Solution of neutron-transport multigroup equations system in subcritical systems
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied. Neutron yield and mult...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
National Research Nuclear University (MEPhI)
2018-10-01
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| Series: | Nuclear Energy and Technology |
| Online Access: | https://nucet.pensoft.net/article/29837/download/pdf/ |