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An Exact MCNP Modeling of Pebble Bed Reactors

Authors: Amin Abedi, Naser Vosoughi, Mohammad Bagher Ghofrani


Double heterogeneity of randomly located pebbles in the core and Coated Fuel Particles (CFPs) in the pebbles are specific features in pebble bed reactors and usually, because of difficulty to model with MCNP code capabilities, are neglected. In this study, characteristics of HTR-10, Tsinghua University research reactor, are used and not only double heterogeneous but also truncated CFPs and Pebbles are considered.Firstly, 8335 CFPs are distributed randomly in a pebble and then the core of reactor is filled with those pebbles and graphite pebbles as moderator such that 57:43 ratio of fuel and moderator pebbles is established.Finally, four different core configurations are modeled. They are Simple Cubic (SC) structure with truncated pebbles,SC structure without truncated pebble, and Simple Hexagonal(SH) structure without truncated pebbles and SH structure with truncated pebbles. Results like effective multiplication factor (Keff), critical height,etc. are compared with available data.

Keywords: Double Heterogeneity, HTR-10, MCNP, Pebble Bed Reactor, Stochastic Geometry.

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[1] E. Webbe, "Simulation of A Randomly Packed Pebble Bed Using The Discrete Element Method", Physics Of Nuclear Reactors, Delft University Of Technology, June 23, 2009.
[2] S. Hu, X. Liang, L. Wei, "Commissioning And Operation Experience and Safety Experiments On HTR-10", 3rd International Topical Meeting on High Temperature Reactor Technology, P.1-16, October 1-4, 2006.
[3] S. Hu, R.Wang, Z. Gao, "Safety Demonstration Tests On HTR-10",2nd International Topical Meeting On High Temperature Reactor Technology , Beijing, China,, P.1-16, September 22-24, 2004.
[4] V.Seker, Ü. Çolak, "HTR-10 Full Core First Criticality Analysis withMCNP", Nuclear Engineering andDesign, P.263-270, 2003.
[5] J.Lebenhaft, "Mcnp4b Modeling of Pebble Bed Reactors", MIT Thesis, October 2001.
[6] K. M. Bakhshayesh and N. Vosoughi, "A Simulation of A Pebble Bed Reactor Core by the MCNP-4C Computer Code", Nuclear Technology & Radiation Protection, P.177-182, October 16, 2009.
[7] H.C.Kim, S. H. Kim, J. K. Kim, " A New Strategy To Simulate A Random Geometry In A Pebble-Bed Core With The Monte Carlo Code MCNP" , Annals Of Nuclear Energy,P1-7, Accepted 18 May 2011.
[8] Ü. Çolak, V.Seker, "Monte Carlo Criticality Calculations for A Pebble Bed Reactor with MCNP", Nuclear Science and Engineering, P.131- 137, 2005.
[9] MCNPTMÔÇöAGeneralMonteCarlo NParticleTransportCode. LosAlamosNationalLaboratory, Version5- 1.51,LA-12625.
[10] H. Chang , X. Raepsaet, F. Damian , Y.K. Lee ,O. Koberl, X. Jing , Y. Yang, " Analysis of HTR-10 First Criticality with Monte Carlo Code Tripoli-4.3" 2nd International Topical Meeting On High Temperature Reactor Technology, Beijing, CHINA, September 22-24, 2004.
[11] Y. Yang ,Z. Luo,X. Jing,Z. Wu, "FuelManagementOfTheHTR10IncludingTheEquilibriumStateAndTheR unning-InPhase", NuclearEngineeringandDesign, P33-41, 2002.
[12] Evaluation of high temperature gas cooled reactor performance: Benchmark analysis related to initial testing of the HTTR and HTR- 10,IAEA-TECDOC-1382.
[13] B.B. Forrest,R.M.William, "Stochastic geometry capability in MCNP5 for theanalysisofparticlefuel",AnnalsofNuclear Energy, P2039-2047, 2004.
[14] H.J. Rtitten, K.A. Haas, H. Brockmann, W. Scherer "V. S. O. P. (99/05),Computer Code System for Reactor Physicsand Fuel Cycle Simulation",October 2005.