Neutron cross section data library for PD-105, AG-109, XE-131 and CS-133 /
Đã lưu trong:
| 主要作者: | Lee, Y. D. |
|---|---|
| 其他作者: | Chang, J. H. |
| 格式: | Bài viết |
| 语言: | English |
| 主题: | |
| 标签: |
添加标签
没有标签, 成为第一个标记此记录!
|
| Thư viện lưu trữ: | Thư viện Trường Đại học Đà Lạt |
|---|
相似书籍
-
Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor
由: Trịnh, Thị Tú Anh, et al.
出版: (2023) -
Fission Neutrons
由: Kornilov, Nikolay
出版: (2015) - Neutronics modeling and simulation of SHARP for fast reactor analysis /
-
Fission and properties of neutron - rich nuclei : proceedings of the fourth International Conference, Sanibel Island, USA, 11 - 17 November 2007 /
出版: (2003) -
Simulation dataset of thermal and epithermal neutron self-shielding correction factors for 186W(n,γ )187W reaction rate experiments using tungsten foil targets
由: Trịnh, Thị Tú Anh, et al.
出版: (2025)