The neutron flux of a252Cf neutron activation analysis device using the MCNP code
โ Scribed by L. Zhao; E. Johnson; L. Robinson
- Publisher
- Springer
- Year
- 1999
- Tongue
- English
- Weight
- 321 KB
- Volume
- 240
- Category
- Article
- ISSN
- 1588-2780
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A conceptual neutronic design of the cold-neutron source (CNS) for the Egyptian second research reactor (ETRR-2) was done using the MCNP code. Parametric analysis to chose the type and geometry of the moderator, and the required CNS dimensions to maximize the cold neutron production was performed. T
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