Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification

10/23/2015 2015 - #03 Thermal physics and thermal hydraulics

Khafizov R.R. Poplavsky V.M. Rachkov V.I. Sorokin A.P. Ashurko Yu.M. Volkov A.V. Ivanov E.F. Privezentsev V.V.

DOI: https://doi.org/10.26583/npe.2015.3.09

UDC: 621.039.526.034+621.039.546.8:536.26

ULOF accident calculations for sodium fast reactor, carried out using COREMELT code, indicate sodium boiling in the core. The process is accompanied with reactor technological parameters oscillations over a period of several tens of seconds. In this case, it is possible the implementation of sustainable decay heat removal. Since the two-phase model implemented in the code has significant influence on calculations, the model need to be experimentally verified.

Obtained experimental data on coolant flow, pressure, sodium and cladding temperatures and oscillations of parameters for sodium boiling process in a fuel subassembly mockup under natural and forced coolant circulation with sodium plenum and upper axial blanket model.

The results showed possibility of long residual heat removal by means of boiling sodium in case of sodium plenum presence in the experimental model under pins heat fluxes up to 140 kW/m2 in natural circulation conditions and up to 170 kW/m2 in forced circulation.

References

  1. Bagdasarov Yu.E., Kuznetsov I.A. Nonsteady and emergency conditions of fast-reactor operation and their role in safety. Atomic Energy. 1982, v. 52, no. 1, pp. 3-10.
  2. Volkov A.V., Kuznetsov I.A. Usovershenstvovannaja model’ kipenija natrija dlja analizaavarij v bystrom reaktore [The advanced sodium boiling model for the analysis of accidents within fast reactors]. Izvestia vuzov. Yadernaya energetika. 2006, v. 2, pp. 101-111 (in Russian).
  3. Ashurko Yu.M. Andreeva K.A. Bur’evsky I.V. Volkov A.V. Egorov A.V. Kuznetsov I.A. Korobeynikova L.V. Matveev V.I. Solomonova N.V. Khomyakov Yu.S. Tsarapkina A.N. Issledovanie vlijanija natrievogo pustotnogo jeffekta reaktivnosti na bezopasnost’ bystrogo natrievogo reaktora bol’shoj moshhnosti [Investigation of the SVRE influence on the safety of large size sodium fast reactor]. Izvestia vuzov. Yadernaya energetika. 2014, v. 3, pp. 5-13 (in Russian).
  4. Haga K. Loss of flow experiment in a 37 pin bundle LMRBR Fuel assembly. Nuclear Engineering and Design. 1984, v. 82, pp. 305-318.
  5. Yamaguchi K. Flow pattern and dryout under sodium boiling conditions at decay power levels. Nuclear Engineering and Design. 1987, v. 99, no. 3, pp. 247-263.
  6. Huber F., Kaiser A., Mattes K. and Peppler W. Steady state and transient sodium boiling experiments in a 37 pin bundle. Nuclear Engineering and Design. 1987, v. 100, pp. 377-386.
  7. Gnatt P.A., Carbajo J.J., Dearing J.F. Sodium boiling experiments in the THORS Facility. Nuclear Engineering and Design. 1984, v. 82, pp. 241-280.
  8. Seiler J.M. Studies on sodium boiling phenomena in out-of-pile rod bundles for various accidental situations in LMFBR: experiments and interpretations. Nuclear Engineering and Design. 1986, v. 82, pp. 227-239.
  9. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Kolesnik V.P., Martsinyuk S.S., Mal’kov V.L., Sorokin G.A., Rymkevich K.S. An investigation of the heat transfer and stability of liquid-metal coolant boiling in a natural circulation circuit. Atomic Energy. 1999, v. 87. iss. 5, pp. 337-342 (in Russian).
  10. Sorokin A.P., Efanov A.D., Ivanov E.F., Martsiniouk D.Ye., Bogoslovskaya G.P., Rymkevich K.S., Mal’kov V.L.. Raschyotno-eksperimental’nye issledovaniya uslovij ustojchivogo teploobmena pri vozniknovenii kipeniya zhidkogo metalla v rezhime avarijnogo rasholazhivaniya bystrogo reaktora. [Numerical and experimental investigations of stable heat-exchange conditions with liquid metal boiling under fast reactor accident heat removal regime]. Izvestia vuzov. Yadernaya energetika. 1999, no. 2, pp. 59-70 (in Russian).
  11. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Kolesnik V.P., Martsinyuk S.S., Mal’kov V.L., Sorokin G.A., Rymkevich K.S. An investigation of the heat transfer and stability of liquid-metal coolant boiling in a natural circulation circuit. Thermal Engineering. 2003, no. 3, pp. 20-26.
  12. Sorokin G.A., Ninokata X., Endo X., Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Ivanov V.V., Volkov A.D., Zueva I.R. Eksperimental’noe i raschetnoe modelirovanie teploobmena pri kipenii zhidkogo metalla v sisteme parallel’nyh teplovydeljajushhih sborok v rezhime estestvennoj konvekcii [Experimental and numerical modeling of liquid metal boiling heat transfer in a system of parallel fuel subassemblies under conditions of natural convection]. Izvestia vuzov. Yadernaya energetika. 2005, no. 4, pp. 92-106 (in Russian).
  13. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Ivanov V.V., Volkov A.D., Sorokin G.A., Zueva I.R. Heat transfer under natural convection of liquid metal during its boiling in a system of channels. Thermal engineering. 2007, no. 3, pp. 43-51.
  14. Khafizov R.R. Ashurko J.M. Volkov A.V. Ivanov E.F. Privezentsev V.V. Sorokin A.P. Kumskoy V.V. Podgotovka jeksperimental’nogo stenda AR-1 i jeksperimental’noj modeli k provedeniju issledovanij kipenija natrija v modeli TVS v obosnovanie bezopasnosti bystrogo reaktora novogo pokolenija [AR-1 experimental model and facility preparation for the purpose of experimental investigation of sodium boiling in fuel subassembly mockup for new generation fast reactor safety justification]. Izvestia vuzov. Yadernaya energetika. 2014, no. 1, pp. 77-87. (in Russian)
  15. Zeigarnik Yu.A. Litvinov V.D. Kipenie shhelochnyh metallov v kanalah [Alkali metal boiling in channels]. Moscow. Nauka Publ., 1983. (in Russian)
  16. Borishanskij V.M., Kutateladze S.S., Novikov I.I., Fedynskij O.S. Zhidkometallicheskie teplonositeli [Liquid metal coolants]. Moscow. Atomizdat Publ., 1976 (in Russian).

fast reactor liquid metal coolant sodium boiling two-phase flow fuel subassembly mockup experimental investigation sodium void reactivity effect

Link for citing the article: Khafizov R.R., Poplavsky V.M., Rachkov V.I., Sorokin A.P., Ashurko Yu.M., Volkov A.V., Ivanov E.F., Privezentsev V.V. Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification. Izvestiya vuzov. Yadernaya Energetika. 2015, no. 3, pp. 85-96; DOI: https://doi.org/10.26583/npe.2015.3.09 (in Russian).