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Nuclear Science and Engineering Volume 193, 2019 - Issue 8
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Technical Papers

A New Approach to Monte Carlo in High Temperature Reactors

Indrajeet SinghBhabha Atomic Research Centre, Reactor Physics Design Division, Mumbai-400085, India;Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, IndiaCorrespondence[email protected]
ORCID Iconhttp://orcid.org/0000-0001-7410-6551
ORCID Icon,
S. B. DegwekerBhabha Atomic Research Centre, Mathematical Physics & Reactor Theory Section, Mumbai-400085, India
,
Amod Kishore MallickBhabha Atomic Research Centre, Reactor Physics Design Division, Mumbai-400085, India;Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, India
&
Anurag GuptaBhabha Atomic Research Centre, Reactor Physics Design Division, Mumbai-400085, India;Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, India
Pages 868-883 | Received 31 Oct 2018, Accepted 25 Jan 2019, Published online: 09 Mar 2019

References

  • “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).
  • P. K. ROMANO et al., “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,” Ann. Nucl. Energy, 82, 90 (2015); https://doi.org/10.1016/j.anucene.2014.07.048.
  • 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).
  • 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).
  • 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).
  • F. B. BROWN and W. R. MARTIN, “Stochastic Geometry Capability in MCNP5 for the Analysis of Particle Fuel,” Ann. Nucl. Energy, 31, 2039 (2004); https://doi.org/10.1016/j.anucene.2004.08.006.
  • H. Q. HO et al., “Numerical Investigation of the Random Arrangement Effect of Coated Fuel Particles on the Criticality of HTTR Fuel Compact Using MCNP6,” Ann. Nucl. Energy, 103, 114 (2017); https://doi.org/10.1016/j.anucene.2017.01.026.
  • F. REITSMA and W. KIM, “The Contribution of Cross-Section Uncertainties to Pebble Bed Reactor Eigenvalues Results: IAEA Cooperative Research Project Phase I Standalone Neutronics,” Proc. PHYSOR, Sun Valley, Idaho, May 1–5, 2016, American Nuclear Society (2016).
  • W. A. COLEMAN, “Mathematical Verification of a Certain Monte Carlo Sampling Technique and Applications of the Technique to Radiation Transport Problems,” Nucl. Sci. Eng., 31, 76 (1968); https://doi.org/10.13182/NSE68-1.
  • E. R. WOODCOCK et al., “Techniques Used in the GEM Code for Monte Carlo Neutronics Calculations in Reactors and Other Systems of Complex Geometry,” ANL-7050, Argonne National Laboratory (1965).
  • I. SINGH, S. B. DEGWEKER, and A. GUPTA, “A New Collision Probability Approach for Solution of the Transport Equation in the Random Medium of High-Plutonium-Content HTR Lattice Cells,” Nucl. Sci. Eng., 189, 2, 101 (2018); https://doi.org/10.1080/00295639.2017.1388092.
  • S. B. DEGWEKER, “BOXER3: A Three Dimensional Integral Transport Code for PHWR Supercell,” BARC-1295, Bhabha Atomic Research Centre (1985).
  • S. RAY et al., “A Collision Probability and MOC Based Lattice and Burnup Code for Analysis of LWR Fuel Assemblies,” Nucl. Sci. Eng., 184, 473 (2016); https://doi.org/10.13182/NSE15-127.
  • A. TRKOV, “WIMS-D Library Update, Final Report of a Co-Ordinated Research Project,” F. LESZCZYNSKI and D. LOPEZ ALDAMA, Eds., International Atomic Energy Agency (2006).
  • Y. LI and W. JI, “A Collective Dynamics-Based Method for Initial Pebble Packing in Pebble Flow Simulations,” Nucl. Eng. Des., 250, 229 (2012); https://doi.org/10.1016/j.nucengdes.2012.05.020.
  • G. J. AUWERDA et al., “Macroscopic and Microscopic Packing Properties of Experimental and Computational Pebble Beds,” Nucl. Technol., 183, 3, 272 (2013); https://doi.org/10.13182/NT13-A19417.
  • I. SINGH, S. B. DEGWEKER, and A. GUPTA, “Treatment of Double Heterogeneity in the Resonance and Thermal Energy Regions in High-Temperature Reactors,” Nucl. Sci. Eng., 189, 3, 243 (2018); https://doi.org/10.1080/00295639.2017.1402568.
  • G. HOSKING and T. D. NEWTON, “Physics of Plutonium Cycle Volume III, Results of a Benchmark Considering a High Temperature Reactor (HTR) Fuelled with Reactor-Grade Plutonium,” NEA No. 6200, Organisation for Economic Co-operation and Development Nuclear Energy Agency (2007).

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