РАЗРАБОТКА КОМПЬЮТЕРНОЙ МОДЕЛИ СОВЕРШЕНСТВОВАНИЯ СИСТЕМЫ ПАССИВНОГО ОТВОДА ТЕПЛА ОТ БАССЕЙНА ВЫДЕРЖКИ С ДВУХФАЗНЫМ КОЛЬЦЕВЫМ ТЕРМОСИФОНОМ
Ключевые слова:
Компьютерная модель, система пассивного отвода тепла, система охлаждения топливного бассейна
Аннотация
Цель данного исследования заключается в создании компьютерной модели, которая будет
использоваться для улучшения системы пассивного отвода тепла от бассейна выдержки с двух-
фазным кольцевым термосифоном. Данная модель позволит провести анализ работы системы,
определить набор квазиоптимальных решений для ее параметров и улучшить эффективность
отвода тепла. Разработка такой модели может помочь улучшить процессы теплообмена и по-
высить эффективность работы системы в целом. Метод. Для решения поставленной задачи использовались методы математического и компьютерного моделирования, производилось изучение
механизмов передачи тепла в системе и определение оптимальных параметров для эффективного
отвода тепла, а также сравнение различных вариантов конструкции и параметров системы для
выбора наиболее эффективного решения. Использование данных методов обеспечил комплексный
подход к разработке и совершенствованию системы пассивного отвода тепла с двухфазным коль-
цевым термосифоном. Результат. Разработана компьютерная модель совершенствования сис-
темы пассивного отвода тепла от бассейна выдержки с двухфазным кольцевым термосифоном.
т а модель позволяет проводить анализ работы системы, усовершенствовать ее параметры и
улучшить эффективность отвода тепла. Создание такой модели является важным шагом в раз-
витии и совершенствовании системы, позволяя более точно прогнозировать ее работу и вносить
необходимые улучшения. Вывод. Разработанная компьютерная модель может быть использована
для дальнейших исследований, усовершенствования процессов отвода тепла и повышения эффек-
тивности работы системы в целом. Она позволяет более детально изучить процессы отвода
тепла и настроить работу системы. Модель предоставляет возможность проводить численные
расчеты, анализировать различные сценарии и оценивать эффективность изменений параметров
системы.
Литература
1. Bukrinskiy A.M. Bezopasnost' atomnykh stanciy po federal'nym normam i pravilam Rossii i standartam
MAGATE. Sravnenie osnovnykh principov i trebovaniy po obespecheniyu bezopasnosti [Safety of nuclear
power plants according to federal norms and rules of Russia and IAEA standards. Comparison of
the basic principles and requirements for safety]. 3rd ed. Moscow: NTC YaRB, 2019, 196 p.
2. Dmitriev S.M. [i dr.]. Issledovanie lokal'noy gidrodinamiki teplonositelya v smeshannoy aktivnoy
zone reaktora VVER [Investigation of the local hydrodynamics of the coolant in the mixed core of the
VVER reactor], Energetika. Izvestiya vysshikh uchebnykh zavedeniy i energeticheskikh ob"edineniy
SNG [Energy. News of higher educational institutions and energy associations of the CIS], 2020, Vol.
63, No. 2, pp. 151-162. Available at: https://doi.org/10.21122/1029-7448-2020-63-2-151-162.
3. Sorokin V.V. Raschet vremeni puska passivnogo kataliticheskogo rekombinatora vodoroda
lokalizuyushchey sistemy bezopasnosti AES s VVER [Calculation of the start-up time of the passive catalytic
hydrogen recombinator of the localized safety system of nuclear power plants with VVER],
Energetika. Izvestiya vysshikh uchebnykh zavedeniy i energeticheskikh ob"edineniy SNG [Energy. News
of higher educational institutions and energy associations of the CIS], 2022, Vol. 65, No. 1, pp. 67-75.
