Analysis of VVER-1200 thermal characteristics using analytical calculation validated by PCTran simulator; Discover Mechanical Engineering; Vol. 4
| Parent link: | Discover Mechanical Engineering.— .— Berlin: Springer Nature Vol. 4.— 2026.— Article number 79, 21 p. |
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| Riassunto: | Title screen An analytical method was developed to predict the thermal parameters of the VVER-1200 pressurized water reactor (PWR). The peak temperatures of the fuel, outer fuel surface temperature, inner cladding surface temperature, outer cladding surface temperature, and coolant temperature were evaluated along and across the fuel rod, assuming that the hottest fuel rod is located at the reactor core center. This method analyzed the steady-state temperature distributions and was validated against a corresponding steady-state and time-dependent COMSOL Multiphysics model. Additionally, validation was conducted using the VVER-1200 PCtran Simulator for peak fuel temperature and the departure from nucleate boiling ratio (DNBR). The analytical method was employed to increase the reactor’s rated power from 100% to approximately 106% to assess the peak fuel temperature and the minimum departure from nucleate boiling ratio (MDNBR), both of which are crucial safety parameters for the operation of the VVER-1200. Given that the VVER-1200 initiates a scram slightly above 106% rated power, we evaluated the peak fuel temperature and DNBR at 100%, 102%, 104%, and 106% rated powers to determine the safety limits for both peak fuel temperature and MDNBR. The results from both the analytical method and simulations were found to be comparable Текстовый файл AM_Agreement |
| Lingua: | inglese |
| Pubblicazione: |
2026
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| Accesso online: | https://doi.org/10.1007/s44245-025-00175-7 |
| Natura: | Elettronico Capitolo di libro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=684611 |
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| 200 | 1 | |a Analysis of VVER-1200 thermal characteristics using analytical calculation validated by PCTran simulator |f Alexander G. Korotkikh, Christopher Joseph Odii | |
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| 330 | |a An analytical method was developed to predict the thermal parameters of the VVER-1200 pressurized water reactor (PWR). The peak temperatures of the fuel, outer fuel surface temperature, inner cladding surface temperature, outer cladding surface temperature, and coolant temperature were evaluated along and across the fuel rod, assuming that the hottest fuel rod is located at the reactor core center. This method analyzed the steady-state temperature distributions and was validated against a corresponding steady-state and time-dependent COMSOL Multiphysics model. Additionally, validation was conducted using the VVER-1200 PCtran Simulator for peak fuel temperature and the departure from nucleate boiling ratio (DNBR). The analytical method was employed to increase the reactor’s rated power from 100% to approximately 106% to assess the peak fuel temperature and the minimum departure from nucleate boiling ratio (MDNBR), both of which are crucial safety parameters for the operation of the VVER-1200. Given that the VVER-1200 initiates a scram slightly above 106% rated power, we evaluated the peak fuel temperature and DNBR at 100%, 102%, 104%, and 106% rated powers to determine the safety limits for both peak fuel temperature and MDNBR. The results from both the analytical method and simulations were found to be comparable | ||
| 336 | |a Текстовый файл | ||
| 371 | 0 | |a AM_Agreement | |
| 461 | 1 | |t Discover Mechanical Engineering |c Berlin |n Springer Nature | |
| 463 | 1 | |t Vol. 4 |v Article number 79, 21 p. |d 2026 | |
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a Thermal power | |
| 610 | 1 | |a Fuel rod | |
| 610 | 1 | |a Temperature | |
| 610 | 1 | |a Pressurized water reactor | |
| 610 | 1 | |a Departure from nucleate boiling ratio | |
| 610 | 1 | |a Critical heat flux | |
| 700 | 1 | |a Korotkikh |b A. G. |c specialist in the field of power engineering |c Professor of Tomsk Polytechnic University, Doctor of Physical and Mathematical Sciences |f 1976- |g Aleksandr Gennadievich |9 18113 | |
| 701 | 1 | |a Odii |b Ch. J. |g Christopher Joseph | |
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