The Perspective of Creating a Closed Fuel Cycle Based on the Fast Reactors in Ukraine

2012 ◽  
Author(s):  
I. A. Tereshchenko ◽  
S. O. Ustimenko
Keyword(s):  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Light Water Reactors ◽  
Fast Reactors ◽  
Closed Fuel Cycle ◽  
Mox Fuel ◽  
Fast Breeder Reactors ◽  
Water Reactors ◽  
Breeder Reactors ◽  
New Generation

It is known that the IAEA considers options for a fuel cycle with light water reactors of new generation (LWR); however, the uranium reserves will not last forever, so the input of fast reactors in order to “close” the fuel cycle is currently the best option. Therefore, the preliminary calculations of the approximate cycle took place, and a comparative analysis of cycles using only LWR and the cycle with a gradual replacement of LWR by fast breeder reactors was carried out as well. It is appropriate, because there is a sufficiently large number of spent nuclear fuel now is accumulated in temporary storage, but soon it has to be either converted into fresh fuel or disposed (that is unacceptable in all respects). The main problem of the closed fuel cycle is usage of MOX-fuel, but this type of fuel is elaborated now and will be improved upon.

scholarly journals On the possibility to improve mixed uranium-plutonium fuel in fast reactors

2020 ◽  
Vol 6 (2) ◽  
pp. 131-135
Author(s):  
Vladimir A. Eliseev ◽  
Dmitry A. Klinov ◽  
Noël Camarcat ◽  
David Lemasson ◽  
Clement Mériot ◽  
...  
Keyword(s):  
Isotopic Composition ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
Fast Reactors ◽  
Light Water ◽  
Fuel Cycles ◽  
Mox Fuel ◽  
Water Reactors ◽  
Operational Activities

Accumulation of plutonium extracted from the spent nuclear fuel (SNF) of light water reactors is one of the central problems in nuclear power. To reduce out-of-the-reactor Pu inventory, leading nuclear power countries (France, Japan) use plutonium in light water power reactors in the form of MOX fuel, with half of Pu fissioning in this fuel. The rest of Pu cannot be reused easily and efficiently in light water reactors because of the high content of even isotopes. Plutonium for which there are no potential consumers is accumulated. Unlike thermal reactors, fast reactors take plutonium of any isotopic composition. That makes it possible to improve plutonium isotopic composition and to reduce the fraction of even isotopes to the level that allows reuse of such plutonium in thermal reactors. The idea of changing the isotopic composition of Pu in fast reactors is well-known. The originality of the research lies in applying this idea to combine the fuel cycles of fast and thermal reactors. Pu isotopic composition can be improved by combining certain operational activities in order to supply fuel to thermal and fast reactors. Scientific and technological justification of the possibility will let Russian BN technologies and French MOX fuel technologies work in synergy with thermal reactors.

The Fast Breeder Reactor — Energy without Depletion of Natural Resources

1976 ◽  
Vol 190 (1) ◽  
pp. 163-175
Author(s):  
R. D. Vaughan ◽  
A. A. Farmer
Keyword(s):  
Energy Production ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Primary Energy ◽  
Western World ◽  
Fast Reactors ◽  
Generating Capacity ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Fuel Reprocessing

SYNOPSIS. Nuclear power should account for 20% of primary energy production in the Western world by the end of the century, but only if growth of generating capacity can be freed of the constraint of uranium supply. It is shown that, providing fast breeder reactors and their associated fuel reprocessing facilities are developed quickly, a substantial increase in nuclear capacity could be provided by fast reactors. The relative importance of various fuel cycle parameters is spelt out and brief accounts are given of the alternative fast reactors being developed to meet the requirements.

Improvement of the Fast Breeder Reactor Plant Dynamic Analysis Code ADYTUM

2012 ◽  
Author(s):  
Isao Tatewaki ◽  
Hiroshi Endo ◽  
Tomoko Ishizu ◽  
Yoshihisa Shindo
Keyword(s):  
Dynamic Analysis ◽  
Safety Evaluation ◽  
Model Parameters ◽  
Light Water Reactors ◽  
Analysis Model ◽  
One Dimensional ◽  
Code Structure ◽  
Fast Breeder Reactors ◽  
Water Reactors ◽  
Breeder Reactors

Japan Nuclear Energy Safety Organization, JNES has been studying the methodology to apply the risk informed regulation (RIR) to the safety regulation for Light Water Reactors (LWRs) and Fast Breeder Reactors (FBRs). A best estimate code of plant dynamic analysis is necessary for the RIR application and it must be validated very carefully. To fulfill this requirement, JNES has been developing a FBR plant dynamic analysis code ADYTUM, which has flexible code structure and algorisms for applying to the safety evaluation. ADYTUM is composed of several inherent components of physical model named “module”, based on one-dimensional flow network model which calculates the sodium flow and the heat transfer between sodium and structures in primary and secondary loop systems. In addition, ADYTUM is designed so that variables of each module have no connection with other modules. Therefore, ADYTUM allows us to calculate and validate each module alone [1]. In order to reinforce the precision of the analysis model of ADYTUM, we are trying to quantify the uncertainty of the model parameters by use of the Code Scaling, Applicability, and Uncertainty (CSAU) methodology for the primary pump stick accident in FBRs. The approaches of the CSAU are (1) to define the physical value and the range of time scale which are focused on, (2) to select the input parameters which have a profound effect on the physical value of focus by use of the phenomena identification and ranking table, and finally (3) to provide the uncertainty quantification of the focusing value.

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors

Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle

Atomic Energy ◽  
2021 ◽  
Author(s):  
N. V. Gorin ◽  
N. P. Voloshin ◽  
Yu. I. Churikov ◽  
A. N. Chebeskov ◽  
V. P. Kuchinov ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Fast Reactors ◽  
Closed Fuel Cycle

When would fast reactors become competitive with light water reactors? Methodology and key parameters

2017 ◽  
Vol 100 ◽  
pp. 103-113 ◽  
Author(s):  
Anne Baschwitz ◽  
Gilles Mathonnière ◽  
Sophie Gabriel ◽  
Jean-Guy Devezeaux de Lavergne ◽  
Yann Pincé
Keyword(s):  
Light Water Reactors ◽  
Fast Reactors ◽  
Light Water ◽  
Water Reactors
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