Published 1971
| Version v1
Report
Open
Numerical integration of transitional multigroup diffusion equations of neutron transport in a one-dimensional reactor
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.Files
3023915.pdf
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Additional details
Additional titles
- Original title (Russian)
- Численное интегрирование нестационарных многогрупповых диффузионных уравнений переноса нейтронов в одномерном реакторе
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- FEI--275
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 3023915
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGOL; INTEGRALS; NEUTRON TRANSFER; NUMERICAL SOLUTION; PULSED NEUTRON TECHNIQUES; REACTORS; TRANSPORT THEORY
- Descriptors DEC
- PROGRAMMING LANGUAGES