Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer

Atomic Energy ◽  
2020 ◽  
Vol 127 (5) ◽  
pp. 280-287
Author(s):  
E. O. Adamov ◽  
L. M. Zabud’ko ◽  
Yu. S. Mochalov ◽  
V. I. Rachkov ◽  
Yu. S. Khomyakov ◽  
...  
Atomic Energy ◽  
2021 ◽  
Author(s):  
A. F. Grachev ◽  
L. M. Zabudko ◽  
Yu. S. Mochalov ◽  
A. V. Belyaeva ◽  
F. N. Kryukov ◽  
...  

Atomic Energy ◽  
2020 ◽  
Vol 129 (2) ◽  
pp. 103-107
Author(s):  
A. F. Grachev ◽  
L. M. Zabud’ko ◽  
M. V. Skupov ◽  
F. N. Kryukov ◽  
V. G. Teplov ◽  
...  

Author(s):  
Maxim S. Fedorov ◽  
Nikolay A. Baydakov ◽  
Alexander N. Zhiganov ◽  
Dmitry V. Zozulya

This paper presents a review and a brief analysis of existing methods for producing mixed uranium nitride and plutonium, developed by both Russian and foreign scientists. The main parameters of the processes are considered, and their advantages and disadvantages are studied. Currently, the main areas of nitride fuel production are the metal hydride method and carbothermic reduction from the starting oxides. The methods are traditional ceramic technology. The starting products for the manufacture of nitride fuel powder can be either oxides (uranium dioxide and plutonium dioxide) or metals (uranium, plutonium and their alloys). To date, the technology for the manufacture of nitride fuel powder has not been finally selected. When considering existing methods, significant emphasis was placed on industrial applications and the simplicity of the hardware design processes. The laboratory methods are reflected in the work, which make it possible to simplify the process and reduce the costs of obtaining powders of mixed uranium and plutonium nitrides. However, they have significant difficulties in the technological implementation and low productivity of the processes. Of special interest among laboratory methods for producing mixed uranium and plutonium nitrides is the method of high-voltage electric pulse consolidation. This method allows sintering of tablets at the stage of powder pressing from mixed uranium and plutonium nitrides by passing a short high-voltage discharge with a power of several kW directly through the powder.


Author(s):  
S N Nikitin ◽  
D P Shornikov ◽  
B A Tarasov ◽  
V G Baranov ◽  
M A Burlakova

2017 ◽  
Vol 80 (8) ◽  
pp. 1470-1475
Author(s):  
A. A. Rusinkevich ◽  
A. S. Ivanov ◽  
G. V. Belov ◽  
M. V. Skupov

2018 ◽  
Vol 3 (3) ◽  
pp. 490
Author(s):  
V.Y. Shorov ◽  
S.N. Ryzhov ◽  
M.Y. Ternovykh ◽  
G.V. Tikhomirov

In this work was carried out the simulation in the SCALE6 code of an experiment on the BN-600 reactor on irradiating of fuel assemblies, containing samples of mixed nitride uranium-plutonium fuel. A comparison of the results for SCALE6 on the results of other codes is presented. The results of an estimation of uncertainties in the calculated data connected with uncertainties of an irradiation of an experimental sample and used neutron cross-sections library. Discussion of possible differences between analytical and experimental results is given.


2017 ◽  
Vol 375 ◽  
pp. 91-100
Author(s):  
Igor I. Konovalov ◽  
Boris A. Tarasov ◽  
Eduard M. Glagovskiy

Article discusses experimental data on creep of (U,Pu)N and other uranium compounds, and possible mechanism of mass-transfer. Proposed equation describes the following creep features: weak temperature dependence at T < 1000°C, creep acceleration in a fuel with micron-sized grains, and acceleration with the content of second phases formed by impurities and fission products. The difference in creep behavior in reactors with thermal and fast neutrons environmentsis discussed. Comparison of irradiation creep of nitride fuel and properties of cladding materials shows that under parameters of fast reactors and typical design of fuel element it is impossible to implement restraining of external nitride swelling. As initial porosity in the fuel will not compensate the nitride swelling, the cladding of fuel element will work in a mode of following the changing of fuel size. Some suggestions on the cladding material properties are done.


Atomic Energy ◽  
2017 ◽  
Vol 122 (5) ◽  
pp. 319-325 ◽  
Author(s):  
A. V. Belyaeva ◽  
I. F. Gil’mutdinov ◽  
I. Yu. Zhemkov ◽  
F. N. Kryukov ◽  
S. V. Kuz’min ◽  
...  

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