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[en] The Interface Meeting will discuss the increased role of evolutionary nuclear systems,,, including small modular reactors, nuclear cogeneration, next generation reactors and advanced fuel cycles. This meeting can also help identify the demands for the GIF and IAEA's cooperation areas and assist us in developing proper programmes to cope with the challenges of developing evolutionary nuclear systems.
[en] The reprocessing of spent fuels is a very complex process that has allowed France to close its fuel cycle. More than 34000 tons of spent fuels have been processed in the La Hague and MELOX plants, operated by NEW AREVA, and the recovered plutonium has been used to fabricate the MOX fuel that is fed into 22 PWR reactors. This strategy is pertinent to reduce waste and spare uranium and is very useful regarding 4. generation reactors that will allow the multi-recycling of nuclear fuels. The main research topics are a simplification of industrial processes like Purex and a reprocessing and recycling that goes beyond the mere actinides. It appears that the most interesting fission products that may have a future in the industry are ruthenium, rhodium and palladium. (A.C.)
[en] EMWG - Plans for the future: - Continue improvements to G4ECONS v3.0; - Seek feedback from SSCs using survey questionnaire; - Discuss and agree on further collaboration with IAEA; - Publication of work on benchmarking; - Monitor use of the methodology and seek feedback; - Maintain watch on international activities on nuclear economics.
[en] Summary: • Development of the next version of G4ECONS is progressing well; • Comparable results obtained from the benchmarking of G4ECONS, HEEP and H2A for hydrogen production; • Completed benchmarking G4ECONS with NEST in collaboration with IAEA: –Once-through SCWR; – Two fast reactors with closed fuel cycle.
[en] Plutonium recycling as currently implemented in the French nuclear fuel cycle leads to the storage of irradiated MOX fuel assemblies. Deploying a limited number of fast reactors (SFR) by the end of the century may limit the growth of this stockpile. This study investigates the possibility of replacing the initial fast reactors by so-called CAPRA reactors, which have fast reactor cores designed to consume significantly more plutonium than breeder reactors. The results show that CAPRA cores can lead to a significant decrease in the stockpile of spent PWR MOX fuel assemblies. However, their performances during a transition towards a closed fuel cycle are comparable to that of standard fast reactors. Further detailed analysis is required to try to find the optimal solution (reprocessing capabilities, fluxes of waste, ect). This document is composed of an introduction and the slides of the presentation.
[en] There are different variants of organizing the closure of nuclear fuel cycle (CNFC) depending on fast reactor type, fuel types, station or centralized allocation of closed nuclear fuel cycle stages. Many processes and engineering solutions used for realization of chosen technologies for reprocessing spent fuel are little-studied. The mathematical modeling of radiochemical technology is used to verify and estimate engineering solutions. It will allow to optimize complex process technology in order to increase effectiveness and reduce cost. To achieve this goal within Project Proryv the mathematical models of key technologies for reprocessing spent fuel, fuel refabrication and handling radioactive waste are being developed. The models are implemented to program complexes VIZART and COD TP. The main objective of this codes is to validate realizability and optimize parameters of processing lines of CNFC. The codes use integrated library of technology models and allow to calculate material balance, create sequence diagrams, determine the most loaded parts of processing lines, estimate accumulation of fissile materials in apparatuses and intermediate vessels, estimate the influence of control actions on technology process. (author)
[en] In this study the equilibrium closed fuel cycle was simulated for eight selected fast reactors and both U-Pu and Th-U fuel cycles. For simplicity, the fission products were neglected and the reactors were represented only by infinite lattices. It was found that the fuel composition in equilibrium cycle is stabilized and does not differ between two consecutive iso-breeding cycles. The equilibrium fuel composition also determines the excess reactivity. This reactivity should be high enough to accommodate the expected captures of fission products and the presumed neutron leakage. The remaining reactivity, if available, can be applied for additional breeding or burning of selected isotopes. The study provided insight for the differences between the eight fast reactors and also between the U-Pu and Th-U closed fuel cycles. (author)
[en] In this meeting we will continue the established tradition to inform each other about the most important achievements of both projects and results of activities identified on last meeting which include areas of Proliferation Resistance, Economics, Safety, and Non-electric applications. We are also expecting discussion of new areas of potential cooperation such as Modelling and Simulation, SMRs, Institutional innovations, Advanced fuel cycles including Thorium, advanced materials, and Education and Training.
[en] China NPPs Development Plan: Improving the utilization rate of uranium resources and disposing of spent fuel are two major problems in the development of nuclear energy. Developing fast reactors and their closed fuel cycles are important options for the sustainable development of nuclear energy in China.