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 |
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Pages (from-to) | 110-116 |
Number of pages | 7 |
Journal | Nuclear Technology |
Volume | 48 |
DOIs | |
State | Published - 1980 |