The method of recursive sums and integrals for solving multigroup neutron diffusion equations
β Scribed by V. Yu. Vasil'ev; A. D. Dymnikov
- Publisher
- Springer US
- Year
- 1974
- Tongue
- English
- Weight
- 178 KB
- Volume
- 37
- Category
- Article
- ISSN
- 1573-8205
No coin nor oath required. For personal study only.
π SIMILAR VOLUMES
For the safety and the control of a nuclear power plant it is necessary to simulate the constituent processes on a computer system. The three-dimensional multigroup neutron di usion equations are commonly used to describe the nuclear ΓΏssion in the reactor core. They form a complicated system of coup
Conventional numerical methods for solving differential equations on a two-dimensional mesh are adapted to solving the one-group pile equation. The method yields the neutron density and the radial Laplacian in a standard manner which is not dependent on the number of control rods or other lattice ir