Decay heat removal for LMFR under accidents

封面

如何引用文章

全文:

开放存取 开放存取
受限制的访问 ##reader.subscriptionAccessGranted##
受限制的访问 订阅存取

详细

Nuclear reactors of “Proryv” project are positioned as the basis for large scale nuclear energetics with inherent safety, which in particular means “eliminating accident at NPP that require evacuation let alone resettlement of population”, which includes cases of multiple malfunctions. The decay heat removal from the reactor core and prevention of the fuel pins overheating is one of first key questions of safety justification problem. On the base of parametric study using engineering thermal-hydraulics code it is shown how to advance efficiency of decay heat removal through modification of reactor upper plenum design.

全文:

受限制的访问

作者简介

V. Rachkov

JSC “PRORYV”

编辑信件的主要联系方式.
Email: rvi@pnproryv.ru
俄罗斯联邦, Moscow

Yu. Khomyakov

JSC “PRORYV”

Email: rvi@pnproryv.ru
俄罗斯联邦, Moscow

Yu. Shvetsov

JSC “PRORYV”

Email: rvi@pnproryv.ru
俄罗斯联邦, Moscow

参考

  1. Rachkov V.I., Adamov E.O., Lopatkin A.V., Pershukov V.A., Troyanov V.M. Fast Reactor Development Program in Russia. Int. conf. on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable scenarios, FR-13. 4–7 March 2013, Paris, France.
  2. Концептуальные положения стратегии развития ядерной энергетики России в перспективе до 2100 г. Адамов Е.О., Джаловян А.В., Лопаткин А.В., Молоканов Н.А., Муравьёв Е.В., Орлов В.В., Калякин С.Г., Рачков В.И., Троянов В.М., Аврорин Е.Н., Иванов В.Б., Алексахин Р.М. – M.: НИКИЭТ, 2012. 61 с.
  3. Рачков В.И. Разработка технологий закрытого ядерного топливного цикла с быстрыми реакторами для крупномасштабной ядерной энергетики // Известия вузов. Ядерная энергетика. 2013. № 3. С. 5–14.
  4. Говердовский А.А., Калякин С.Г., Рачков В.И. Альтернативные стратегии развития ядерной энергетики в XXI в. // Теплоэнергетика. 2014. № 5. C. 3–20.
  5. Shvetsov Iu.E., Ashurko Iu.M., Osipov S.L., Gorbunov V.S. Comparative Analysis of Effectiveness of Various Emergency Core Cooling System Design Options for Sodium Fast Reactors of High Rower. International Conference on FAST REACTORS AND RELATED FUEL CYCLES: Safe Technologies and Sustainable Scenarios. FR13, 4–7 March 2013 Paris, France.
  6. Адамов Е.О., Рачков В.И., Хомяков Ю.С. Швецов Ю.Е. О возможных технических решениях по аварийному отводу остаточного тепловыделения в быстрых реакторах, охлаждаемых жидким металлом. Изв. РАН. Энергетика. 2019, № 2, с. 1–16.
  7. GRIF and HYDRON – 3D Codes for Analysis of Thermal and Hydraulics Parameters or Reactors with 1-Phase Incompressible coolant/ Shvetsov Yu.Е., Volkov A.V. / Report 10-th International Meeting of IAHR Working Group on Advanced Nuclear Reactors Thermal Hydraulics. Obninsk, Russia, 2001, July 17–19.
  8. Кузнецов И.А., Поплавский В.М. Безопасность АЭС с реакторами на быстрых нейтронах. Москва. ИздАТ, 2012 г.
  9. Kuznetsov I.A., Shvetsov Yu.E. Calculation of thermal-hydraulic parameters of fast neutron with account of inter-fuel-assembly space influence / Book of extended synopses Intern meeting FR09, Kyoto, Japan, Dec. 7–11, 2009. IAEA, 2009. CN-176. Р. 483.
  10. Ohira H., Xu Y., Bieder U., Velusamy K., Benchmark H. Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel. International Conference on FAST REACTORS AND RELATED FUEL CYCLES: Safe Technologies and Sustainable Scenarios. FR13, 4–7 March 2013. Paris, France.
  11. Tenchine D., Pialla D., Fanning T.H. International benchmark on the natural convection test in Phenix reactor. Nuclear Engineering and Design, Volume 258, May 2013, P. 189–198.
  12. Аттестационный паспорт программы для электронных вычислительных машин. Программное средство для моделирования теплогидравлических параметров быстрых реакторов с натриевым теплоносителем. Версия 1.0. (GRIF). Рег. № 506 от 14 декабря 2020 г.

补充文件

附件文件
动作
1. JATS XML
2. Fig. 1. Sodium circulation diagram in the reactor in cooldown mode according to the DRACS scheme: 1 – active zone; 2 – intermediate heat exchanger; 3 – 1st circuit circulation pump; 4 – control and protection system column; 5 – emergency heat exchanger.

下载 (232KB)
3. Fig. 2. Vertical (a) and horizontal (b) sections of the reactor calculation region.

下载 (497KB)
4. Fig. 3. Dynamics of the main circulation pump pressure and flow rate in the 1st circuit (a) and the maximum temperature of the fuel element cladding (b) during the transition to the cooldown mode.

下载 (173KB)
5. Fig. 4. Location of the ATO drain chamber.

下载 (661KB)
6. Fig. 5. Dynamics of the maximum fuel element cladding temperature (a) and flow rate in the 1st circuit (b) for different values ​​of the dividing partition height.

下载 (267KB)
7. Fig. 6. Dependence of the relative sodium consumption through the PTO (a) and the total “overturning” consumption through the fuel assembly (b) on the height of the dividing partition.

下载 (144KB)
8. Fig. 7. Lifting GIWS28up and lowering GIWS28d flows through the MPP at the level of the upper end of the “active zone”.

下载 (73KB)
9. Fig. 8. Dependence of the maximum fuel element cladding temperature on the height of the dividing partition.

下载 (85KB)
10. Fig. 9. Dynamics of the maximum fuel cladding temperature for different ESR design options.

下载 (105KB)

版权所有 © Российская академия наук, 2024