scholarly journals Scoping Studies of Dopants for Stabilization of Uranium Nitride Fuel

2019 ◽  
Vol 193 (11) ◽  
pp. 1255-1264
Author(s):  
Klara Insulander Björk ◽  
Aneta Herman ◽  
Marcus Hedberg ◽  
Christian Ekberg
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.


1973 ◽  
Author(s):  
J.G. Slaby ◽  
B.L. Siegel ◽  
L. Gedeon ◽  
R.J. Galbo
Keyword(s):  

JOM ◽  
2021 ◽  
Author(s):  
S. S. Parker ◽  
S. Newman ◽  
A. J. Fallgren ◽  
J. T. White

AbstractThe miscibility, lattice parameter, and thermophysical properties of (Th0.2U0.8)N and (Th0.5U0.5)N have been investigated. It is shown that additions of thorium nitride (ThN) to uranium nitride (UN) increases the thermophysical performance of the mixed nitride fuel form in comparison to reference UN. In the more dilute limit, additions of ThN serve as a burnable neutronic poison and reduces the change in keff over the lifecycle of the fuel. At higher concentrations, additions of ThN serve as a significant fertile source of 233U. Where appropriate, comparisons to previous work on UN + PuN mixtures are made, as this is a comparable fuel form for potential fast reactor concepts, and a suitable point of contrast in the possible design space afforded by mixed (ThxU1 − x)N fuel forms. The data from this work are the input parameters for finite element modeling of the temperature distribution in a compact reactor. The results of modeling and simulation of this core design are shown for the case of steady-state operation and during double, adjacent heat pipe failure.


1988 ◽  
Vol 151 (3) ◽  
pp. 318-326 ◽  
Author(s):  
Steven B. Ross ◽  
Mohamed S. El-Genk ◽  
R.Bruce Matthews

1990 ◽  
Vol 170 (2) ◽  
pp. 169-177 ◽  
Author(s):  
Steven B. Ross ◽  
Mohamed S. El-Genk ◽  
R.Bruce Matthews
Keyword(s):  

1988 ◽  
Vol 151 (3) ◽  
pp. 345 ◽  
Author(s):  
R.B. Matthews ◽  
K.M. Chidester ◽  
C.W. Hoth ◽  
R.E. Mason ◽  
R.L. Petty
Keyword(s):  

Sign in / Sign up

Export Citation Format

Share Document