4. Morozov A.V. [i dr.]. Puti sovershenstvovaniya sistemy passivnogo okhlazhdeniya aktivnoy zony
reaktora VVER [Ways to improve the passive cooling system of the VVER reactor core], Mater. XIV
Mezhdunarodnoy nauchno-tekhnicheskoy konferencii «Problemy sovershenstvovaniya toplivnoenergeticheskogo
kompleksa», Saratov, 30 oktyabrya - 1 noyabrya 2018 [Proceedings of the XIV International
Scientific and Technical Conference "Problems of improving the fuel and energy complex",
Saratov, October 30 - November 1, 2018]. Saratov, 2018, pp. 115-120.
5. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants. IAEATECDOC-
1624. Vienna: IAEA, 2009. Mode of access: https://www-pub.iaea.org/MTCD/ Publications/
PDF/te_1624_web.pdf (Date of access: 07.01.2022).
6. Natural circulation in water cooled nuclear power plants: Phenomena, models, and methodology for
system reliability assessments. IAEA-TECDOC-1474. Vienna: IAEA, 2005. Mode of access:
https://www-pub.iaea.org/MTCD/Publications/PDF/TE_1474_web.pdf (Date of access: 05.01.2022).
7. Sierchuła J. Analysis of passive residual heat removal system in AP1000 nuclear power plant, IOP
Conference Series: Earth and Environmental Science, 2019, Vol. 214. Art. ID 012095. Available at:
https://doi.org/10.1088/1755-1315/214/1/012095.
8. Li Feng [et al.]. Design, Experiment, and Commissioning of the Passive Residual Heat Removal System
of hina’s Generation III Nuclear Power PR1000, Science and Technology of Nuclear Installations,
2021, 6 p. Available at: https://doi.org/10.1155/2021/6680400.
9. Dan P.D., Rey D.A. Teplovye truby [Heat pipes], transl. from Engl. by. Yu.A. Zeygarnik. Moscow:
Energiya, 1979, 272 p.
10. Chi S. Teplovye truby: Teoriya i praktika [Heat pipes: Theory and practice][: transl. from Engl. by.
V.Ya. Sidorov. Moscow: Mashinostroenie, 1981, 207 p.
11. Vijayan P.K., Nayak A.K., Kumar N. Chapter 1 - Natural circulation loops - advantages, challenges,
and classification, Single-Phase, Two-Phase and Supercritical Natural Circulation Systems.
Woodhead Publishing, 2019, pp. 1-30. Available at: https://doi.org/10.1016/B978-0-08-102486-
7.00001-9.
12. Sviridenko I.I. [et al.]. Passive Residual Heat Removal System for WWER with the Thermosiphon
Heatexchange Equipment, International Journal of Energy for a Clean Environment, 2015, Vol. 16,
No. 1-4, pp. 209-223. Available at: https://doi.org/10.1615/InterJEnerCleanEnv.2015015683.
13. Sviridenko I.I., Shevelev D.V., Sverdlov V.V. Raschetnye issledovaniya avariynogo teplootvoda VVER
avtonomnoy termosifonnoy SPOT pervogo kontura [Computational studies of the emergency heat sink
of the VVER autonomous thermosiphon SPOT of the first circuit], Tekhnologii obespecheniya
zhiznennogo tsikla yadernykh energeticheskikh ustanovok: Nauch.-tekh. sb. [Technologies for ensuring
the life cycle of nuclear power plants: scientific and technical collection]. Sosnovyy Bor: FGUP
NITI, 2018, Issue 3 (13), pp. 28-41.
14. Sviridenko I.I. Uderzhanie reaktora v podkriticheskom sostoyanii pri zaproektnoy avarii odnovremennym
raskholazhivaniem i dekompressiey pervogo kontura [Keeping the reactor in a subcritical state in case of an
out-of-design accident by simultaneous cooling and decompression of the primary circuit], Izvestiya
vysshikh uchebnykh zavedeniy. Yadernaya energetika [News of higher educational institutions. Nuclear energy],
2019, No. 1, pp. 85-96. Available at: https://doi.org/10.26583/npe.2019.1.08.
