Modelling of HTRs: From a homogenous to an exact heterogeneous core with Monte Carlo

Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

Volumn , Issue , 2002, Pages

  Ridikas, Danas ^a   Plukiene, Rita ^a  

^a CEA SACLAY   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COMBUSTION; EIGENVALUES AND EIGENFUNCTIONS; FUELS; GAS TURBINES; HIGH TEMPERATURE REACTORS;

COATED PARTICLE FUEL; DIFFERENT GEOMETRY; FUEL COMPOSITIONS; HELIUM-COOLED REACTORS; HETEROGENEOUS CORES; INDUSTRIAL FABRICATION; MONTE CARLO APPROACH; MONTEBURNS CODE;

MONTE CARLO METHODS;

EID: 26544458126     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (11)

1. “Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report”, No. 910720, Revision 1, General Atomics, GA Project No.7658, July 1996, San Diego, USA.
2. C. Rodriguez et al, “The Once-through Helium Cycle for Economical Transmutation in Secure, Clean and Safe Manner”, paper 72 in the Proceedings of the 6th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Madrid, Spain, 11-13 December 2000.
3. H. R. Trellue and D.I. Poston, “Users' Manual, Version 2.0 for Monteburns, Version 5B”, LANL preprint LA-UR-99-4999 (1999);
4. H.R. Trellue, private communication, April 2000.
5. J.F. Briesmeister, “MCNP - A General Monte Carlo N-Particle Code”, Technical Report LA-12625-M, LANL (1997).
6. RSIC Computer Code Collection, “ORIGEN 2.1 - Isotope Generation and Depletion Code Matrix Exponential Method”, RSIC report CCC-371 (1991).
7. D. Ridikas et al., “On the Fuel Cycle and Neutron Fluxes of the High Flux Reactor at ILL Grenoble”, Proceedings of the 5th Int pecialists Meeting SATIF-5, OECD/NEA, Paris, France, 17-21 July 2000.
8. F. Damian, “Capacity Analysis of HTRs in terms of utilisation of fissile materials”, CEA Saclay, report CEA-R-5981 (PhD thesis in French) 2001.
9. D. Ridikas et al., “Critical and Sub-Critical GR-MHRs for Waste Disposal and Proliferation-Resistant Plutonium Fuel Cycles”, paper 71 in the Proceedings of the 6t OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Madrid, Spain, 11-13 December 2000.
10. D. Ridikas et al., “Comparative Analysis of ENDF, JEF and JENDL Data Libraries by Modelling High Temperature Reactors and Plutonium Based Fuel Cycles: Military Pu case”, Proceedings of the Int. Conference on Nuclear Dat for Science and Technology (N2001), Tsukuba, Japan, 7-12 October 2001.
11. D. Ridikas et al., “Comparative Analysis of Different Data Libraries for the Performance of High Temperature Reactors (GT-MHR): Civil Pu case”, Proceedings of the Int. Conference on Accelerator Applications/Accelerator Driven Transmutation Technology and Applications (AccApp/ADTTA'01), 12-15 November 2001, Reno, Nevada, USA.