The Advanced Fuel Cycle Facility (AFCF) Role in the Global Nuclear Energy Partnership

2008 ◽  
Author(s):  
Andrew Griffith ◽  
John Boger ◽  
Jeffrey Perry
Keyword(s):  
Nuclear Energy ◽  
Fuel Cycle ◽  
The United States ◽  
Treatment Center ◽  
Management Approach ◽  
Used Nuclear Fuel ◽  
Reactor Technology ◽  
Advanced Technologies ◽  
Fuel Fabrication ◽  
Advanced Fuel

The Global Nuclear Energy Partnership (GNEP), launched in February, 2006, proposes to introduce used nuclear fuel recycling in the United States (U.S.) with improved proliferation-resistance and a more effective waste management approach. This program is evaluating ways to close the fuel cycle in a manner that introduces the most advanced technologies of today and builds on recent breakthroughs in U.S. national laboratories while drawing on international and industry partnerships. Central to moving this advanced fuel recycling technology from the laboratory to commercial implementation is the development and siting of three proposed GNEP facilities: the Consolidated Fuel Treatment Center (CFTC), the Advanced Burner Reactor (ABR), and the Advanced Fuel Cycle Facility (AFCF). These three projects are envisioned to introduce used fuel separations, advanced fuel fabrication, and fast reactor technology in a manner that efficiently recycles material, produces the most energy out of the existing inventory of used fuel, and improves our ability to manage nuclear waste. The CFTC and ABR will depend on industry involvement and will not be covered by this paper. This paper will cover key considerations for the AFCF. The AFCF will provide the U.S. with the capabilities required to evaluate technologies that separate used fuel into reusable material and waste in a proliferation-resistant manner. The separations technology demonstration capability is coupled with a remote transmutation fuel fabrication demonstration capability in an integrated manner that demonstrates advanced safeguard technologies.

The fast-neutron breeder fission: development, operational experience, and implications for future design in the United States

1990 ◽  
Vol 331 (1619) ◽  
pp. 323-338
Keyword(s):  
United States ◽  
Fuel Cycle ◽  
The United States ◽  
Commercial Application ◽  
Operational Experience ◽  
Market Penetration ◽  
Future Design ◽  
Reactor Technology ◽  
The Status ◽  
Design Activities

As the need for breeder technology in the United States has receded into the more distant future, it has become clear that an alternative justification must be found for continued priority development of sodium-cooled fast-reactor technology. Both the modular high-temperature gas-cooled reactor and the liquid-metal-cooled reactor (LMR) have technical attributes that provide more simple and transparent solutions to some of the problems confronting the nuclear enterprise, in addition to their potential for greater market penetration, resource extension, and waste management improvements. For the past five years, the LMR development programme in the United States has attempted to use these technical attributes in more innovative ways to provide more elegant solutions for the practical commercial application of nuclear energy. This paper discusses the reasons and status of the technological approaches that have evolved to support these policy considerations. For the LMR, efforts are focused on four interrelated development thrusts: (1) increased use of standardization; (2) passive safety approaches; (3) modularity; and (4) improved fuel cycle approaches. The paper also discusses the status of related design activities being conducted by the General Electric Company and a team of U. S. vendors.

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.

An Initial Study on Modeling the United States Thermal Fuel Cycle Mass Flow Using Vensim

2008 ◽  
Author(s):  
Samuel Brinton ◽  
Akira Tokuhiro
Keyword(s):  
Mass Flow ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Flow Model ◽  
Fuel Cycle ◽  
Spent Fuel ◽  
Uranium Ore ◽  
Plant Construction ◽  
Mox Fuel ◽  
Fuel Fabrication