15. Instruktsiya po likvidatsii avariy i avariynykh situatsiy na reaktornoy ustanovke energobloka № 5
Zaporozhskoy AES. 05.GT.00.IE.11. OP «Zaporozhskaya AES», 2017 [Instructions for the elimination
of accidents and emergencies at the reactor unit of power unit No. 5 of the Zaporizhia NPP.
05.GT.00.IE.11. OP "Zaporizhia NPP", 2017], 444 p.
16. Vasil'ev,L.L. Teploobmenniki na teplovykh trubakh [Heat exchangers on heat pipes]. Minsk: Nauka i
tekhnika, 1981, 143 p.
17. Bezrodnyy M.K., Pioro I.L., Kostyuk T.O., Fakt K. Protsessy perenosa v dvukhfaznykh
termosifonnykh sistemakh. Teoriya i praktika [Transfer processes in two-phase thermosiphon systems.
Theory and practice], 2005, 704 p.
18. AES «Kudankulam». Klassifikatsiya sistem, oborudovaniya, truboprovodov i elementov teplotekhnicheskoy
chasti. KK.UJA.0.SR.PZ.PR004. Institut «Atomenergoproekt», 2002 [Kudankulam
NPP. Classification of systems, equipment, pipelines and elements of the thermal engineering part.
KK.UJA.0.SR.PZ.PR004. Atomenergoproject Institute, 2002].
19. Blagoveshchenskiy A.Ya. [i dr.]. Kontseptsiya rasshirennogo ispol'zovaniya estestvennoy tsirkulyatsii
teplonositelya pervogo kontura v energoblokakh s VVER-1000 (1200) i perspektivy ee realizatsii [The
concept of expanded use of natural circulation of the primary coolant in power units with VVER-1000
(1200) and prospects for its implementation], Bezopasnost', effektivnost' i ekonomika atomnoy energetiki:
Mater. 8-y Mezhdunar. nauch.-tekhn. konf., Moskva, 23-25 maya 2012 g. [Safety, efficiency and economics
of nuclear energy: Materials of the 8th International Scientific and Technical Conference. Conf.,
Moscow, May 23-25, 2012]. Moscow: Kontsern «Rosenergoatom», 2012, pp. 602-605.
20. Bukin N.V. [i dr.]. Vliyanie passivnykh sistem na protekanie tipichnykh zaproektnykh avariy RU V-392
[The influence of passive systems on the course of typical out-of-design accidents of RU V-392],
Obespechenie bezopasnosti AES s VVER: Mater. 2-y nauch.-tekhn. konf., Podol'sk, 19-23 noyabrya 2001
g. [Ensuring the safety of nuclear power plants with VVER: materials of the 2nd scientific and technical
Conference, Podolsk, November 19-23, 2001]. Available at: http://www.gidropress.podolsk.ru/files/ proceedings/
mntk2001/report1/vpsnptza.pdf (accessed 17 September 2021).
21. Andrushechko S.A. [i dr.]. AES s reaktorom tipa VVER-1000. Ot fizicheskikh osnov ekspluatatsii do
evolyutsii proekta [Nuclear power plant with a VVER-1000 reactor. From the physical foundations of
operation to the evolution of the project]. Moscow: Logos, 2010, 603 p.
MAGATE. Sravnenie osnovnykh principov i trebovaniy po obespecheniyu bezopasnosti [Safety of nuclear
power plants according to federal norms and rules of Russia and IAEA standards. Comparison of
the basic principles and requirements for safety]. 3rd ed. Moscow: NTC YaRB, 2019, 196 p.
2. Dmitriev S.M. [i dr.]. Issledovanie lokal'noy gidrodinamiki teplonositelya v smeshannoy aktivnoy
zone reaktora VVER [Investigation of the local hydrodynamics of the coolant in the mixed core of the
VVER reactor], Energetika. Izvestiya vysshikh uchebnykh zavedeniy i energeticheskikh ob"edineniy
SNG [Energy. News of higher educational institutions and energy associations of the CIS], 2020, Vol.
