scholarly journals Accelerator–Reactor Coupling for Energy Production in Advanced Nuclear Fuel Cycles

2015 ◽  
Vol 08 ◽  
pp. 99-114 ◽  
Author(s):  
Florent Heidet ◽  
Nicholas R. Brown ◽  
Malek Haj Tahar
Keyword(s):  
Nuclear Fuel ◽  
Energy Production ◽  
Fuel Cycle ◽  
Reactor Core ◽  
Nuclear Fuel Cycle ◽  
Driven Systems ◽  
Fuel Cycles ◽  
Accelerator Driven Systems ◽  
The Impact ◽  
Nuclear Fuel Cycles

This article is a review of several accelerator–reactor interface issues and nuclear fuel cycle applications of accelerator-driven subcritical systems. The systems considered here have the primary goal of energy production, but that goal is accomplished via a specific application in various proposed nuclear fuel cycles, such as breed-and-burn of fertile material or burning of transuranic material. Several basic principles are reviewed, starting from the proton beam window including the target, blanket, reactor core, and up to the fuel cycle. We focus on issues of interest, such as the impact of the energy required to run the accelerator and associated systems on the potential electricity delivered to the grid. Accelerator-driven systems feature many of the constraints and issues associated with critical reactors, with the added challenges of subcritical operation and coupling to an accelerator. Reliable accelerator operation and avoidance of beam trips are critically important. One interesting challenge is measurement of blanket subcriticality level during operation. We also review the potential benefits of accelerator-driven systems in various nuclear fuel cycle applications. Ultimately, accelerator-driven subcritical systems with the goal of transmutation of transuranic material have lower 100,000-year radioactivity than a critical fast reactor with recycling of uranium and plutonium.

scholarly journals The Accelerator Driven Systems, a 21st Century Option for Closing Nuclear Fuel Cycles and Transmuting Minor Actinides

2021 ◽  
Vol 13 (22) ◽  
pp. 12643
Author(s):  
Hamid Aït Abderrahim ◽  
Michel Giot
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Building Blocks ◽  
Minor Actinides ◽  
Physical Treatment ◽  
Driven Systems ◽  
Fuel Cycles ◽  
Fuel Fabrication ◽  
Global Vision ◽  
Accelerator Driven Systems

Closing the nuclear fuel cycle and transmuting Minor Actinides (M.As) can be considered as an application of the duty of care principlel principle which says that, “before the final disposal of any waste, any possible chemical and/or physical treatment has to be applied in order to reduce the waste’s toxicity, provided the treatment does not convey unacceptable risks or unacceptable costs”. Forty years of complex research and development has shown that Accelerator Driven Systems could provide a solution to the challenge posed by spent nuclear fuels, by enabling the ability to considerably decrease their radiotoxicity lifetime burden and volume. In particular, a multilateral strategy of treatment of the MAs could be a commendable solution for both the countries phasing out the exploitation of nuclear energy and for those pursuing and developing this exploitation. The pre-industrial assessment of the technical and financial feasibility for industrialization is the next step. This applies to the four R&D and Demonstration building blocks: advanced separation, MAs’ loaded fuel fabrication, dedicated transmuters demonstration (MYRRHA) and provision for MAs’ fuel loaded processing. A global vision of the process leading to a sustainable option is proposed.

Overview of the U.S. Department of Energy Advanced Waste Forms Development

2018 ◽  
Author(s):  
Kimberly Gray ◽  
John Vienna ◽  
Patricia Paviet
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Department Of Energy ◽  
High Level Waste ◽  
Fuel Cycles ◽  
Waste Forms ◽  
The U.S

