Abstract
Calculations were performed for **2**3**8U and **2**3**2Th blankets for a fusion hybrid reactor. Comparisons between results using ENDF/B-III and ENDF/B-IV cross sections for **2**3**8U were made. Corrections to the latter cross-section set were suggested, bringing the computed results close to the reported experimental ones.
| Original language | English |
|---|---|
| Pages (from-to) | 110-116 |
| Number of pages | 7 |
| Journal | Nuclear Technology |
| Volume | 48 |
| DOIs | |
| State | Published - 1980 |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 7 Affordable and Clean Energy
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