Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core

Author:

Srivastava Argala,Mallick Amod Kishore,Singh K. P.,Kannan Umasankari

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference9 articles.

1. Brown FB (2006) On the use of Shannon entropy of the fission distribution for assessing convergence of Monte Carlo criticality calculations. LA-UR-06-3737

2. Judd RA, Rouben B (1981) Three dimensional kinetics benchmark problem in a heavy water reactor. AECL-7236

3. Mallick AK, Kannan U (2018) PATMOC: a multi-group Monte Carlo code for neutron transport simulation. RPDD/EP/164

4. Mallick AK, Degweker SB, Krishnani PD (2014) Fission matrix and acceleration fission source convergence in Monte Carlo neutron transport simulation. RPDD/EP/99

5. Rana YS, Arun S, Degweker SB (2013) Diffusion theory based analogue Monte Carlo for simulating noise experiments in sub-critical systems. Nuclear Sci Eng 174:245–263

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