Article
| Title: | An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium (English) |
| Author: | Mjasnikov, A. |
| Author: | Zezula, R. |
| Language: | English |
| Journal: | Acta Universitatis Carolinae. Mathematica et Physica |
| ISSN: | 0001-7140 |
| Volume: | 13 |
| Issue: | 2 |
| Year: | 1972 |
| Pages: | 61-71 |
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| Category: | math |
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| Date available: | 2012-10-05T18:25:31Z |
| Last updated: | 2012-10-05 |
| Stable URL: | http://hdl.handle.net/10338.dmlcz/142281 |
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Files
| Files | Size | Format | View |
|---|---|---|---|
| ActaCarolinae_013-1972-2_7.pdf | 1.618Mb | application/pdf |
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