| Title:
|
Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux (English) |
| Author:
|
Zezula, Rostislav |
| Language:
|
English |
| Journal:
|
Aplikace matematiky |
| ISSN:
|
0373-6725 |
| Volume:
|
15 |
| Issue:
|
5 |
| Year:
|
1970 |
| Pages:
|
328-338 |
| Summary lang:
|
English |
| Summary lang:
|
Czech |
| . |
| Category:
|
math |
| . |
| Summary:
|
In the paper the following problem of the nuclear reactor theory is mathematically formulated (in the two-group diffusion approximation and for multidimensional geometries): For a prescribed flux $\Phi$ of thermal neutrons in the core $\Omega$ of the finite homogenized reactor the distribution $M(x)$ of the fuel concentration in $\Omega$ which induces this given flux $\Phi$ in the reactor core $\Omega$ is to be determined. The conditions (in particular on the form of the boundary $\Omega$ of the core $\Omega$ as well as of the boundary $\Lambda$ of its reflector $\Lambda$) are given which are sufficient for the existence of a unique solution of this problem and, especially, also for the existence of a unique solution in the special case of flattened thermal neutron flux $\Phi = \Phi_0 = const$ in the reactor core $\Omega$ which is of practical significance for it yields the minimum of the critical mass. () |
| MSC:
|
35J60 |
| MSC:
|
35Q40 |
| MSC:
|
82D75 |
| idZBL:
|
Zbl 0228.35076 |
| idMR:
|
MR0273905 |
| DOI:
|
10.21136/AM.1970.103304 |
| . |
| Date available:
|
2008-05-20T17:48:44Z |
| Last updated:
|
2020-07-28 |
| Stable URL:
|
http://hdl.handle.net/10338.dmlcz/103304 |
| . |
| Reference:
|
[1] V. Bartošek R. Zezula: Flat Flux in a Slab reactor with Natural Uranium.Report ÚJV ČSAV 1310 (1965). |
| Reference:
|
[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. |
| Reference:
|
[3] A. Miasnikov R. Zezula: Radial flux flattening in a cylindrical reactor with natural uranium.(In Czech - Internal Report OTRF, ÚJV ČSAV). |
| Reference:
|
[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. 10.1016/0368-3230(66)90023-1 |
| Reference:
|
[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). |
| Reference:
|
[6] V. Bartošek R. Zezula: Stability of flat thermal flux in a slab reactor.Apl. Mat. 13 (1968), 367-375. MR 0243795 |
| Reference:
|
[7] Ladyzhenskaya O. A., Uraľceva N. N.: Linear and quasilinear equations of elliptic type.Nauka, Moscow 1964 (in russian). MR 0509265 |
| . |
