Some models of multigroup approximation in nuclear reactor theory. (English. Russian original) Zbl 0820.65095
Comput. Math. Math. Phys. 34, No. 2, 175-191 (1994); translation from Zh. Vychisl. Mat. Mat. Fiz. 34, No. 2, 214-233 (1994).
Summary: Approximate methods of solving boundary value problems of the theory of neutron transport, based on different ways of averaging cross-sections, are analysed. The methods of the theory of positive operators in Banach spaces with cones are used to establish the solvability conditions and properties of the corresponding solutions of linear and nonlinear conditional-critical problems which arise in the framework of such averaging.
MSC:
| 65R20 | Numerical methods for integral equations |
| 82D75 | Nuclear reactor theory; neutron transport |
| 45K05 | Integro-partial differential equations |
| 82C70 | Transport processes in time-dependent statistical mechanics |
| 47H07 | Monotone and positive operators on ordered Banach spaces or other ordered topological vector spaces |
