This report presents the results of an assessment of advanced reactor technology options and is intended to provide a sound comparative technical context for future decisions concerning these technologies. A wide variety of important missions and advanced reactor technology needs were identified based on recent Department of Energy and international studies. Strategic objectives were established that span the range of key nuclear energy missions and needs. A broad team of stakeholders from industry, academia and government was assembled as part of the study. The team developed a comprehensive set of goals, criteria and metrics to evaluate advanced test and demonstration reactor concepts. Point designs of a select number of concepts were commissioned to provide a deeper technical basis for evaluation. The technology options were compared on the bases of technical maturity and the ability to meet the different strategic objectives. Pathways to deployment for concepts of varying technical maturity were estimated for the different demonstration systems with regard to cost, schedule and possible licensing approaches. This study also presents the tradeoffs that exist among the different irradiation test reactor options in terms of the ability to conduct irradiations in support of advanced reactor R&D and to serve potential secondary missions. viii EXECUTIVE SUMMARYGlobal efforts to address climate change will require large-scale decarbonization of energy production in the United States and elsewhere. Nuclear power already provides 20% of electricity production in the United States (U.S.) and is increasing in countries undergoing rapid growth around the world. Because reliable, grid-stabilizing, low-emission electricity generation, energy security, and energy resource diversity will be increasingly valued, nuclear power's share of electricity production has a potential to grow. In addition, there are non-electricity applications (e.g., process heat, desalination, hydrogen production) that could be better served by advanced nuclear systems. Thus, the timely development, demonstration, and commercialization of advanced nuclear reactors could diversify the nuclear through a combination of both new and existing facilities. From a long-term perspective, many advanced concepts will benefit from an irradiation test reactor that can support fuel and material testing and qualification. Design and construction of an irradiation test reactor are estimated to take about 10 to 13 years. Cost estimates for these irradiation test reactors are both around $3 billion and are highly uncertain at this early stage in the design process.xii Licensing OptionsThe licensing options also vary by concept maturity. For the mature concepts (HTGR and SFR), both reactor vendors providing demonstration reactor point designs have reported they would pursue a commercial power reactor Class 103 Nuclear Regulatory Commission (NRC) license. Considerable data exist from past demonstration projects and R&D activities conducted over the past 50 years to supp...
h i g h l i g h t s• Comparison of intermediate and fast spectrum thorium-fueled reactors.• Variety of reactor technology options enables self-sustaining thorium fuel cycles. • Fuel cycle analyses indicate similar performance for fast and intermediate systems.• Reproduction factor plays a significant role in breeding and burn-up performance. a b s t r a c t This paper presents analyses of possible reactor representations of a nuclear fuel cycle with continuous recycling of thorium and produced uranium (mostly U-233) with thorium-only feed. The analysis was performed in the context of a U.S. Department of Energy effort to develop a compendium of informative nuclear fuel cycle performance data. The objective of this paper is to determine whether intermediate spectrum systems, having a majority of fission events occurring with incident neutron energies between 1 eV and 10 5 eV, perform as well as fast spectrum systems in this fuel cycle. The intermediate spectrum options analyzed include tight lattice heavy or light water-cooled reactors, continuously refueled molten salt reactors, and a sodium-cooled reactor with hydride fuel. All options were modeled in reactor physics codes to calculate their lattice physics, spectrum characteristics, and fuel compositions over time. Based on these results, detailed metrics were calculated to compare the fuel cycle performance. These metrics include waste management and resource utilization, and are binned to accommodate uncertainties. The performance of the intermediate systems for this self-sustaining thorium fuel cycle was similar to a representative fast spectrum system. However, the number of fission neutrons emitted per neutron absorbed limits performance in intermediate spectrum systems.
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