According to current forecasts, nuclear power plant construction and nuclear-generated electricity production is projected to increase in the next half-century. This is likely due to the fact that nuclear energy is an ‘environmental alternative’ to fossil fuel plants that emit greenhouse gases (GHG). Nuclear power also has a much higher energy density output than other alternative energy sources such as solar, wind, and biomass energies. There is also growing consensus that processing of low- and high-level waste, LLW and HLW respectively, is a political issue rather than a technical challenge. Prudent implementation of a closed fuel cycle not only curbs build-up of GHGs, but can equally mitigate the need to store nuclear used fuel. The Global Nuclear Energy Partnership (GNEP) is promoting gradual integration of fuel reprocessing, and deployment of fast reactors (FRs) into the global fleet for long-term uranium resource usage. The use of mixed oxide (MOX) fuel burning Light Water Reactors (LWR) has also been suggested by fuel cycle researchers. This study concentrated on modeling the construction and decommissioning rates of six major facilities comprising the nuclear fuel cycle, as follows: (1) current LWRs decommissioned at 60-years service life, (2) new LWRs burning MOX fuel, (3) new (Gen’ III+) LWRs to replace units and/or be added to the fleet, (4) new FRs to be added to the fleet, (5) new reprocessing and MOX fuel fabrication facilities and (6) new LWR fuel fabrication facilities. Our initial work [1] focused on modeling the construction and decommissioning rates of reactors to be deployed. This is being followed with a ‘mass flow model’, starting from uranium ore and following it to spent forms. The visual dynamic modeling program Vensim was used to create a system of equations and variables to track the mass flows from enrichment, fabrication, burn-up, and the back-end of the fuel cycle. Sensible construction and deployment rates were benchmarked against recent reports and then plausible scenarios considered parametrically. The timeline starts in 2007 and extends in a preliminary model to 2057; a further mass flow model scenario continues until 2107. The scenarios considered provide estimates of the uranium ore requirements, quantities of LLW and HLW production, and waste storage volume needs. The results of this study suggest the number of reprocessing facilities necessary to stabilize and/or reduce recently reported levels of spent fuel inventory. Preliminary results indicate that the entire national spent fuel inventory produced over the next ∼50 years can be reprocessed by a reprocessing plant construction rate of less than 0.07 plants/year (small capacity) or less than 0.05 plants /year (large capacity). Any larger construction rate could reduce the spent fuel inventory destined for storage. These and additional results will be presented.

Fuel Cycle Research and Development Program, Used Fuel Disposition Campaign Objective, Mission, Plans, and Activity Status

2010 ◽  
Vol 1265 ◽  
Author(s):  
William Mark Nutt ◽  
Mark Peters ◽  
Peter Swift ◽  
Kevin McMahon ◽  
Ken Sorenson ◽  
...  
Keyword(s):  
Research And Development ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Development Program ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Radioactive Material ◽  
Fundamental Aspect ◽  
Geologic Repository ◽  
Used Nuclear Fuel

AbstractThe safe management and disposition of used nuclear fuel and/or high level nuclear waste is a fundamental aspect of the nuclear fuel cycle. The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. However, a decision not to use the proposed Yucca Mountain Repository will result in longer interim storage at reactor sites than previously planned. In addition, alternatives to the once-through fuel cycle are being considered and a variety of options are being explored under the U.S. Department of Energy's Fuel Cycle Research and Development Program.These two factors lead to the need to develop a credible strategy for managing radioactive wastes from any future nuclear fuel cycle in order to provide acceptable disposition pathways for all wastes regardless of transmutation system technology, fuel reprocessing scheme(s), and/or the selected fuel cycle. These disposition paths will involve both the storing of radioactive material for some period of time and the ultimate disposal of radioactive waste.To address the challenges associated with waste management, the DOE Office of Nuclear Energy established the Used Fuel Disposition Campaign within its Fuel Cycle Research and Development Program in the summer of 2009. The mission of the Used Fuel Disposition Campaign is to identify alternatives and conduct scientific research and technology development to enable storage and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The near-and long-term objectives of the Fuel Cycle Research and Development Program and it's Used Fuel Disposition Campaign are presented.

La situazione dell'energia nucleare nel mondo: un quadro di sintesi

2009 ◽  
pp. 19-36
Author(s):  
Maurizio Cumo
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Technological Development ◽  
Reactor Technology ◽  
The World ◽  
Points Of View ◽  
Generation Costs ◽  
Jel Classifications

- This article gives an overview of the situation of nuclear power in the world and analyzes the problems of this source of energy from different points of view: the generation costs, fuel cycle, particularly with regard to the resources of uranium and radioactive waste, and the programs of technological development of new reactors.Key words: Nuclear energy, generation costs, uranium resources, radioactive waste, new reactor technology.JEL classifications: L94 Q40 Q31

scholarly journals A Fast Numerical Method for the Calculation of the Equilibrium Isotopic Composition of a Transmutation System in an Advanced Fuel Cycle

2012 ◽  
Vol 2012 ◽  
pp. 1-6
Author(s):  
F. Álvarez-Velarde ◽  
E. M. González-Romero
Keyword(s):  
Isotopic Composition ◽  
Numerical Method ◽  
Fuel Cycle ◽  
Direct Methods ◽  
Banach Fixed Point Theorem ◽  
Matrix Formulation ◽  
Fuel Fabrication ◽  
Advanced Fuel ◽  
Water Reactors ◽  
Arbitrary Precision

