Study Ways to Increase KW in Fast Reactors with MOX Fuel Aiming for the Minimum of Sodium Void Reactivity Effect

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan
Keyword(s):  
Fast Reactors ◽  
Reactivity Effect ◽  
Mox Fuel

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.

A non destructive technique for determination of U233 and Pu content in MOX fuel pins for fast reactors

2011 ◽  
Vol 241 (8) ◽  
pp. 2783-2786 ◽  
Author(s):  
K.V. Vrinda Devi ◽  
T. Soreng ◽  
J.P. Panakkal ◽  
H.S. Kamath
Keyword(s):  
Fast Reactors ◽  
Mox Fuel ◽  
Non Destructive

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.

Non destructive determination of PuO2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning

2010 ◽  
Vol 399 (1) ◽  
pp. 122-127 ◽  
Author(s):  
K.V. Vrinda devi ◽  
T. Soreng ◽  
D. Mukherjee ◽  
J.P. Panakkal ◽  
H.S. Kamath
Keyword(s):  
Fast Reactors ◽  
Mox Fuel ◽  
Non Destructive ◽  
Gamma Scanning
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