In order to maintain the U.S. domestic nuclear capability, its scientific technical leadership, and to keep our options open for closing the nuclear fuel cycle, the Department of Energy, Office of Nuclear Energy (DOE-NE) invests in various R&D programs to identify and resolve technical challenges related to the sustainability of the nuclear fuel cycle. Sustainable fuel cycles are those that improve uranium resource utilization, maximize energy generation, minimize waste generation, improve safety and limit proliferation risk. DOE-NE chartered a Study on the evaluation and screening of nuclear fuel cycle options, to provide information about the potential benefits and challenges of nuclear fuel cycle options and to identify a relatively small number of promising fuel cycle options with the potential for achieving substantial improvements compared to the current nuclear fuel cycle in the United States. The identification of these promising fuel cycles helps in focusing and strengthening the U.S. R&D investment needed to support the set of promising fuel cycle system options and nuclear material management approaches. DOE-NE is developing and evaluating advanced technologies for the immobilization of waste issued from aqueous and electrochemical recycling activities including off-gas treatment and advanced fuel fabrication. The long-term scope of waste form development and performance activities includes not only the development, demonstration, and technical maturation of advanced waste management concepts but also the development and parameterization of defensible models to predict the long-term performance of waste forms in geologic disposal. Along with the finding of the Evaluation and Screening Study will be presented the major research efforts that are underway for the development and demonstration of waste forms and processes including glass ceramic for high-level waste raffinate, alloy waste forms and glass ceramics composites for HLW from the electrochemical processing of fast reactor fuels, and high durability waste forms for radioiodine.

scholarly journals Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without long-lived nuclear waste

Nukleonika ◽  
2015 ◽  
Vol 60 (3) ◽  
pp. 581-590 ◽  
Author(s):  
Przemysław Stanisz ◽  
Jerzy Cetnar ◽  
Grażyna Domańska
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Waste ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Core ◽  
Nuclear Fuel Cycle ◽  
Minor Actinide ◽  
Closed Nuclear Fuel Cycle ◽  
European Collaboration ◽  
Multiple Recycling

Abstract The concept of closed nuclear fuel cycle seems to be the most promising options for the efficient usage of the nuclear energy resources. However, it can be implemented only in fast breeder reactors of the IVth generation, which are characterized by the fast neutron spectrum. The lead-cooled fast reactor (LFR) was defined and studied on the level of technical design in order to demonstrate its performance and reliability within the European collaboration on ELSY (European Lead-cooled System) and LEADER (Lead-cooled European Advanced Demonstration Reactor) projects. It has been demonstrated that LFR meets the requirements of the closed nuclear fuel cycle, where plutonium and minor actinides (MA) are recycled for reuse, thereby producing no MA waste. In this study, the most promising option was realized when entire Pu + MA material is fully recycled to produce a new batch of fuel without partitioning. This is the concept of a fuel cycle which asymptotically tends to the adiabatic equilibrium, where the concentrations of plutonium and MA at the beginning of the cycle are restored in the subsequent cycle in the combined process of fuel transmutation and cooling, removal of fission products (FPs), and admixture of depleted uranium. In this way, generation of nuclear waste containing radioactive plutonium and MA can be eliminated. The paper shows methodology applied to the LFR equilibrium fuel cycle assessment, which was developed for the Monte Carlo continuous energy burnup (MCB) code, equipped with enhanced modules for material processing and fuel handling. The numerical analysis of the reactor core concerns multiple recycling and recovery of long-lived nuclides and their influence on safety parameters. The paper also presents a general concept of the novel IVth generation breeder reactor with equilibrium fuel and its future role in the management of MA.

scholarly journals Sustainability Features of Nuclear Fuel Cycle Options

2012 ◽  
Vol 4 (10) ◽  
pp. 2377-2398 ◽  
Author(s):  
Stefano Passerini ◽  
Mujid Kazimi
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy System ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Base Line ◽  
Energy Potential ◽  
Fuel Cycle Analysis ◽  
The Impact

The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for use as fuel. Thus, different types of fuel recycling technologies may be introduced in order to more fully utilize the energy potential of the fuel, or reduce the environmental impacts and proliferation concerns about the discarded fuel materials. Nuclear fuel cycle systems analysis is applied in this paper to attain a better understanding of the strengths and weaknesses of fuel cycle alternatives. Through the use of the nuclear fuel cycle analysis code CAFCA (Code for Advanced Fuel Cycle Analysis), the impact of a number of recycling technologies and the associated fuel cycle options is explored in the context of the U.S. energy scenario over 100 years. Particular focus is given to the quantification of Uranium utilization, the amount of Transuranic Material (TRU) generated and the economics of the different options compared to the base-line case, the OTC option. It is concluded that LWRs and the OTC are likely to dominate the nuclear energy supply system for the period considered due to limitations on availability of TRU to initiate recycling technologies. While the introduction of U-235 initiated fast reactors can accelerate their penetration of the nuclear energy system, their higher capital cost may lead to continued preference for the LWR-OTC cycle.

