Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux

Rostislav Zezula

Aplikace matematiky (1970)

  • Volume: 15, Issue: 5, page 328-338
  • ISSN: 0862-7940

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Zezula, Rostislav. "Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux." Aplikace matematiky 15.5 (1970): 328-338. <http://eudml.org/doc/14663>.

@article{Zezula1970,
author = {Zezula, Rostislav},
journal = {Aplikace matematiky},
language = {eng},
number = {5},
pages = {328-338},
publisher = {Institute of Mathematics, Academy of Sciences of the Czech Republic},
title = {Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux},
url = {http://eudml.org/doc/14663},
volume = {15},
year = {1970},
}

TY - JOUR
AU - Zezula, Rostislav
TI - Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux
JO - Aplikace matematiky
PY - 1970
PB - Institute of Mathematics, Academy of Sciences of the Czech Republic
VL - 15
IS - 5
SP - 328
EP - 338
LA - eng
UR - http://eudml.org/doc/14663
ER -

References

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  1. V. Bartošek R. Zezula, Flat Flux in a Slab reactor with Natural Uranium, Report ÚJV ČSAV 1310 (1965). (1965) Zbl0172.20201
  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. (1969) Zbl0174.41802
  3. A. Miasnikov R. Zezula, Radial flux flattening in a cylindrical reactor with natural uranium, (In Czech - Internal Report OTRF, ÚJV ČSAV). 
  4. V. Bartošek R. Zezula, 10.1016/0368-3230(66)90023-1, Journal of Nuclear Energy Parts A/B, 1966, vol. 20, pp. 129-139. (1966) Zbl0172.20201DOI10.1016/0368-3230(66)90023-1
  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). (1966) 
  6. V. Bartošek R. Zezula, Stability of flat thermal flux in a slab reactor, Apl. Mat. 13 (1968), 367-375. (1968) Zbl0172.20201MR0243795
  7. Ladyzhenskaya O. A., Uraľceva N. N., Linear and quasilinear equations of elliptic type, Nauka, Moscow 1964 (in russian). (1964) MR0509265

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