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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| Format: | Article |
| Language: | English |
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Elsevier
2023-04-01
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| Series: | Alexandria Engineering Journal |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1110016823000662 |
| _version_ | 1797847726691450880 |
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| author | Moustafa Aziz |
| author_facet | Moustafa Aziz |
| author_sort | Moustafa Aziz |
| collection | DOAJ |
| description | 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 kinetics and safety parameters were evaluated. It was found that thermal neutron spectrum is harder in UN than in UO2. UN can achieve a longer fuel residence time in the reactor than UO2. Kinetic and safety parameters are within the acceptable range similar to UO2. Control rod worth is lower in UN due to thermal flux hardening. This research was carried out with the addition of three types of variations of burnable poison. |
| first_indexed | 2024-04-09T18:16:58Z |
| format | Article |
| id | doaj.art-ccd494536a7542f4a5f96412e14d7b8c |
| institution | Directory Open Access Journal |
| issn | 1110-0168 |
| language | English |
| last_indexed | 2024-04-09T18:16:58Z |
| publishDate | 2023-04-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Alexandria Engineering Journal |
| spelling | doaj.art-ccd494536a7542f4a5f96412e14d7b8c2023-04-13T04:26:14ZengElsevierAlexandria Engineering Journal1110-01682023-04-016918A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR)Moustafa Aziz0Nuclear and Radiation Safety Research Center, Atomic Energy Authority, 3 Ahmed Alzomer Str, 11762 Nasr City, Cairo, EgyptMCNPX 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 kinetics and safety parameters were evaluated. It was found that thermal neutron spectrum is harder in UN than in UO2. UN can achieve a longer fuel residence time in the reactor than UO2. Kinetic and safety parameters are within the acceptable range similar to UO2. Control rod worth is lower in UN due to thermal flux hardening. This research was carried out with the addition of three types of variations of burnable poison.http://www.sciencedirect.com/science/article/pii/S1110016823000662Nitride fuel (UN)PWR reactorMCNPX codeMonte Carlo methodZirconium oxide (ZrO2) |
| spellingShingle | Moustafa Aziz A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) Alexandria Engineering Journal Nitride fuel (UN) PWR reactor MCNPX code Monte Carlo method Zirconium oxide (ZrO2) |
| title | A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) |
| title_full | A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) |
| title_fullStr | A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) |
| title_full_unstemmed | A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) |
| title_short | A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR) |
| title_sort | study on the feasibility of using uranium nitride un fuel in pressurized water reactors pwr |
| topic | Nitride fuel (UN) PWR reactor MCNPX code Monte Carlo method Zirconium oxide (ZrO2) |
| url | http://www.sciencedirect.com/science/article/pii/S1110016823000662 |
| work_keys_str_mv | AT moustafaaziz astudyonthefeasibilityofusinguraniumnitrideunfuelinpressurizedwaterreactorspwr AT moustafaaziz studyonthefeasibilityofusinguraniumnitrideunfuelinpressurizedwaterreactorspwr |