A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR)
MCNPX computer code is used to design a three-dimensional model for a typical Pressurized Water reactor (PWR) core. Uranium Nitride fuel (UN) was tested for the reactor and the results were compared with a typical UO2 fuel. Neutron spectrum, power distributions, plutonium isotopes productions, and k...
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| Định dạng: | Bài viết |
| Ngôn ngữ: | English |
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Elsevier
2023-04-01
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| Loạt: | Alexandria Engineering Journal |
| Những chủ đề: | |
| Truy cập trực tuyến: | http://www.sciencedirect.com/science/article/pii/S1110016823000662 |