Pressure vessel calculations for VVER-440 reactors
For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron tr...
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| Veröffentlicht in: | Radiation protection dosimetry 2005-01, Vol.115 (1-4), p.100-103 |
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| container_issue | 1-4 |
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| container_title | Radiation protection dosimetry |
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| creator | Hordósy, G. Hegyi, Gy Keresztúri, A. Maráczy, Cs Temesvári, E. Vértes, P. Zsolnay, É. |
| description | For the determination of the fast neutron load of the reactor pressure vessel a mixed calculational procedure was developed. The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed by the Monte Carlo code MCNP. The reaction rate in the activation detectors at surveillance positions and at the cavity were calculated and compared with measurements. In most cases, fairly good agreement was found. |
| doi_str_mv | 10.1093/rpd/nci038 |
| format | Article |
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The procedure was applied to the Unit II of Paks NPP, Hungary. The neutron source on the outer surfaces of the reactor was determined by a core design code, and the neutron transport calculations outside the core were performed by the Monte Carlo code MCNP. The reaction rate in the activation detectors at surveillance positions and at the cavity were calculated and compared with measurements. 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| ispartof | Radiation protection dosimetry, 2005-01, Vol.115 (1-4), p.100-103 |
| issn | 0144-8420 1742-3406 |
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| source | Oxford University Press Journals All Titles (1996-Current); MEDLINE |
| subjects | Algorithms Computer Simulation Equipment Failure Equipment Failure Analysis - methods Facility Design and Construction - methods Hungary Models, Statistical Monte Carlo Method Neutrons Nuclear Reactors Pressure Radiation Dosage Radiation Monitoring - methods Radiation Protection - instrumentation Radiation Protection - methods Risk Assessment - methods Software |
| title | Pressure vessel calculations for VVER-440 reactors |
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