Zezula, Rostislav Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux. (English) Zbl 0228.35076 Apl. Mat. 15, 328-338 (1970). Page: −5 −4 −3 −2 −1 ±0 +1 +2 +3 +4 +5 Show Scanned Page MSC: 35Q40 PDEs in connection with quantum mechanics 35J60 Nonlinear elliptic equations 82D75 Nuclear reactor theory; neutron transport PDF BibTeX XML Cite \textit{R. Zezula}, Apl. Mat. 15, 328--338 (1970; Zbl 0228.35076) Full Text: EuDML OpenURL 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 This reference list is based on information provided by the publisher or from digital mathematics libraries. Its items are heuristically matched to zbMATH identifiers and may contain data conversion errors. It attempts to reflect the references listed in the original paper as accurately as possible without claiming the completeness or perfect precision of the matching.