Investigation of the GFR2400 Reactivity Control System
The presented paper is related to the design methods and neutronic characterization of the reactivity control system in the large power unit of Generation IV Gas cooled Fast Reactor – GFR2400. The reactor core is based on carbide pin fuel type with the application of refractory metallic liners used to enhance the fission product retention of the SiCcladding. The heterogeneous design optimization of control rod is presented and the results of rods worth and their interferences in a core are evaluated. In addition, the idea of reflector removal as an additive reactivity management option is investigated and briefly described.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1096015Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1451
 Forum, U.S. DOE Nuclear Energy Research Advisory Committee and the Generatio IV International, "A Technology Roadmap for Generation IV Energy Systems," 2002.
 P. Anzieu, R. Stainsby and K. Mikityuk, "Gas-cooled Fast Reactor (GFR): Overview anPerspektives," in GiF Symposium, Paris, 2009.
 Z. Perko, S. Pelloni, K. Mikityuk, J. Kreppel, M. Sziebert, G. Geatan, B. Vrban, J. Luley, Š. Čerba, M. Halasz, S. Feher, T. Reiss, J. L. Kloosterman, R. Stainsby and C. Poette, "Core Neutronic Characterization of the GFR2400 Gas Cooled Fast Reactor," Progress in Nuclear Energy, submitted for publication.
 GoFastR, "GFR 2400 MWth pin core at start of GOFASTR". Internal document
 B. Vrban, Š. Čerba, J. Lüley, J. Haščík, V. Nečas and S. Pelloni, "Investigation of the Coupled Reactivity Effects of the Movable Reflector and Safety Control Rods in the GFR," in Proceedings of International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, Paris, 2013.
 M. Zabiego, C. Sauder, P. David, G. C., L. Briottet, J. J. Ingremeau, A. Ravenet, C. Lorrette, L. Chaffron, P. Guédeney, M. Le Flem and J. Séran, "Overview of CEA's R&D on GFR fuel element design: from challenges to solutions," Progress in Nuclear Energy, 2014, submitted for publication.
 W. van Rooijen and J. Kloosterman, "Closed Fuel Cycle and Minor Actinide Multirecycling," Science and Technology of Nuclear Installations, 2009.
 ORNL, "SCALE: A Comperhensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design," 2011.
 LANL, "MCNP X-5 MONTE CARLO TEAM: MCNP - A General N - Particle Transport Code," 2003.
 G. Girardin, G. Rimpault, F. Morin, J. C. Bosq, P. Coddington, K. Mikityuk and R. Chawla, "Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor," Annals of Nuclear Energy, no. 35, pp. 2206-2218, 2008.
 R. MacFarlane and D. W. Muir, "The NJOY Nuclear Data Processing System," 1994.
 Y. Katoh, D. F. Wilosn and C. W. Forsberg, "Assesment of Silicon Carbide Composites for Advanced Salt-Cooled Reactors," 2007.
 B. C. Kiedrowski, F. B. Brown and P. P. H. Wilson, "Calculating Kinetics Parameters and Reactivity Changes WithContinous-Energy Monte Carlo".