DOI: https://doi.org/10.15588/1607-6761-2018-2-3

HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS

S.V. Alyokhina

Abstract


Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container.

Methodology. Mathematical modeling, numerical solving of the direct and inverse heat transfer problems.

Findings. The distribution of temperatures and heat transfer coefficients on the surfaces of guide tubes inside storage cask with spent fuel assemblies of power reactors WWER-1000 of Zaporizhska NPP are obtained. With usage of the iterative methodology of thermal processes modeling the detailed temperature fields of spent fuel assemblies inside storage cask are obtained. The maximum temperatures in each spent fuel assembly are defined and the places of the most heated fuel rods are identified.

Originality.  For the first time with usage of iterative methodology of thermal processes modeling at the dry spent nuclear fuel storage the detailed information about thermal processes inside storage cask with spent fuela under normal conditions of operations is obtained.

Practical value. The safety of spent nuclear fuel of reactors WWER-1000 in the dry storage facility of Zaporizhska NPP is confirmed. The obtained results are reasonable for usage at development of scientific-methodological basis of safety of the dry storage of spent nuclear fuel of power reactors, and also useful at development and implementation of designs of creation and modernization of equipment for spent nuclear fuel.


Keywords


nuclear energy industry; spent nuclear fuel; ventilated dry storage container; spent fuel assemblies; thermal processes; conjugate heat transfer problems; heat transfer coefficient

References


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GOST Style Citations


[1] Yamakawa, H. Demonstration test for a shipping cask transporting high burn-up spent fuels – thermal test and analyses / H.Yamakawa, M.Wataru, Y.Kouno, T.Saegusa // The 12th International Conference on the Packaging and Transportation of Radioactive Materials, May 10-15, 1998, Paris, France – P. 659-666.

[2] Evaluation of the use of Homogenized Fuel Assemblies in the Thermal Analysis of Spent Fuel Storage Casks / G.R.Thomas, R.W.Carlson – Lawrence Livermore National Laboratory, 1999 – 45 P.

[3] Murakami, J. Li, H. Peak Cladding Temperature in a Spent Fuel Storage or Transportation Cask / J. Li, H. Murakami, Y. Liu, P.E.A. Gomez, M.Gudipati, M.Greiner // The 12th International Conference on the Packaging and Transportation of Radioactive Materials, October 21-26, 2007, Miami, Florida, USA, 1-11 P.

[4] Wataru, M. Thermal Hydraulic Analysis Compared with Tests of Full-scale Concrete Casks /, H.Takeda, K.Shirai, T. Saegusa // Nuclear Engineering and Design. – 2008. –No. 238. –1213-1219 pp.

[5] Suffield, S.R. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI / J.M. Cuta, J.A. Fort, B.A. Collins, H.E. Adkins, E.R. Siciliano // Pacific Northwest National Laboratory – 2012. – 102 Р.

[6] Preliminary Thermal Modeling of HI-STORM 100 S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI / U.S. Department of Energy – 2013. – 59 Р.

[7]  Spent Nuclear Fuel Effective Thermal Conductivity Report – CRWMS M&O, Nevada Site – 1996. – 204 p.

[8] Alyokhina, S. Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors / S. Alyokhina, A. Kostikov // Kerntechnik. – 2014. – Vol. 79, No. 6. – P. 484-487, DOI: 10.3139/124.110443

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[11] Walavalkar, A. Y. 3-D CFD Simulation of a ventilated concrete cask used for spent nuclear fuel storage /  A. Y. Walavalkar, D. G. Schowalter // Proceedings of WM’04 Conference, February 29 – March 4, 2004, Tucson. P. 75-77

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