlo and Deterministic Criticality Calculations,” LA-13052-T;Urbatsch,1995

2. Fission Matrix Capability for MCNP, Part I-Theory,” M&C 2013 Conference;Brown,2013

3. Theory and applications of the fission matrix method for continuous-energy Monte Carlo;Carney;Annals of Nuclear Energy,2014

4. Automated variance reduction of Monte Carlo shielding calculations using the discrete ordinates adjoint function;Wagner;Nuclear Science and Engineering,1998

5. FW-CADIS method for global and regional variance reduction of Monte Carlo radiation transport calculations;Wagner;Nuclear Science and Engineering,2014

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