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Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux. (English) Zbl 0228.35076
MSC:
35Q40 PDEs in connection with quantum mechanics
35J60 Nonlinear elliptic equations
82D75 Nuclear reactor theory; neutron transport
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References:
[1] V. Bartošek R. Zezula: Flat Flux in a Slab reactor with Natural Uranium. Report ÚJV ČSAV 1310 (1965).
[2] R. Zezula: A sufficient condition for the flattening of thermal neutron flux and some related problems. (in onedimensional geometries). Apl. Mat. 14 (1969), 134-145. · Zbl 0174.41802
[3] A. Miasnikov R. Zezula: Radial flux flattening in a cylindrical reactor with natural uranium.
[4] V. Bartošek R. Zezula: Flat flux in a slab reactor with natural uranium. Journal of Nuclear Energy Parts A/B, 1966, vol. 20, pp. 129-139.
[5] M. Hron V. Lelek: Flux flattening by means of a nonuniform fuel distribution in a slab reactor with finite reflector. Report ÚJV ČSAV 1660 (1966).
[6] V. Bartošek R. Zezula: Stability of flat thermal flux in a slab reactor. Apl. Mat. 13 (1968), 367-375. · Zbl 0172.20201
[7] Ladyzhenskaya O. A., Uraľceva N. N.: Linear and quasilinear equations of elliptic type. Nauka, Moscow 1964
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