scholarly journals Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems

2014 ◽  
Vol 69 ◽  
pp. 314-330 ◽  
Author(s):  
S.F. Ashley ◽  
B.A. Lindley ◽  
G.T. Parks ◽  
W.J. Nuttall ◽  
R. Gregg ◽  
...  
Keyword(s):  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Systems ◽  
Open Cycle

scholarly journals Elaboration of approach to nuclear energy systems assessment by criterion of sustainable development

2018 ◽  
Vol 4 (1) ◽  
pp. 27-33
Author(s):  
Vladimir I. Usanov ◽  
Stepan A. Kviatkovskii ◽  
Andrey A. Andrianov
Keyword(s):  
Sustainable Development ◽  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Energy Systems ◽  
Nuclear Fuel Cycle ◽  
Time Interval ◽  
Subject Areas ◽  
Key Events

The paper describes the approach to the assessment of nuclear energy systems based on the integral indicator characterizing the level of their sustainability and results of comparative assessment of several nuclear energy system options incorporating different combinations of nuclear reactors and nuclear fuel cycle facilities. The nuclear energy systems are characterized by achievement of certain key events pertaining to the following six subject areas: economic performance, safety, availability of resources, waste handling, non-proliferation and public support. Achievement of certain key events is examined within the time interval until 2100, while the key events per se are assessed according to their contribution in the achievement of sustainable development goals. It was demonstrated that nuclear energy systems based on the once-through nuclear fuel cycle with thermal reactors and uranium oxide fuel do not score high according to the integral sustainable development indicator even in the case when the issue of isolation of spent nuclear fuel in geological formation is resolved. Gradual replacement of part of thermal reactors with fast reactors and closing the nuclear fuel cycle results in the achievement of evaluated characteristics in many subject areas, which are close to maximum requirements of sustainable development, and in the significant enhancement of the sustainability indicator.

scholarly journals Technology Assessment of Near-Term Open-Cycle Thorium-Fuelled Nuclear Energy Systems

2019 ◽  
pp. 117-124
Author(s):  
W. J. Nuttall ◽  
S. F. Ashley ◽  
R. A. Fenner ◽  
P. D. Krishnani ◽  
G. T. Parks
Keyword(s):  
Technology Assessment ◽  
Nuclear Energy ◽  
Energy Systems ◽  
Open Cycle ◽  
Near Term

scholarly journals Generation-IV nuclear reactor systems

2020 ◽  
Vol 246 ◽  
pp. 00011
Author(s):  
R. Caciuffo ◽  
C. Fazio ◽  
C. Guet
Keyword(s):  
Nuclear Energy ◽  
Nuclear Reactor ◽  
Fuel Cycle ◽  
Energy Systems ◽  
International Forum ◽  
Industrial Manufacturing ◽  
Energy Needs ◽  
World Energy ◽  
Nuclear Systems ◽  
Zero Carbon

In this paper, we provide a concise description of the six nuclear reactor concepts that are under development in the framework of the Generation-IV International Forum. After a brief introduction on the world energy needs, its plausible evolution during the next fifty years, and the constraints imposed by the necessity to address the climate challenges we are facing today, we will present the main features of the innovative nuclear energy systems that hold the promise to produce almost-zero-carbon-emission electricity, heat for chemistry and industrial manufacturing, hydrogen to be used as energy vector, and affordable freshwater. Potential advantages over currently available nuclear systems in terms of increased safety, reduced proliferation risks, economical affordability, sustainability of the fuel cycle, and management of the waste inventory will be critically discussed against the technical challenges that remain to be overcome.

Open cycle thorium–uranium-fuelled nuclear energy systems

2013 ◽  
Vol 166 (2) ◽  
pp. 74-81 ◽  
Author(s):  
Stephen F. Ashley ◽  
Richard A. Fenner ◽  
William J. Nuttall ◽  
Geoffrey T. Parks
Keyword(s):  
Nuclear Energy ◽  
Energy Systems ◽  
Open Cycle

scholarly journals Feasibility Studies on Pyro-SFR Closed Fuel Cycle and Direct Disposal of Spent Nuclear Fuel in Line with the Latest National Policy and Strategy of Korea

2017 ◽  
Vol 2017 ◽  
pp. 1-17
Author(s):  
Muhammad Minhaj Khan ◽  
Jae Min Lee ◽  
Jae Hak Cheong ◽  
Joo Ho Whang
Keyword(s):  
Nuclear Fuel ◽  
Cost Estimation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Energy Systems ◽  
Economic Feasibility ◽  
Closed Fuel Cycle

With a view to providing supportive information for the decision-making on the direction of the future nuclear energy systems in Korea (i.e., direct disposal or recycling of spent nuclear fuel) to be made around 2020, quantitative studies on the spent nuclear fuel (SNF) including transuranic elements (TRUs) and a series of economic analyses were conducted. At first, the total isotopic inventory of TRUs in the SNF to be generated from all thirty-six units of nuclear power plants in operation or under planning is estimated based on the Korean government’s official plan for nuclear power development. Secondly, the optimized deployment strategies are proposed considering the minimum number of sodium cooled-fast reactors (SFRs) needed to transmute all TRUs. Finally, direct disposal and Pyro-SFR closed nuclear energy systems were compared using equilibrium economic model and considering reduction of TRUs and electricity generation as benefits. Probabilistic economic analysis shows that the assumed total generation cost for direct disposal and Pyro-SFR closed nuclear energy systems resides within the range of 13.60~33.94 mills/kWh and 11.40~25.91 mills/kWh, respectively. Dominant cost elements and the range of SFR overnight cost which guarantees the economic feasibility of the Pyro-SFR closed nuclear energy system over the direct disposal option were also identified through sensitivity analysis and break-even cost estimation.

