Published 1995
| Version v1
Journal article
New numerical calculation algorithm of neutron distribution in problems of reactor physics and radiation shielding. Part 1
Description
A new numerical method of solving the equations of transport in the integral form is presented. Basic and conjugated equations are derived, particular approximations and differential algorithms of the method are described. Computer codes using this method and some numerical investigations of the solutions of neutron transport problem for reactor and shielding purposes are briefly considered
Additional details
Additional titles
- Original title (Russian)
- Новый численный алгоритм расчета распределения нейтронов в задачах физи ки реакторов и радиационной защиты
Publishing Information
- Journal Title
- Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
- Journal Issue
- no.1
- Journal Page Range
- p. 20-31.
- ISSN
- 0204-3327
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 28075578
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ADJOINT DIFFERENCE METHOD; ALGORITHMS; COMPUTER CALCULATIONS; NEUTRON TRANSPORT THEORY; PROBABILISTIC ESTIMATION; REACTOR PHYSICS; SHIELDING; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; TRANSPORT THEORY
Optional Information
- Notes
- 6 refs., 1 fig.