PE Day 7:Nuclear Criticality, Kinetics, Neutronics
This theme covers much wide area. For example,
- Neutron transport and diffusion
- Reactor kinetics and control
- Macroscopic cross sections
- Burn-up and depletion
- Multigroup diffusion calculations
- Reactor criticality
Boron Carbide, B4C, can be employed in certain shielding applications.
10-B has a large (n,a) cross section fro thermal neutrons
| 固定リンク
« PE Day 6: Radiation Protection/Shielding/Interaction of Radiation with matter | トップページ | PE Day 8: Nuclear Measurements and Instruments »
「FE/PE」カテゴリの記事
- PE Link(2012.12.31)
- PE exma result(2012.12.30)
- PE Day 8: Nuclear Measurements and Instruments(2012.10.27)
- PE Day 7:Nuclear Criticality, Kinetics, Neutronics(2012.10.21)
- PE Day 6: Radiation Protection/Shielding/Interaction of Radiation with matter(2012.10.16)
コメント