Users’ Requirements for Environmental Effects From Innovative Nuclear Energy Systems and Their Fuel Cycles

2002 ◽  
Author(s):  
M. Carreter ◽  
M. Gray ◽  
E. Falck ◽  
A. Bonne ◽  
M. Bell
Keyword(s):  
Environmental Impact ◽  
Impact Assessment ◽  
Environmental Impact Assessment ◽  
Environmental Effects ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Systems ◽  
User Requirements ◽  
Fuel Cycles ◽  
Nuclear Systems

The objective of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) is to support the safe, sustainable, economic and proliferation resistant use of nuclear technology to meet the needs of the 21st century. The first part of the project focusses on the development of an understanding of the requirements of possible users of innovative concepts for reactors and fuel cycle applications. This paper reports progress made on the identification of user requirements as they relate to the environment and environmental protection. The user requirements being formulated are intended to limit adverse environmental effects from the different facilities involved in the nuclear fuel cycles to be well below maximum acceptable levels. To determine if the user requirements are met, it is necessary to identify those factors that are relevant to assessment of the environmental performance of innovative nuclear systems. To this effect, Environmental Impact Assessment (EIA) and the Material Flow accounting (MFA) methodologies are being appraised for the suitability for application. This paper develops and provides the rationale for the “users’ requirements” as they are currently defined. Existing Environmental Impact Assessment and Materials Flow Accounting methodologies that can be applied to determine whether or not innovative technologies conform to the User Requirements are briefly described. It is concluded that after establishing fundamental principles, it is possible to formulate sets of general and specific users’ requirements against which, the potential adverse environmental effects to be expected from innovative nuclear energy systems (INES) can be assessed. The application of these users’ requirements should keep the adverse environmental effects from INES’s within acceptable limits.

Framework for Assessing Transition Scenarios to Sustainable Nuclear Energy Systems

2014 ◽  
Author(s):  
Galina Fesenko ◽  
Vladimir Kuznetsov ◽  
Vladimir Usanov
Keyword(s):  
Nuclear Fuel ◽  
Material Flow ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Nuclear Reactors ◽  
Energy Systems ◽  
Energy System ◽  
Analytical Framework ◽  
Member States ◽  
Fuel Cycles

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.

A Once-Through Fuel Cycle for Fast Reactors

2009 ◽  
Author(s):  
Kevan D. Weaver ◽  
John Gilleland ◽  
Charles Ahlfeld ◽  
Charles Whitmer ◽  
George Zimmerman
Keyword(s):  
Traveling Wave ◽  
Paradigm Shift ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Systems ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Design Work ◽  
Fuel Burn ◽  
Fast Neutron Spectrum

A paradigm shift has recently altered the design targets for advanced nuclear energy systems that use a fast neutron spectrum. A previous emphasis on extending fissile fuel reserves has been supplanted by a desire for reactor technologies that are “cleaner, more efficient, less waste-intensive, and more proliferation-resistant.” [1] This shift, along with recent advances in fast-reactor designs that enable high fuel burn-up even with fuels that have been minimally enriched, creates an opportunity to employ fast reactors in an open nuclear fuel cycle. These goals now appear feasible as a result of recent design work exploiting a phenomenon, known as a traveling wave, that can attain high burn-ups without reprocessing. A traveling-wave reactor (TWR) breeds and uses its own fuel in place as it operates. Fueled almost entirely by depleted or natural uranium, such reactors would also require little initial enrichment. We have performed calculations demonstrating that TWRs can achieve burn-ups of ≥20%, which is four to five times that realized in current LWRs. Burn-ups of up to 50% appear feasible. The factors that contribute to these high burn-ups and the implications for materials design will be discussed.

Fuels for Advanced Nuclear Energy Systems

MRS Bulletin ◽  
2009 ◽  
Vol 34 (1) ◽  
pp. 40-45 ◽  
Author(s):  
D. Petti ◽  
D. Crawford ◽  
N. Chauvin
Keyword(s):  
Nuclear Energy ◽  
Fuel Cycle ◽  
Fission Products ◽  
Energy Systems ◽  
Light Water Reactor ◽  
Current Status ◽  
Limiting Factor ◽  
Functional Requirements ◽  
Reactor Performance ◽  
Fuel Performance

AbstractFuels for advanced nuclear reactors differ from conventional light water reactor fuels and also vary widely because of the specific architectures and intended missions of the reactor systems proposed to deploy them. Functional requirements of all fuel designs for advanced nuclear energy systems include (1) retention of fission products and fuel nuclides, (2) dimensional stability, and (3) maintenance of a geometry that can be cooled. In all cases, anticipated fuel performance is the limiting factor in reactor system design, and cumulative effects of increased utilization and increased exposure to inservice environments degrade fuel performance. In this article, the current status of each fuel system is reviewed, and technical challenges confronting the implementation of each fuel in the context of the entire advanced reactor fuel cycle (fabrication, reactor performance, recycle) are discussed.

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