Browse > Article
http://dx.doi.org/10.1016/j.net.2017.08.014

APOLLO3 homogenization techniques for transport core calculations-application to the ASTRID CFV core  

Vidal, Jean-Francois (CEA, DEN, DER/SPRC/LEPh)
Archier, Pascal (CEA, DEN, DER/SPRC/LEPh)
Faure, Bastien (CEA, DEN, DER/SPRC/LEPh)
Jouault, Valentin (CEA, DEN, DER/SPRC/LEPh)
Palau, Jean-Marc (CEA, DEN, DER/SPRC/LEPh)
Pascal, Vincent (CEA, DEN, DER/SPRC/LEPh)
Rimpault, Gerald (CEA, DEN, DER/SPRC/LEPh)
Auffret, Fabien (CEA, DEN, DANS/DM2S/SERMA/LTSD)
Graziano, Laurent (CEA, DEN, DANS/DM2S/SERMA/LTSD)
Masiello, Emiliano (CEA, DEN, DANS/DM2S/SERMA/LTSD)
Santandrea, Simone (CEA, DEN, DANS/DM2S/SERMA/LTSD)
Publication Information
Nuclear Engineering and Technology / v.49, no.7, 2017 , pp. 1379-1387 More about this Journal
Abstract
This paper presents a comparison of homogenization techniques implemented in the APOLLO3 platform for transport core calculations: standard scalar flux weighting and new flux-moment homogenization, in different combinations with (or without) leakage models. Besides the historical B1-homogeneous model, a new B-heterogeneous one has indeed been implemented recently in the two/three-dimensional-transport solver using the method of characteristics. First analyses have been performed on a very simple Sodium Fast Reactor core with a regular hexagonal lattice. They show that using the heterogeneous leakage model in association with flux-moment homogenization strongly improves the prediction of $k_{eff}$ and void reactivity effects. These good results are confirmed when the application is done to the fissile assemblies of the more complex CFV (Low Void Effect) core of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project of sodium-cooled fast breeder reactor (Generation IV).
Keywords
Homogenization; Flux moments weighting; Heterogeneous leakage; APOLLO3;
Citations & Related Records
연도 인용수 순위
  • Reference
1 R. Sanchez, Assembly homogenization techniques for core calculations, Prog. Nucl. Energy 51 (2009) 14-31.   DOI
2 J.-F. Vidal, O. Litaize, D. Bernard, A. Santamarina, C. Vaglio-Gaudard, R. Tran, New modelling of LWR assemblies using the APOLLO2 code package, in: Proceedings of M&C+SNA 2007, American Nuclear Society, Monterey, CA, USA, April 15-19, 2007.
3 A. Hebert, A reformulation of the transport-transport SPH equivalence technique, in: 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering, Canadian Nuclear Society, Ottawa, Ontario, Canada, October 18-21, 2015.
4 F. Varaine, P. Marsault, M.-S. Chenaud, B. Bernardin, A. Conti, P. Sciora, C. Venard, B. Fontaine, L. Martin, G. Mignot, Pre-conceptual design study of ASTRID core, in: Proceedings of ICAPP 2012, Chicago, IL, USA, June 24-28, 2012.
5 P. Archier, J.-M. Palau, J.-F. Vidal, V. Pascal, G. Rimpault, B. Roque, S. Santandrea, New reference $APOLLO3^{(R)}$ calculation scheme for sodium fast reactors: from sub-assembly to full core calculations, in: Proceedings of PHYSOR 2016, American Nuclear Society, Sun Valley, ID, USA, May 1-5, 2016.
6 G.I. Bell, S. Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold Company, New York, USA, 1970.
7 J. Tommasi, Heterogeneous BN equations and symmetries, Ann. Nucl. Energy 85 (2015) 145-158.   DOI
8 E. Brun, E. Dumonteil, F.X. Hugot, N. Huot, C. Jouanne, Y.K. Lee, F. Malgavi, A. Mazzolo, O. Petit, J.C. Trama, A. Zoia, Overview of TRIPOLI-4 version 7 continuous energy Monte Carlo transport code, in: Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011.
9 G. Rimpault, Algorithmic features of the ECCO cell code for treating heterogeneous fast reactor subassemblies, in: International Topical Meeting on Reactor Physics and Computations, Portland, OR, May 1-5, 1995.
10 J.-Y. Moller, J.-J. Lautard, MINARET, a deterministic neutron transport solver for nuclear core calculations, in: Proceedings of M&C 2011, American Nuclear Society, Rio de Janeiro, Brazil, May 8-12, 2011.
11 D. Sciannandrone, S. Santandrea, R. Sanchez, Optimized tracking strategies for step MOC calculations in extruded 3D axial geometries, Ann. Nucl. Energy 87 (2016) 49-60.   DOI
12 V.C. Deniz, The Theory of Neutron Leakage in Reactor Lattices, CRC Handbook of Nuclear Reactor Calculations, vol. 2, CRC Press, Boca Raton, FL, 1986, pp. 409-508.
13 J.-F. Vidal, P. Archier, A. Calloo, Ph. Jacquet, J. Tommasi, R. Le Tellier, An improved energy-collapsing method for core-reflector modelization in RNR core calculations using the PARIS platform, in: Proceedings of PHYSOR 2012, American Nuclear Society, Knoxville, TN, USA, April 15-20, 2012.
14 G. Rimpault, J.M. Rieunier, D. Verrier, D. Biron, The ERANOS code and data system for fast reactor neutronic analyses, in: Proceedings of PHYSOR 2002, American Nuclear Society, Seoul, Korea, October 7-10, 2002.
15 D. Schneider, F. Dolci, F. Gabriel, J.-M. Palau, M. Guillo, B. Pothet, P. Archier, K. Ammar, F. Auffret, R. Baron, A.-M. Baudron, P. Bellier, L. Bourhrara, L. Buiron, M. Coste-Delclaux, C. De Saint Jean, J.-M. Do, B. Espinosa, E. Jamelot, V. Jouault, J.-J. Lautard, R. Lenain, J.-C. Le Pallec, L. Lei Mao, E. Masiello, S. Mengelle, F. Moreau, P. Mosca, M. Muniglia, N. Odry, V. Pascal, S. Pastoris, B. Roque, A. Targa, C. Patricot, S. Santandrea, D. Sciannandrone, A. Tsilanizara, J.-F. Vidal, I. Zmijarevic, $APOLLO3^{(R)}$: CEA/DEN deterministic multi-purpose code for reactor physics analysis, in: Proceedings of PHYSOR 2016, American Nuclear Society, Sun Valley, ID, USA, May 1-5, 2016.
16 G. Rimpault, J.-F. Vidal, W.F.G. Van Rooijen, Neutron leakage treatment in reactor physics: consequences for predicting core characteristic, in: Proceedings of PHYSOR 2014, American Nuclear Society, Kyoto, Japan, September 28-October 3, 2014.
17 G. Chiba, W.F.G. Van Rooijen, Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods, Ann. Nucl. Energy 38 (2011) 133-144.   DOI