Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon
This article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRA...
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| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2018-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2018/7862847 |
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| _version_ | 1832549427985776640 |
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| author | Soroush Heidari Sangestani Mohammad Rahgoshay Naser Vosoughi Mitra Athari Allaf |
| author_facet | Soroush Heidari Sangestani Mohammad Rahgoshay Naser Vosoughi Mitra Athari Allaf |
| author_sort | Soroush Heidari Sangestani |
| collection | DOAJ |
| description | This article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRAGON 4 and DONJON 4 coupling codes. The results of the developed package are compared with WIMS/CITATION and final safety analysis report of Bushehr VVER-1000 reactor (FSAR). Afterwards, time dependent thermal-hydraulic equations are answered by employing Single Heated Channel by Sectionalized Compressible Fluid method. Then, the obtained results were validated by the same transient simulation in a pressurized water reactor core. Then, thermal-hydraulic and neutronic modules are coupled concurrently by use of producing group constants regarding the thermal feedback effect. Results were compared to the mentioned transient simulation in RELAP5 computer code, which show that mass flux drop is sensed at the end of channel in several milliseconds which causes heat flux drop too. The thermal feedback resulted in production of some perturbations in the changes of these parameters. The achieved results for this very fast pressure drop represent accurate calculations of thermoneutronic parameters fast changes. |
| format | Article |
| id | doaj-art-2cba0a2a4d7b41a5911fc1ea2f355066 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2018-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-2cba0a2a4d7b41a5911fc1ea2f3550662025-02-03T06:11:13ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/78628477862847Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic PhenomenonSoroush Heidari Sangestani0Mohammad Rahgoshay1Naser Vosoughi2Mitra Athari Allaf3Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, IranDepartment of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, IranDepartment of Energy Engineering, Faculty of Engineering, Sharif University of Technology, Tehran, IranDepartment of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, IranThis article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRAGON 4 and DONJON 4 coupling codes. The results of the developed package are compared with WIMS/CITATION and final safety analysis report of Bushehr VVER-1000 reactor (FSAR). Afterwards, time dependent thermal-hydraulic equations are answered by employing Single Heated Channel by Sectionalized Compressible Fluid method. Then, the obtained results were validated by the same transient simulation in a pressurized water reactor core. Then, thermal-hydraulic and neutronic modules are coupled concurrently by use of producing group constants regarding the thermal feedback effect. Results were compared to the mentioned transient simulation in RELAP5 computer code, which show that mass flux drop is sensed at the end of channel in several milliseconds which causes heat flux drop too. The thermal feedback resulted in production of some perturbations in the changes of these parameters. The achieved results for this very fast pressure drop represent accurate calculations of thermoneutronic parameters fast changes.http://dx.doi.org/10.1155/2018/7862847 |
| spellingShingle | Soroush Heidari Sangestani Mohammad Rahgoshay Naser Vosoughi Mitra Athari Allaf Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon Science and Technology of Nuclear Installations |
| title | Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon |
| title_full | Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon |
| title_fullStr | Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon |
| title_full_unstemmed | Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon |
| title_short | Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon |
| title_sort | study of fast transient pressure drop in vver 1000 nuclear reactor using acoustic phenomenon |
| url | http://dx.doi.org/10.1155/2018/7862847 |
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