Metallic Fast Reactor Separate Effect Studies for Fuel Safety

2021 ◽  
Author(s):  
Fidelma Di Lemma ◽  
Colby Jensen ◽  
Joshua Kane ◽  
Wei-Ying Chen Chen ◽  
Xiang Liu ◽  
...  
Keyword(s):  
Nuclear Energy ◽  
Source Term ◽  
Fuel Cycle ◽  
Energy Development ◽  
Department Of Energy ◽  
Waste Minimization ◽  
Metallic Fuel ◽  
Closed Fuel Cycle ◽  
Research Areas ◽  
Irradiation Performance

Abstract The benefits of sodium-cooled fast reactors (SFR) are well known and include: the possibility of a closed fuel cycle, proliferation resistance, waste minimization and breeding capabilities. Metallic fuel used in SFR has well demonstrated irradiation performance. More studies are, however, necessary to optimize and extend operational and safety limits through reduction of uncertainties in transient fuel behaviors and fuel failure thresholds. This paper describes the experimental Research and Development (R&D) program aimed at providing the necessary data to support the development of SFR optimized safety limits. This program integrates Separate Effects Testing (SET) and Integral Effects Testing (IET), combined with advanced Modelling and Simulation (M&S) to provide "solution-driven, goal-oriented, science-based approach to nuclear energy development" described in the Department of Energy Office of Nuclear Energy (DOE-NE) Roadmap. This R&D program, finally, focuses on delivering the science-based information necessary for supporting the licensing and utilization of SFR based on metallic fuel. Three research areas centered on fuel development by SET testing are described in this paper: 1) Microstructural, Chemistry and Material properties; 2) Thermo-mechanical behavior; and 3) Source term and fission product behavior. Preliminary results from these SET studies and the current instruments and experimental plan are presented.

Transmutation and the Global Nuclear Energy Partnership

2006 ◽  
Vol 985 ◽  
Author(s):  
James Bresee
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Energy Use ◽  
Fuel Cycle ◽  
Spent Fuel ◽  
Closed Fuel Cycle ◽  
State Of The Union ◽  
Foreign Countries ◽  
The U.S

AbstractIn the January 2006 State of the Union address, President Bush announced a new Advanced Energy Initiative, a significant part of which is the Global Nuclear Energy Initiative. Its details were described on February 6, 2006 by the U.S. Secretary of Energy. In summary, it has three parts: (1) a program to expand nuclear energy use domestically and in foreign countries to support economic growth while reducing the release of greenhouse gases such as carbon dioxide. (2) an expansion of the U.S. nuclear infrastructure that will lead to the recycling of spent fuel and a closed fuel cycle and, through transmutation, a reduction in the quantity and radiotoxicity of nuclear waste and its proliferation concerns, and (3) a partnership with other fuel cycle nations to support nuclear power in additional nations by providing small nuclear power plants and leased fuel with the provision that the resulting spent fuel would be returned by the lessee to the lessor. The final part would have the effect of stabilizing the number of fuel cycle countries with attendant non-proliferation value. Details will be given later in the paper.

A study of the nuclear natural resources utilization in open and closed fuel cycles: nuclear energy a sustainable and renewable source of energy

2020 ◽  
Vol 25 (2) ◽  
Author(s):  
Letícia Caroline Gonçalves ◽  
José Rubens Maiorino
Keyword(s):  
Natural Resources ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Closed Fuel Cycle ◽  
Pressurized Water ◽  
Renewable Source ◽  
Water Reactor ◽  
Fuel Cycles ◽  
Technological Advances ◽  
Breeder Reactors

In this work, the use of natural resources was analyzed using a simplified methodology and assuming calculation conditions close to the real ones, to assess the sustainability of the nuclear source and the efficiency in the use of these resources. For the analysis of open fuel cycles, four reactors were selected, these being the Pressurized Water Reactor (PWR) and Pressurized Heavy Water Reactor (PHWR), two Generation II reactors commonly used until today, the advanced Generation III reactor AP1000 and the conceptual reactor AP-Th 1000. For closed fuel cycles, the variation of the utilization of the natural resource alongside with the variation of the conversion factor were evaluated, parameterized by the burnup. It was observed that the Generation II reactors use only 1% of the natural resources and, despite technological advances, the Generation III reactor did not show a significant increase in comparison to the former. Although the closed fuel cycle includes recycling the burnt fuel from thermal reactors, it exploits only about 10% of the resources. Major improvements are observed in Fast Breeder Reactors, being able to obtain a use of almost 100% with the increase of the burning and the minimization of losses. Although the feasibility of using thorium as a nuclear fuel has been proven, it would be better used in a closed cycle, as in the self-sustainable Liquid Fluoride Thorium Reactor (LFTR), a Generation IV reactor that can transform the nuclear energy in a sustainable and renewable source of energy.

scholarly journals Achievability of radiological equivalence associated with closed nuclear fuel cycle with fast reactors: impact of uncertainty factors in scenarios of Russian nuclear power development through to 2100. Part 1. Fast and thermal reactors

2021 ◽  
Vol 30 (2) ◽  
pp. 62-76
Author(s):  
V.K. Ivanov ◽  
◽  
A.V. Lopatkin ◽  
A.N. Menyajlo ◽  
E.V. Spirin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Development ◽  
Radioactive Wastes ◽  
Fast Reactors ◽  
Power Development ◽  
The Public ◽  
Radiation Risks ◽  
Nuclear Power Development