scholarly journals A METHOD FOR STUDY OF NUCLEAR FUEL CYCLE SCENARIOS WITH AN INTENSIVE ELECTRICITY PRODUCTION DECLINE IN A SHORT PERIOD

2021 ◽  
Vol 247 ◽  
pp. 13005
Author(s):  
Weifeng Zhou ◽  
Guillaume Krivtchik ◽  
Patrick Blaise
Keyword(s):  
Nuclear Fuel ◽  
Energy Production ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Nuclear Industry ◽  
Decision Makers ◽  
Electricity Production ◽  
Strong Impact ◽  
Short Period ◽  
Scenario Model

Nuclear fuel cycle scenario study can be of benefit for decision-making in nuclear industry development. However, due to the lack of knowledge about the future, many scenario studies are subject to uncertainties. As a result, some parameters may be disrupted. Energy production of an entire nuclear fleet of interest is such a parameter. Its disruptive decline has a strong impact on the results of scenario studies. Resilience study against disruption of decline in energy production is required to anticipate possible failures of scenario studies. In such a resilience study, a large number of scenario trajectory simulations with different modes of decline are expected. It is too difficult to set the values of all scenario parameters in each trajectory manually. As a solution, a method is proposed in this paper to reduce the number of input parameters. A set of rules has been implemented as an intermediate layer between the decision-makers and the scenario code to drive the evolution of a nuclear fleet. In this case, a trajectory can be fully characterized by a few parameters. This method has been applied to a simplified academic nuclear fleet with two different modes of decline in energy production. The simulation results showed that the developed method is feasible. One should note that the scenario model in this paper is only used for academic purposes and does not correspond to any industrial strategy or policy.

Analysis of Environmental Friendliness of Advanced Nuclear Fuel Cycle in Korea

2003 ◽  
Author(s):  
Yong Han Kim ◽  
Kun Jai Lee ◽  
Won Zin Oh
Keyword(s):  
Waste Management ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Clean Energy ◽  
Nuclear Fuel Cycle ◽  
Utilization Efficiency ◽  
High Level Waste ◽  
Environmental Friendliness ◽  
Fuel Cycles ◽  
Advanced Fuel

In order to show that the nuclear energy could be a clean energy, radioactive waste management, especially high level waste has to be successfully managed and also accepted by the public. As discussed, progressed and focused at GEN IV international project, reduction of long lived actinide source term and corresponding toxicity through transmutation process has been recognized as one possible solution to the problem and draw lots of attention these days and active R&D efforts are pursued and progressed worldwidely. Especially, much of interest has been initiated to the accelerator driven system (ADS) for the transmutation of the actinide as a subcritical reactors or combination to fast reactor (FR) to generate energy and transmute the HLW simultaneously in a cleaner and safer ways. This study compare and clarifies the roles and merits of the FR and ADS, which would be expected to be introduced into the future Korean nuclear fuel cycle partly, in view of environmental friendliness especially with the existing nuclear fuel cycle dominated by PWR in Korea. After selecting the most plausible and appropriate reactor strategy scenario, the mass flow balance of active radionuclides from ore to waste for several cases of advanced nuclear fuel cycle (where “advanced nuclear fuel cycle” means the nuclear fuel cycle with FR or ADS) is analyzed by computer code. Advanced nuclear fuel cycle with only FR or ADS, and with both FR and ADS were considered for this analysis. A spread sheet type of code, that compute material flow and some environmental friendliness indices chronologically, was developed and analyzed for the calculation. Some indices for the environmental friendliness (i.e. amount of actinide nuclides, radioactivity and radiotoxicity of them, and uranium resource requirement) for several types of advanced nuclear fuel cycles are analyzed comparing with those of once-through fuel cycle. According to the final results, it confirmed quantitatively that the advanced fuel cycle with FRs and ADSs would be one of the possible alternatives to relieve the burden of HLW waste management because those fuel cycle options might reduce the generation of the transuranic radionuclides by tens to hundreds times less compared to that of once-through fuel cycle. Especially advanced nuclear system combined with FR and ADS shows much better effects compared to not combined system. Resource utilization efficiency is also much upgraded high by the introduction of advanced fuel cycles with a significant high share of fast reactors (i.e. only a half amount of uranium can be consumed in case of introduction of breakeven type FR compared to once-through fuel cycle case.)

Sign in / Sign up

Export Citation Format

Share Document