scholarly journals Minor actinides transmutation in equilibrium cores of next generation FRs

2019 ◽  
Vol 5 (4) ◽  
pp. 353-359
Author(s):  
Alexander V. Egorov ◽  
Yurii S. Khomyakov ◽  
Valerii I. Rachkov ◽  
Elena A. Rodina ◽  
Igor R. Suslov
Keyword(s):  
Isotopic Composition ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Synergetic Effect ◽  
Transient State ◽  
Advanced Technology ◽  
Thermal Reactor ◽  
Spent Fuel ◽  
Operating Period ◽  
Nitride Fuel

The Russian Federation is developing a number of technologies within the «Proryv» project for closing the nuclear fuel cycle utilizing mixed (U-Pu-MA) nitride fuel. Key objectives of the project include improving fast reactor nuclear safety by minimizing reactivity changes during fuel operating period and improving radiological and environmental fuel cycle safety through Pu multi-recycling and МА transmutation. This advanced technology is expected to allow operating the reactor in an equilibrium cycle with a breeding ratio equaling approximately 1 with stable reactivity and fuel isotopic composition. Nevertheless, to reach this state the reactor must still operate in an initial transient state for a lengthy period (over 10 years) of time, which requires implementing special measures concerning reactivity control. The results obtained from calculations show the possibility of achieving a synergetic effect from combining two objectives. Using МА reprocessed from thermal reactor spent fuel in initial fuel loads in FR ensures a minimal reactivity margin during the entire fast reactor fuel operating period, comparable to the levels achieved in equilibrium state with any kind of relevant Pu isotopic composition. This should be combined with using reactivity compensators in the first fuel micro-campaigns. In the paper presented are the results of simulation of the overall life cycle of a 1200 MWe fast reactor, reaching equilibrium fuel composition, and respective changes in spent fuel nuclide and isotopic composition. It is shown that МА from thermal and fast reactors spent fuel can be completely utilized in the new generation FRs without using special actinide burners.

scholarly journals Evaluation of isotopic composition of fast reactor core in closed nuclear fuel cycle

2017 ◽  
Vol 153 ◽  
pp. 07031
Author(s):  
Georgy Tikhomirov ◽  
Mikhail Ternovykh ◽  
Ivan Saldikov ◽  
Peter Fomichenko ◽  
Alexander Gerasimov
Keyword(s):  
Isotopic Composition ◽  
Nuclear Fuel ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Core ◽  
Nuclear Fuel Cycle ◽  
Closed Nuclear Fuel Cycle

Environmental aspects of the fast reactor fuel cycle

1990 ◽  
Vol 331 (1619) ◽  
pp. 395-408 ◽  
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Thermal Reactor ◽  
Environmental Aspects ◽  
Fuel Cycles ◽  
Global Environmental ◽  
Delay Times ◽  
Fast Reactor Fuel ◽  
Reactor Accidents

The main characteristics that differentiate a developed fast reactor fuel cycle from the thermal reactor fuel cycles operating now are the higher fissile content of the fuel, the greater incentive to reprocess fuel at shorter delay times and the elimination of uranium mining. The local and global environmental impacts of a typical fuel cycle normalized to 1GW e a of output are estimated, including those from the fabrication, transport and reprocessing of fuel and from reactor operations. Radioactive emissions and radiation doses arising from these operations are compared with those from thermal reactor cycles. The risks of accidental discharges from reprocessing plants are discussed, but reactor accidents are not included. The requirements for safeguards are described. Typical inventories of radioactive wastes arising from reprocessing and from decommissioning have been calculated; the management and disposal of these wastes will pose no significant new problems. The overall result is that a transition from thermal to fast reactor fuel cycles should not result in any increase in environmental impact.

Lead Fast Reactor Sustainability

2014 ◽  
Author(s):  
Marco Ciotti ◽  
Jorge L. Manzano ◽  
Giacomo Grasso ◽  
Luigi Mansani ◽  
Carlo Petrovich
Keyword(s):  
Fast Reactor ◽  
Environmental Sustainability ◽  
Power Plants ◽  
Chemical Potential ◽  
Fuel Cycle ◽  
Geographical Area ◽  
Electricity Production ◽  
Spent Fuel ◽  
Closed Fuel Cycle ◽  
The Public

The electricity production systems, especially those based on nuclear fission, are increasingly facing more tight constraints and are subjected to more deep analyses based on the three aspects of economical sustainability, environmental sustainability and social sustainability. Nuclear Reactors future development has been outlined in the framework of the GIF (Generation IV International Forum), where the Lead Fast Reactor (LFR) is placed among the most promising innovative solutions. Many aspects of LFR offer a huge improvement from different points of view. The non pressurization of the system and the absence of sources of hazardous chemical potential energy enhances consistently its safety aspects, improving the perception of inherent safety of the Generation IV (G4) reactors in the public opinion. At the moment, due to the abundance of the new fossil resources, the competitiveness of Nuclear Power Plants is severely challenged, this aspect representing the most difficult to manage, besides the public acceptability. Moreover, for G4 reactors, an additional “cost premium” associated with the innovative technological concept has to be taken into account. Conversely, looking at the mid-term future, the real economical comparison has to be performed considering as competing sources, according to the IPCC recommendations and constraints enacted by the European Community, only CO2 free sources. In this context, economical competitiveness could be regained depending on the “cost premium” to be added to fossil fuels to become CO2 free, through the improvement of the carbon separation and storage techniques. The intrinsic lead properties (e.g.: low absorption cross section) permit to easily design LFR flexible cores, optimized with respect to a number of possible goals, as a long-lived core with minimal reactivity swing intended for battery concepts, or what is called an “adiabatic” core, where the entire Pu and MA inventory in the spent fuel can be indefinitely reused in a closed fuel cycle. The latter option allows to limit the waste throughput to the fission products only (along with the — unavoidable — losses from fuel reprocessing), and to benefit of natural resources minimization. These are both specific Generation IV goals envisioned to reach nuclear energy sustainability. An overall fuel cycle balance in a scenario with a step by step introduction of LFR reactors fleet grown in a specific geographical area, is in details analyzed in [1] and presented in this conference.

scholarly journals Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors

Energies ◽  
2021 ◽  
Vol 14 (11) ◽  
pp. 3094
Author(s):  
Mikołaj Oettingen
Keyword(s):  
Isotopic Composition ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Hybrid Energy ◽  
Cycle Simulation ◽  
Water Reactors

The paper presents the methodology for the estimation of the long-term actinides radiotoxicity and isotopic composition of spent nuclear fuel from a fleet of Pressurized Water Reactors (PWR). The methodology was developed using three independent numerical tools: the Spent Fuel Isotopic Composition database, the Nuclear Fuel Cycle Simulation System and the Monte Carlo Continuous Energy Burnup Code. The validation of spent fuel isotopic compositions obtained in the numerical modeling was performed using the available experimental data. A nuclear power embarking country benchmark was implemented for the verification and testing of the methodology. The obtained radiotoxicity reaches the reference levels at about 1.3 × 105 years, which is common for the PWR spent nuclear fuel. The presented methodology may be incorporated into a more versatile numerical tool for the modeling of hybrid energy systems.

Current Status of the Development of the Fast Reactor Fuel Cycle in India

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Current Status ◽  
Fast Reactor Fuel
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