The Russian Government approved the Energy Strategy of the Russian Federation (Government Decree No.1523-r of June 9, 2020). The Strategy envisages the use of both thermal (TR) and fast (FR) reactors. The Strategy points out that the problems of nuclear power are associated with po-tential high expenses for irradiated fuel and radioactive wastes management. The previously de-signed model of the Russian nuclear energy development suggested that fast reactors only would operate at NPPs after 2010. Radiological equivalence, expressed as the equivalence of lifetime radiation risks to the public from radioactive wastes and from primary uranium ore, was shown to be achieved after 100-year storage. The burnup of 241Am, 237Np и 242Сm in closed nu-clear fuel cycle with fast reactors is a key part in the achievability of radiation risks equivalence. Scenarios of the Russian nuclear energy development through to 2100 with account of uncertain-ty factors in the measurement of contribution of fast and thermal reactors to the electric energy production are considered in the paper. The following three scenarios were developed: uncer-tainty is replaced by FRs; uncertainty is replaced by TRs; 50 per cent of FRs and 50 per cent of TRs replace uncertainty. If the energy is produced by fast reactors only (scenario 1) radiological equivalence was found to be achieved in 412 years. In two other scenarios radiological equiva-lence will be achieved after more than 1000 years. Contribution of main dose-forming radionu-clides and relevant ratios of potential biological hazards is included in models regardless of whether uncertainty in nuclear energy development is taking or not taking into account. Results of the study of conditions for radiological equivalence achievement should be used for amending Strategic plan of Russian nuclear power development through to 2100 that meets requirements of radiation ecology and radiation protection of the public.

A metallic fuel cycle for Self-Consistent Nuclear Energy System (SCNES)

2002 ◽  
Vol 40 (3-4) ◽  
pp. 615-620
Author(s):  
Reiko Fujita ◽  
Mitsuaki Yamaoka ◽  
Masatoshi Kawashima ◽  
Masaki Saito ◽  
Haruaki Matsuura ◽  
...  
Keyword(s):  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy System ◽  
Metallic Fuel ◽  
Self Consistent

INPRO Results and Future Tasks: A Look From Russia

2004 ◽  
Author(s):  
Vladimir G. Asmolov ◽  
Leonid A. Bolshov ◽  
Evgeny P. Velikhov ◽  
Anatoly V. Zrodnikov ◽  
Vyacheslav P. Kuznetsov
Keyword(s):  
Sustainable Development ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Development Process ◽  
Fuel Cycle ◽  
Energy Development ◽  
Effective Development ◽  
Vladimir Putin ◽  
Realization Process ◽  
New Generation

Russia is supporting the INPRO Innovative Project, being fulfilled by the IAEA in the field of innovative nuclear energy. The participation of Russia in the INPRO is a part of realization process of Russia’s President Vladimir Putin Initiative, presented at the UN Millennium Summit in September 2000, on creation of new generation nuclear energy, meeting the requirements of sustainable development and excluding using the nuclear weapons technologies and materials. In 2003 the draft INPRO Methodology for assessment of the innovative nuclear energy systems correspondence to the requirements of sustainable development has been developed. At present time the Methodology’s approbation on the examples of national nuclear power technologies is being completed. It is supposed that the Methodology will be used as a navigator for the world nuclear energy development process. The INPRO stresses the timeliness of nuclear energy development problems. The International Organization on nuclear fuel cycle is the key decision of non-proliferation problem. Important are the questions of interaction and particularities of the INPRO and Generation IV programs. State support and international cooperation are conditions for effective development of nuclear energy.

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.

scholarly journals Gas Cooled Fast Reactor Research and Development in the European Union

2009 ◽  
Vol 2009 ◽  
pp. 1-7 ◽  
Author(s):  
Richard Stainsby ◽  
Karen Peers ◽  
Colin Mitchell ◽  
Christian Poette ◽  
Konstantin Mikityuk ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy System ◽  
Outlet Temperature ◽  
Framework Programme ◽  
The European Union ◽  
Closed Fuel Cycle ◽  
Gen Iv ◽  
Actinide Transmutation

Gas-cooled fast reactor (GFR) research is directed towards fulfilling the ambitious goals of Generation IV (Gen IV), that is, to develop a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. The research is directed towards developing the GFR as an economic electricity generator, with good safety and sustainability characteristics. Fast reactors maximise the usefulness of uranium resources by breeding plutonium and can contribute to minimising both the quantity and radiotoxicity nuclear waste by actinide transmutation in a closed fuel cycle. Transmutation is particularly effective in the GFR core owing to its inherently hard neutron spectrum. Further, GFR is suitable for hydrogen production and process heat applications through its high core outlet temperature. As such GFR can inherit the non-electricity applications that will be developed for thermal high temperature reactors in a sustainable manner. The Euratom organisation provides a route by which researchers in all European states, and other non-European affiliates, can contribute to the Gen IV GFR system. This paper summarises the achievements of Euratom's research into the GFR system, starting with the 5th Framework programme (FP5) GCFR project in 2000, through FP6 (2005 to 2009) and looking ahead to the proposed activities within the 7th Framework Programme (FP7).

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