63, No. 2, pp. 151-162. Available at: https://doi.org/10.21122/1029-7448-2020-63-2-151-162.
3. Sorokin V.V. Raschet vremeni puska passivnogo kataliticheskogo rekombinatora vodoroda
lokalizuyushchey sistemy bezopasnosti AES s VVER [Calculation of the start-up time of the passive catalytic
hydrogen recombinator of the localized safety system of nuclear power plants with VVER],
Energetika. Izvestiya vysshikh uchebnykh zavedeniy i energeticheskikh ob"edineniy SNG [Energy. News
of higher educational institutions and energy associations of the CIS], 2022, Vol. 65, No. 1, pp. 67-75.
4. Morozov A.V. [i dr.]. Puti sovershenstvovaniya sistemy passivnogo okhlazhdeniya aktivnoy zony
reaktora VVER [Ways to improve the passive cooling system of the VVER reactor core], Mater. XIV
Mezhdunarodnoy nauchno-tekhnicheskoy konferencii «Problemy sovershenstvovaniya toplivnoenergeticheskogo
kompleksa», Saratov, 30 oktyabrya - 1 noyabrya 2018 [Proceedings of the XIV International
Scientific and Technical Conference "Problems of improving the fuel and energy complex",
Saratov, October 30 - November 1, 2018]. Saratov, 2018, pp. 115-120.
5. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants. IAEATECDOC-
1624. Vienna: IAEA, 2009. Mode of access: https://www-pub.iaea.org/MTCD/ Publications/
PDF/te_1624_web.pdf (Date of access: 07.01.2022).
6. Natural circulation in water cooled nuclear power plants: Phenomena, models, and methodology for
system reliability assessments. IAEA-TECDOC-1474. Vienna: IAEA, 2005. Mode of access:
https://www-pub.iaea.org/MTCD/Publications/PDF/TE_1474_web.pdf (Date of access: 05.01.2022).
7. Sierchuła J. Analysis of passive residual heat removal system in AP1000 nuclear power plant, IOP
Conference Series: Earth and Environmental Science, 2019, Vol. 214. Art. ID 012095. Available at:
https://doi.org/10.1088/1755-1315/214/1/012095.
8. Li Feng [et al.]. Design, Experiment, and Commissioning of the Passive Residual Heat Removal System
of hina’s Generation III Nuclear Power PR1000, Science and Technology of Nuclear Installations,
2021, 6 p. Available at: https://doi.org/10.1155/2021/6680400.
9. Dan P.D., Rey D.A. Teplovye truby [Heat pipes], transl. from Engl. by. Yu.A. Zeygarnik. Moscow:
Energiya, 1979, 272 p.
10. Chi S. Teplovye truby: Teoriya i praktika [Heat pipes: Theory and practice][: transl. from Engl. by.
V.Ya. Sidorov. Moscow: Mashinostroenie, 1981, 207 p.
11. Vijayan P.K., Nayak A.K., Kumar N. Chapter 1 - Natural circulation loops - advantages, challenges,
and classification, Single-Phase, Two-Phase and Supercritical Natural Circulation Systems.
Woodhead Publishing, 2019, pp. 1-30. Available at: https://doi.org/10.1016/B978-0-08-102486-
7.00001-9.
12. Sviridenko I.I. [et al.]. Passive Residual Heat Removal System for WWER with the Thermosiphon
Heatexchange Equipment, International Journal of Energy for a Clean Environment, 2015, Vol. 16,
No. 1-4, pp. 209-223. Available at: https://doi.org/10.1615/InterJEnerCleanEnv.2015015683.
13. Sviridenko I.I., Shevelev D.V., Sverdlov V.V. Raschetnye issledovaniya avariynogo teplootvoda VVER
avtonomnoy termosifonnoy SPOT pervogo kontura [Computational studies of the emergency heat sink
of the VVER autonomous thermosiphon SPOT of the first circuit], Tekhnologii obespecheniya
zhiznennogo tsikla yadernykh energeticheskikh ustanovok: Nauch.-tekh. sb. [Technologies for ensuring
the life cycle of nuclear power plants: scientific and technical collection]. Sosnovyy Bor: FGUP
NITI, 2018, Issue 3 (13), pp. 28-41.
