A New Approach to Monte Carlo in High Temperature Reactors-Reference-Cited by-同舟云学术

A New Approach to Monte Carlo in High Temperature Reactors

Published:2019-03-09 Issue:8 Volume:193 Page:868-883
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Singh Indrajeet¹²^ORCID,Degweker S. B.³,Mallick Amod Kishore¹²,Gupta Anurag¹²

Affiliation:

1. Bhabha Atomic Research Centre, Reactor Physics Design Division, Mumbai-400085, India

2. Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, India

3. Bhabha Atomic Research Centre, Mathematical Physics & Reactor Theory Section, Mumbai-400085, India

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2019.1576453

Reference17 articles.

1. “MCNP—A General Monte Carlo N-Particle Transport Code Version 5 Volume I: Overview and Theory,” LA-UR-03-1987, Los Alamos National Laboratory (2008).

2. OpenMC: A state-of-the-art Monte Carlo code for research and development

3. S. A. DUPREE and S. K. FRALEY, A Monte Carlo Primer: A Practical Approach to Radiation Transport, ISBN 0-306-46748-8, p. 356, Kluwer Academic/Plenum Publishers Hardbound (Dec. 2002); https://doi.org/10.1044/1059-0889(2002/er01).

4. J. CETNAR, W. GUDOWSKI, and J. WALLENIUS, “MCB: A Continuous Energy Monte Carlo Burnup Simulation Code,” in “Actinide and Fission Product Partitioning and Transmutation,” EUR 18898 EN, p. 523, Organisation for Economic Co-operation and Development Nuclear Energy Agency (1999).

5. H. R. TRELLUE and D. I. POSTON, “User’s Manual, Version 2.0 for Monteburns, Version 1.0,” LA-UR-99-4999, Los Alamos National Laboratory (1999).

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Simulation of random medium of fuel pebble with liquid salt coolant using PebMC code;Physics Open;2023-12