Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

Thermal-Hydraulic Calculations for the New Integral Small Modular Reactor VVER-I With Natural Circulation in Primary Circuit

Not scheduled
20m
Vienna

Vienna

Poster Track 1: Design and Technology Development of SMRs

Speaker

Mark Bedretdinov

Description

Initial constructive development of new small modular pressurized water reactor VVER-I with natural convection in primary circuit has been started in 2022 in JSC «GIDROPRESS». The design of reactor is shown in [1]. VVER-I thermohydrodynamics calculation results which were made using one-dimensional code KORSAR/GP are presented within this work. Code KORSAR/GP [2] is widely used for NPP with VVER reactors safety analysis development.
Results of provided calculations for normal operation mode of integral reactor VVER-I confirm results which were previously obtained using analytical methodology for reactor and steam generator general sizes estimation [3].
Stability of circulation and coolant parameters of primary circuit are confirmed via the calculations. During normal operation the reactor core is cooled by means of natural circulation in non-boiling mode. For basic thermal power of 250 MW and 13.4 m height of reactor vessel temperature in outlet of the core is about 310 ºC, coolant mass flow through the core equals to 820 kg/s and the temperature of overheated steam in the outlet of steam generator is about 300 ºC.
It is shown that the reactor has substantial potential for thermal power increasing right up to 400 MW without significant design changes. With the exception of NuScale reactor, general sizes of which are visibly stand out of the trend maybe because of safety hull application, VVER-I rather good fits worldwide trend of such type reactors development.
1. https://www.atomic-energy.ru/news/2023/02/09/132648.
2. Yu. G. Dragunov, М.А. Bykov, V.А. Vasilenko, Yu.А. Migrov. Experience with introduction and development of the KORSAR computer code for substantiating the safety of NPSs with type VVER reactors / Thermal Engineering. 2006.
3. M.M. Bedretdinov, M.A. Bykov, O.E. Stepanov, R.M. Sledkov. Thermal-Hydraulic Сalculations for the New Project of Small Modular Reactor VVER-I, «XXXIX Siberian thermophysical workshop», 28 – 31.08.2023, Novosibirsk.

Country OR International Organization Russia
Email address olegmpei@ya.ru
Confirm that the work is original and has not been published anywhere else yes

Authors

Presentation materials

Peer reviewing

Paper