14. Sviridenko I.I. Uderzhanie reaktora v podkriticheskom sostoyanii pri zaproektnoy avarii odnovremennym
raskholazhivaniem i dekompressiey pervogo kontura [Keeping the reactor in a subcritical state in case of an
out-of-design accident by simultaneous cooling and decompression of the primary circuit], Izvestiya
vysshikh uchebnykh zavedeniy. Yadernaya energetika [News of higher educational institutions. Nuclear energy],
2019, No. 1, pp. 85-96. Available at: https://doi.org/10.26583/npe.2019.1.08.
15. Instruktsiya po likvidatsii avariy i avariynykh situatsiy na reaktornoy ustanovke energobloka № 5
Zaporozhskoy AES. 05.GT.00.IE.11. OP «Zaporozhskaya AES», 2017 [Instructions for the elimination
of accidents and emergencies at the reactor unit of power unit No. 5 of the Zaporizhia NPP.
05.GT.00.IE.11. OP "Zaporizhia NPP", 2017], 444 p.
16. Vasil'ev,L.L. Teploobmenniki na teplovykh trubakh [Heat exchangers on heat pipes]. Minsk: Nauka i
tekhnika, 1981, 143 p.
17. Bezrodnyy M.K., Pioro I.L., Kostyuk T.O., Fakt K. Protsessy perenosa v dvukhfaznykh
termosifonnykh sistemakh. Teoriya i praktika [Transfer processes in two-phase thermosiphon systems.
Theory and practice], 2005, 704 p.
18. AES «Kudankulam». Klassifikatsiya sistem, oborudovaniya, truboprovodov i elementov teplotekhnicheskoy
chasti. KK.UJA.0.SR.PZ.PR004. Institut «Atomenergoproekt», 2002 [Kudankulam
NPP. Classification of systems, equipment, pipelines and elements of the thermal engineering part.
KK.UJA.0.SR.PZ.PR004. Atomenergoproject Institute, 2002].
19. Blagoveshchenskiy A.Ya. [i dr.]. Kontseptsiya rasshirennogo ispol'zovaniya estestvennoy tsirkulyatsii
teplonositelya pervogo kontura v energoblokakh s VVER-1000 (1200) i perspektivy ee realizatsii [The
concept of expanded use of natural circulation of the primary coolant in power units with VVER-1000
(1200) and prospects for its implementation], Bezopasnost', effektivnost' i ekonomika atomnoy energetiki:
Mater. 8-y Mezhdunar. nauch.-tekhn. konf., Moskva, 23-25 maya 2012 g. [Safety, efficiency and economics
of nuclear energy: Materials of the 8th International Scientific and Technical Conference. Conf.,
Moscow, May 23-25, 2012]. Moscow: Kontsern «Rosenergoatom», 2012, pp. 602-605.
20. Bukin N.V. [i dr.]. Vliyanie passivnykh sistem na protekanie tipichnykh zaproektnykh avariy RU V-392
[The influence of passive systems on the course of typical out-of-design accidents of RU V-392],
Obespechenie bezopasnosti AES s VVER: Mater. 2-y nauch.-tekhn. konf., Podol'sk, 19-23 noyabrya 2001
g. [Ensuring the safety of nuclear power plants with VVER: materials of the 2nd scientific and technical
Conference, Podolsk, November 19-23, 2001]. Available at: http://www.gidropress.podolsk.ru/files/ proceedings/
mntk2001/report1/vpsnptza.pdf (accessed 17 September 2021).
21. Andrushechko S.A. [i dr.]. AES s reaktorom tipa VVER-1000. Ot fizicheskikh osnov ekspluatatsii do
evolyutsii proekta [Nuclear power plant with a VVER-1000 reactor. From the physical foundations of
operation to the evolution of the project]. Moscow: Logos, 2010, 603 p.
