Abstract
The current paper describes the loss of flow (LOF) transient investigated in the MYRRHA reactor by the
means of Computational Fluid Dynamics. This scenario is starting from the nominal operation case then
the two pumps stop simultaneously. An unsteady solution with resolved interface was considered with
calculating conjugate heat transfer through the relevant structures (with the myrrhaFOAM, OpenFOAM
based flow solver [6]).
Due to a postulated event (e.g. loss of the electric grid) the pumps are not powered anymore stops. After
the detection of the problem (temperature difference above the core rises with 20 degree) the reactor
power is stopped by the safety rods (delay of 1 second). The fuel elements, however, continue to generate
residual heat according to the decay heat curve. Due to the loss of the pumps, the pressure difference
between the cold and the hot plenum is decreasing, which result in a gravitational flow equilibrating the
two free surfaces to the same level. The objective of the work was to determine the flow through the core
during the coast down of the pumps and eventual flow reversal into the pump/heat-exchanger box due to
the gravitational flow.
The simulation revealed that after losing power, the LBE flow reverses into the pumps in less than 0.1
seconds according to the simulations. In the core there is a brief moment of reverse flow, too, but only
after the core is scrammed, therefore, the loss of cold LBE flow is not causing overheat. Once the core is
scrammed, the position of the maximum temperature in the system shifts to the Above Core Structure,
where the residual hot plume rising from the core impinges to the Above Core Upper Closure. The levels
of the lower and upper plenum equilibrate roughly 20 seconds after the pump failure event.
Original language | English |
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Title of host publication | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) |
Publisher | American Nuclear Society |
Pages | 1-14 |
Number of pages | 14 |
State | Published - 18 Aug 2019 |
Event | 2019 - NURETH: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Portland Marriott Downtown Waterfront, Portland Duration: 18 Aug 2019 → 23 Aug 2019 http://epsr.ans.org/meeting/?m=285 |
Conference
Conference | 2019 - NURETH |
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Abbreviated title | NURETH18 |
Country/Territory | United States |
City | Portland |
Period | 2019-08-18 → 2019-08-23 |
Internet address |