DOI: 10.55176/2414-1038-2021-3-213-226

Authors & Affiliations

Bedretdinov M.M., Stepanov O.E.
Experimental and Design Organization “GIDROPRESS”, Podolsk, Russia

Bedretdinov M.M. – Design Engineer. Contacts: 21 Ordzhonikidze Street, Podolsk, Moscow region, Russia, 142103. Tel.: +7 (905) 579-82-11; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Stepanov O.E. – Head of the Group, Cand. Sci. (Techn.).

Abstract

The results of experiments on boiling off a coolant in the assembly of rods ADELA-2 and ALADIN test facility were considered in the article. During the work, the ADELA-2 and ALADIN test facilities were simulated using the KORSAR/GP and SOCRAT/V1 thermal-hydraulic codes. The effect of the degree of spatial discretization on the calculation results was estimated and it was shown that the results of the calculated data are in acceptably good accordance with the experimental data. The results obtained demonstrate insignificant errors in determining the time of uncovering the rods and reaching the max-imum temperature. The computer code’s results in most cases are more conservative than experimental. The effect of earlier uncovering of less powerful fuel assemblies in ALADIN experiment is detected. It is confirmed by the results of calculations. This effect should be taken into attention when analyzing safety in emergency modes with spent fuel pool heat removal system failure.

Keywords
spent nuclear fuel, spent fuel pool, nuclear power plant, fuel assembly, loss of cooling, KORSAR/GP code, SOCRAT/V1 code

Article Text (PDF, in Russian)

References

UDC 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 3, 3:18