Liquid metal-cooled nuclear reactor incorporating a completely passive residual power removal (DHR) system
View Patent ↗The invention concerns a liquid metal-cooled fast-neutron nuclear reactor ( 1 ), comprising a system ( 2 ) for removing at least part of both the nominal power and the residual power of the reactor, which ensures, at the same time: removal of the residual power in a totally passive manner from the initial instant of the accident; removal of the heat through the primary vessel; implementation of a final cold source (container with PCM) other than the sodium/air or NaK/air heat exchangers used in the prior art.
1. A liquid metal-cooled fast-neutron nuclear reactor, comprising:
a vessel referred to as the primary vessel, filled with a liquid metal as the heat transfer fluid of the primary circuit of the reactor;
a vessel well arranged around the primary vessel, defining an inter-vessel space;
a top slab for enclosing the liquid metal inside the primary vessel;
a removal system for removing at least part of both the nominal power and the residual power of the reactor, the removal system comprising:
a closed circuit filled with a heat transfer liquid comprising:
an array of a plurality of U-shaped pipes, arranged in the inter-vessel space, being distributed around the primary vessel and each U-shaped pipe extending along the primary vessel with the bottom of the U shapes being adjacent to a bottom of the primary vessel,
a first collector, referred to as the cold collector, connected to one of the branches of the U, referred to as the cold branch, of each of the pipes of the array, the cold collector being arranged on the outside of the primary vessel, above the top slab,
a second collector, referred to as the hot collector, connected to the other branch of the U, referred to as the hot branch, of each of the pipes of the array, the hot collector being arranged on the outside of the primary vessel, above the top slab,
at least one single-pipe heat exchanger, one end of which is connected to the cold collector and the other end of which is connected to the hot collector,
the circuit being configured such that the heat transfer liquid flows inside the circuit by natural convection and remains in the liquid state both during nominal operation of the nuclear reactor and during shutdown operation of the nuclear reactor releasing residual power;
a cold source comprising at least one container arranged at a distance from the primary vessel and above the top slab, the container containing a solid-liquid phase-change material (PCM) into which the single-pipe heat exchanger is inserted, the PCM being capable, during the exchange with the liquid metal of the single-pipe heat exchanger, of being in the solid state during nominal operation of the nuclear reactor and of switching to the liquid state during shutdown operation of the nuclear reactor releasing residual power.
2. The nuclear reactor according to claim 1 , wherein the nuclear reactor has a loop architecture.
3. The nuclear reactor according to claim 1 , comprising a thermal insulation layer for thermally insulating the vessel well, the thermal insulation layer being arranged in such a way as to insulate the cold branch from the hot branch of each of the pipes of the array.
4. The nuclear reactor according to claim 1 , wherein the inter-vessel space is filled with a thermally conductive gas in order to cool the surface of the primary vessel.
5. The nuclear reactor according to claim 1 , wherein the hot and cold collectors each have a toroidal shape centered around the central axis of the primary vessel.
6. The nuclear reactor according to claim 1 , wherein the hot and cold collectors bear against support parts, welded directly to the top slab.
7. The nuclear reactor according to claim 1 , the closed circuit comprising two single-pipe heat exchangers, one end of each single-pipe heat exchanger being connected to the cold collector and the other end of said single-pipe heat exchanger being connected to the hot collector,
the cold source comprising two separate containers arranged at a distance from the primary vessel and above the top slab, each of the containers containing a solid-liquid phase-change material (PCM) into which one of the two single-pipe heat exchanger is inserted, the PCM being capable, during the exchange with the liquid metal of the said single-pipe heat exchanger, of being in the solid state during nominal operation of the nuclear reactor and of switching to the liquid state during shutdown operation of the nuclear reactor releasing residual power.
8. The nuclear reactor according to claim 7 , wherein one of the two single-pipe heat exchangers is connected to an end of the cold collector opposite that to which the other of the two single-pipe heat exchangers is connected.
9. The nuclear reactor according to claim 1 , wherein the single-pipe heat exchanger(s) is a coil type heat exchanger(s).
10. The nuclear reactor according to claim 1 , comprising a circulation loop comprising at least one hydraulic branch connecting the cold collector to the end of the single-pipe heat exchanger and at least one hydraulic branch connecting the hot collector to the end of the single-pipe heat exchanger.
11. The nuclear reactor according to claim 1 , comprising at least one containment building for containing the container(s) of the removal system.
12. The nuclear reactor according to claim 1 , wherein the heat transfer liquid of the circuit is a liquid metal chosen from a lead-bismuth (Pb—Bi) binary alloy, a sodium-potassium (NaK) binary alloy or a ternary alloy of liquid metals.
13. The nuclear reactor according to claim 1 , wherein the PCM filling the container(s) is chosen from lead, cadmium or a mixture of salts made up of 53% KNO3, 40% NaNO2 and 7% NaNO in mass percentages.
14. The nuclear reactor according to claim 1 , wherein the U-shaped pipes of the array and the hot and cold collectors of the circuit are made from a material chosen from stainless steel AISI 316L, ferritic steels, and nickel.