PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

COMPARISON OF THE CALCULATION PROGRAMS RELAP5/Mod3.4 AND KORSAR (V3.038.002) ON THE EXAMPLE OF A PASSIVE HEAT REMOVAL SYSTEM OF A REACTOR INSTALLATION WITH WWER-1000

EDN: ZFBWZW

Authors & Affiliations

Meniuk D.S.
Sevastopol State University, Sevastopol, Russia

Meniuk D.S. – student. Contacts: 33, st. Universitetskaya, Sevastopol, Russia, 249033. Tel.: +7 (978) 029-18-77; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

Based on the previously created model of a promising passive heat removal system directly from the primary circuit of the WWER-1000 reactors, based on the use of ordinary two-phase thermosiphons (OTPT), which was used for calculations using the RELAP5/Mod3.x software, a completely similar calculation model was built for the KORSAR program. The calculated results of the operation and efficiency of the PHRS RP channel obtained using both models are compared. It is established that, despite the differences in the design parameters within the actual OTPT, the design characteristics of the PHRS RP channel as a whole, obtained using both PS, differ insignificantly. This is explained, in particular, by the damping properties of a closed two-phase intermediate circuit, which performs heat transfer from the condensing section of the OTPT to the heat exchanger – condenser of the intermediate circuit, which, in turn, removes heat to the end sink – atmospheric air or water outside the containment. Nevertheless, the results of the work performed allow us to conclude that a series of experimental studies of heat and mass transfer processes inside the OTPT on the simplest stands, followed by a comparison of experimental data with calculated results obtained using both of the above-mentioned programs.

Keywords
passive heat removal system, reactor plant, spent fuel storage pool, two-phase thermal siphon, thermohydraulic program RELAP5/Mod3.4, water-water power reactor, thermohydraulic program KORSAR (V3.038.002)12

Article Text (PDF, in Russian)

References

UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:16