Deterministic Calculation Method for Continuous-energy Neutron Transport Equation in No-resonance Energy-range
In analyzing the power density distribution within the core of a nuclear reactor, it is necessary to employ numerical methods to solve the neutron transport equation and obtain the neutron flux density distribution. Deterministic method, either the two-step or the one-step scheme, employed multi-gro...
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| Format: | Article |
| Language: | English |
| Published: |
Editorial Board of Atomic Energy Science and Technology
2024-06-01
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| Series: | Yuanzineng kexue jishu |
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