Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer

Atomic Energy ◽  
2021 ◽  
Author(s):  
A. F. Grachev ◽  
L. M. Zabud’ko ◽  
A. V. Belyaeva ◽  
F. N. Kryukov ◽  
O. N. Nikitin ◽  
...  
Atomic Energy ◽  
2021 ◽  
Author(s):  
A. F. Grachev ◽  
L. M. Zabudko ◽  
Yu. S. Mochalov ◽  
A. V. Belyaeva ◽  
F. N. Kryukov ◽  
...  

Atomic Energy ◽  
2019 ◽  
Vol 125 (5) ◽  
pp. 314-321 ◽  
Author(s):  
A. F. Grachev ◽  
A. A. Zherebtsov ◽  
L. M. Zabud’ko ◽  
E. A. Zvir ◽  
F. N. Kryukov ◽  
...  

Atomic Energy ◽  
2020 ◽  
Vol 127 (6) ◽  
pp. 356-361 ◽  
Author(s):  
A. V. Boldyrev ◽  
A. V. Zadorozhnyi ◽  
V. D. Ozrin ◽  
V. I. Tarasov ◽  
I. O. Dolinskii ◽  
...  

Atomic Energy ◽  
2019 ◽  
Vol 126 (3) ◽  
pp. 182-190
Author(s):  
A. F. Grachev ◽  
L. M. Zabud’ko ◽  
Yu. A. Ivanov ◽  
M. V. Skupov ◽  
E. A. Zvir ◽  
...  

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.


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