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Burnup calculations involving the processing of nuclear data as microscopic cross section. Then macroscopic cross section calculation was done by multiplying the <br /> <br /> <br /> microscopic cross section with a density of nuclides and all materials involved in the reactors i...
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| Format: | Final Project |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/16317 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
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