Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations
Author:
Affiliation:
1. Bhabha Atomic Research Centre, Reactor Physics Design Division, Mumbai- 400085, India
2. Bhabha Atomic Research Centre, Formerly Raja Ramanna Fellow of the DAE, Mumbai-400085, India
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2019.1645502
Reference30 articles.
1. “MCNP—A General Monte Carlo N-Particle Transport Code,” LA-CP-03-0284, Los Alamos National Laboratory (2003).
2. The Serpent Monte Carlo code: Status, development and applications in 2013
3. V. S. W. SHERRIFFS, “MONK A General Purpose Monte Carlo Neutronics Program,” Safety and Reliability Directorate Report SRD R 86, UKAEA (Jan. 1978).
4. High temperature reactors
5. Advanced Nuclear Reactor Systems – An Indian Perspective
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