A fast numerical method for the calculation in a zero-dimensional approach of the equilibrium isotopic composition of an iteratively used transmutation system in an advanced fuel cycle, based on the Banach fixed point theorem, is described in this paper. The method divides the fuel cycle in successive stages: fuel fabrication, storage, irradiation inside the transmutation system, cooling, reprocessing, and incorporation of the external material into the new fresh fuel. The change of the fuel isotopic composition, represented by an isotope vector, is described in a matrix formulation. The resulting matrix equations are solved using direct methods with arbitrary precision arithmetic. The method has been successfully applied to a double-strata fuel cycle with light water reactors and accelerator-driven subcritical systems. After comparison to the results of the EVOLCODE 2.0 burn-up code, the observed differences are about a few percents in the mass estimations of the main actinides.

scholarly journals Atomic Routes and Cultures for a New Narrative on Franco’s Regime

2021 ◽  
Vol 10 (1) ◽  
pp. e005
Author(s):  
Ana Romero de Pablos
Keyword(s):  
United States ◽  
Financial Support ◽  
Nuclear Energy ◽  
Electrical Energy ◽  
The United States ◽  
Direct Influence ◽  
Nuclear Facilities ◽  
Franco Regime ◽  
Reactor Technology ◽  
Political Economic

A decision by two Spanish companies to start producing nuclear-based electrical energy was the beginning of a journey that led two Spanish engineers to the United States and Canada in 1957. They wanted to learn about the reactor technology that North American companies were developing, contact specialized consultants to explore possible consultancy services, and search out political, economic, and financial support to make their project viable. The trip’s travel log suggests that the route they set off on was decisive in convincing the dictatorship’s political, industrial, and economic powers of the importance of nuclear energy; this journey had a direct influence on subsequent construction of Spanish nuclear facilities and on the policies designed to manage it. In this article I suggest exploring this journey and its record to reflect on how nuclear energy participated in building a new narrative on the Franco regime, one that showed Spain as a modern, internationally-connected State capable of incorporating the latest atomic technologies.

scholarly journals Used Fuel Disposition Campaign – Objectives, Mission, Plans and Current Activities

2012 ◽  
Vol 1475 ◽  
Author(s):  
Kevin McMahon ◽  
Peter Swift ◽  
Ken Sorenson ◽  
Mark Nutt ◽  
Mark Peters
Keyword(s):  
Nuclear Fuel ◽  
Technology Development ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Radioactive Material ◽  
Fundamental Aspect ◽  
Geologic Repository ◽  
Used Nuclear Fuel ◽  
High Level

ABSTRACTThe safe management and disposition of used nuclear fuel and/or high level nuclear waste is a fundamental aspect of the nuclear fuel cycle. The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. However, a decision not to use the proposed Yucca Mountain Repository will result in longer interim storage at reactor sites than previously planned. In addition, alternatives to the once-through fuel cycle are being considered and a variety of options are being explored under the U.S. Department of Energy’s Fuel Cycle Technologies Program.These two factors lead to the need to develop a credible strategy for managing radioactive wastes from any future nuclear fuel cycle in order to provide acceptable disposition pathways for all wastes regardless of transmutation system technology, fuel reprocessing scheme(s), and/or the selected fuel cycle. These disposition paths will involve both the storing of radioactive material for some period of time and the ultimate disposal of radioactive waste.To address the challenges associated with waste management, the DOE Office of Nuclear Energy established the Used Fuel Disposition Campaign in the summer of 2009. The mission of the Used Fuel Disposition Campaign is to identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The near-and long-term objectives of the Fuel Cycle Technologies Program and its’ Used Fuel Disposition Campaign are presented.

Pu and MA Management in Thermal HTGRs: Impact at Fuel, Reactor and Fuel Cycle Levels

2008 ◽  
Author(s):  
J. C. Kuijper
Keyword(s):  
Nuclear Energy ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The European Union ◽  
International Forum ◽  
Reactor Technology ◽  
The Status ◽  
Fuel Reactor ◽  
Key Issues ◽  
The Eu

The PUMA project, a Specific Targeted Research Project (STREP) of the European Union EURATOM 6th Framework Program, is mainly aimed at providing additional key elements for the utilisation and transmutation of plutonium and minor actinides (neptunium and americium) in contemporary and future (high temperature) gas-cooled reactor design, which are promising tools for improving the sustainability of the nuclear fuel cycle. PUMA would also contribute to the reduction of Pu and MA stockpiles and to the development of safe and sustainable reactors for CO2-free energy generation. The project runs from September 1, 2006 until August 31, 2009. PUMA also contributes to technological goals of the Generation IV International Forum. It contributes to developing and maintaining the competence in reactor technology in the EU and addresses European stakeholders on key issues for the future of nuclear energy in the EU. An overview is presented of the status of the project at mid-term.

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