HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS
Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical modeling, numerical solving of the direct and...
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| Format: | Article |
| Language: | English |
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Zaporozhye National Technical University
2018-07-01
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| Series: | Elektrotehnìka ta Elektroenergetika |
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| Online Access: | http://ee.zntu.edu.ua/article/view/143290 |
| Summary: | Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container.
Methodology. Mathematical modeling, numerical solving of the direct and inverse heat transfer problems.
Findings. The distribution of temperatures and heat transfer coefficients on the surfaces of guide tubes inside storage cask with spent fuel assemblies of power reactors WWER-1000 of Zaporizhska NPP are obtained. With usage of the iterative methodology of thermal processes modeling the detailed temperature fields of spent fuel assemblies inside storage cask are obtained. The maximum temperatures in each spent fuel assembly are defined and the places of the most heated fuel rods are identified.
Originality. For the first time with usage of iterative methodology of thermal processes modeling at the dry spent nuclear fuel storage the detailed information about thermal processes inside storage cask with spent fuela under normal conditions of operations is obtained.
Practical value. The safety of spent nuclear fuel of reactors WWER-1000 in the dry storage facility of Zaporizhska NPP is confirmed. The obtained results are reasonable for usage at development of scientific-methodological basis of safety of the dry storage of spent nuclear fuel of power reactors, and also useful at development and implementation of designs of creation and modernization of equipment for spent nuclear fuel. |
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| ISSN: | 1607-6761 2521-6244 |