Nuclear fuel recycling: National and regional options for the US nuclear energy system

2010 ◽  
Vol 3 (8) ◽  
pp. 996 ◽  
Author(s):  
R. Busquim e Silva ◽  
M. S. Kazimi ◽  
P. Hejzlar
2012 ◽  
Vol 4 (10) ◽  
pp. 2377-2398 ◽  
Author(s):  
Stefano Passerini ◽  
Mujid Kazimi

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.


2019 ◽  
Vol 5 (1) ◽  
pp. 39-45 ◽  
Author(s):  
Andrey A. Andrianov ◽  
Ilya S. Kuptsov ◽  
Tatyana A. Osipova ◽  
Olga N. Andrianova ◽  
Tatyana V. Utyanskaya

The article presents a description and some illustrative results of the application of two optimization models for a two-component nuclear energy system consisting of thermal and fast reactors in a closed nuclear fuel cycle. These models correspond to two possible options of developing Russian nuclear energy system, which are discussed in the expert community: (1) thermal and fast reactors utilizing uranium and mixed oxide fuel, (2) thermal reactors utilizing uranium oxide fuel and fast reactors utilizing mixed nitride uranium-plutonium fuel. The optimization models elaborated using the IAEA MESSAGE energy planning tool make it possible not only to optimize the nuclear energy system structure according to the economic criterion, taking into account resource and infrastructural constraints, but also to be used as a basis for developing multi-objective, stochastic and robust optimization models of a two-component nuclear energy system. These models were elaborated in full compliance with the recommendations of the IAEA’s PESS and INPRO sections, regarding the specification of nuclear energy systems in MESSAGE. The study is based on publications of experts from NRC “Kurchatov Institute”, JSC “SSC RF-IPPE”, ITCP “Proryv”, JSC “NIKIET”. The presented results demonstrate the characteristic structural features of a two-component nuclear energy system for conservative assumptions in order to illustrate the capabilities of the developed optimization models. Consideration is also given to the economic feasibility of a technologically diversified nuclear energy structure providing the possibility of forming on its base a robust system in the future. It has been demonstrated that given the current uncertainties in the costs of nuclear fuel cycle services and reactor technologies, it is impossible at the moment to make a reasonable conclusion regarding the greatest attractiveness of a particular option in terms of the economic performance.


2022 ◽  
Vol 8 ◽  
pp. 2
Author(s):  
Andrei A. Andrianov ◽  
Olga N. Andrianova ◽  
Ilya S. Kuptsov ◽  
Leonid I. Svetlichny ◽  
Tatyana V. Utianskaya

The paper presents the results of a case study on evaluating performance and sustainability metrics for Russian nuclear energy deployment scenarios with thermal and sodium-cooled fast reactors in a closed nuclear fuel cycle. Ten possible scenarios are considered which differ in the shares of thermal and sodium-cooled fast reactors, including options involving the use of mixed uranium-plutonium oxide fuel in thermal reactors. The evolution of the following performance and sustainability metrics is estimated for the period from 2020 to 2100 based on the considered assumptions: annual and cumulative uranium consumption, needs for uranium enrichment capacities, fuel fabrication and reprocessing capacities, spent fuel stocks, radioactive wastes, amounts of plutonium in the nuclear fuel cycle, amounts of accumulated depleted uranium, and the levelised electricity generation cost. The results show that the sustainability of the Russian nuclear energy system can be significantly enhanced through the intensive deployment of sodium-cooled fast reactors and the transition to a closed nuclear fuel cycle. The authors have highlighted some issues for further considerations, which will lead to more rigorous conclusions regarding the preferred options for the development of the national nuclear energy system.


Author(s):  
Galina Fesenko ◽  
Vladimir Kuznetsov ◽  
Vladimir Usanov

The International Atomic Energy Agency’s (IAEA’s) International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 with the goal to ensure a sustainable nuclear energy supply to meet the global energy needs in the 21st century. The INPRO activities on global and regional nuclear energy scenarios provide newcomers and mature nuclear countries alike with better understanding of options for making a collaborative transition to future sustainable nuclear energy systems. Collaborative project GAINS (Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle) developed an internationally verified analytical framework for assessing such transition scenarios. The framework (hereafter, GAINS framework) is a part of the integrated services provided by IAEA to Member States considering initial development or expansion of their nuclear energy programmes. The paper presents major elements of the analytical framework and selected results of its application, including: • Long-term nuclear energy demand scenarios based on the IAEA Member States’ high and low estimations of nuclear power deployment until 2030 and expected trends until 2050 and on forecasts of competent international energy organizations; • Heterogeneous world model comprised of groups of non-personified non-geographical countries (NGs) with different policy regarding nuclear fuel cycle back end; • Architectures of nuclear energy systems; • Metrics and tools for the assessment of dynamic nuclear energy system evolution scenarios regarding sustainability, including a set of key indicators and evaluation parameters; • An internationally verified database with best estimate material flow and economic characteristics of existing and advanced nuclear reactors and associated nuclear fuel cycles needed for material flow analysis and comparative economic analysis, extending the previously developed IAEA databases and taking into account preferences of different countries; • Selected results of sample analysis for scenarios involving transition from the present fleets of nuclear reactors and fuel cycles to future sustainable nuclear energy system architectures involving innovative technological solutions.


2018 ◽  
Vol 2018 (3) ◽  
pp. 100-112 ◽  
Author(s):  
Andrey Alekseevich Andrianov ◽  
Ilya Sergeevich Kuptsov ◽  
Tatiana Andreevna Osipova ◽  
Olga Nikolaevna Andrianova ◽  
Tatyana Vladimirovna Utyanskaya

MRS Advances ◽  
2018 ◽  
Vol 3 (19) ◽  
pp. 991-1003 ◽  
Author(s):  
Evaristo J. Bonano ◽  
Elena A. Kalinina ◽  
Peter N. Swift

ABSTRACTCurrent practice for commercial spent nuclear fuel management in the United States of America (US) includes storage of spent fuel in both pools and dry storage cask systems at nuclear power plants. Most storage pools are filled to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler fuel from pools into dry storage. In the absence of a repository that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 134,000 metric tons of spent fuel in dry storage by mid-century when the last plants in the current reactor fleet are decommissioned. Current designs for storage systems rely on large dual-purpose (storage and transportation) canisters that are not optimized for disposal. Various options exist in the US for improving integration of management practices across the entire back end of the nuclear fuel cycle.


2017 ◽  
Vol 46 (45) ◽  
pp. 15746-15756 ◽  
Author(s):  
Xintao Wei ◽  
Qi Liu ◽  
Hongsen Zhang ◽  
Zetong Lu ◽  
Jingyuan Liu ◽  
...  

The ability to recover uranium, an important nuclear fuel, from seawater provides the potential for long-term sustainable fuel supply for nuclear energy.


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