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Apr 19 – 22, 2022
Vienna, Austria
Europe/Vienna timezone
FR22 starts in Vienna 19 - 22 April 2022 Online Stream:

The Severe Accident Management of the high-power SFR with loss of the heat removal from the core

Apr 20, 2022, 2:28 PM
Vienna, Austria

Vienna, Austria

ORAL Track 2. Fast Reactor Safety 2.3 Accident Analysis


Ilia Pakhomov


The accident at the Fukushima NPP (Japan) showed that the design of the power unit should consider the unforeseen excess of the external influence intensity. The accidents for internal reasons can be predicted on the basis of knowledge and it depends, first of all, on the designers approach, but it is impossible to foresee catastrophic external influences.
This method is proposed the heat removing for from the vessel by air for a high-power SFR (RVAC). This report proposes to limit heat dissipation - not to exceed the shell temperature of 800 °C in a severe beyond design basis accident such as the accident at the Fukushima NPP.
The air duct composition of the Severe Accident Management (SAMG) proposed method consist of: cold air supply pipes, a hot air heat-insulated exhaust pipe and an air duct around the safety vessel, created by shell with a gap.
Heat transfer to air is carried out due to the transfer of heat by radiation to the safety vessel and shell and due to heat removal from the safety vessel and shell surface to the air in the gap between them, during air circulation through the air path. The thermal balance of the sodium and the vessel are established by intense circulation flows of sodium, which are forced by the core decay heat and the heat outflow to the air. Many-hour processes are considered, so there is no delay in the temperature of structural elements from the sodium.
As a SAMG including the gap between the main and safety vessel to the air cooling system and filling this gap with sodium is considered like option.
It is shown that taking into account heat exchange by radiation provides a safety SAMG regime for the fast reactors with a sodium coolant for removing heat from the reactor vessel through the channels of natural air circulation around the reactor. Even it’s possible to keep the reactor vessel temperature below the limit of 800 °C with heat removal only through the safety vessel - shell channel.

Speaker's title Mr
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Affiliation/Organization IPPE JSC
Country/Int. organization Russian Federation

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