Thermal energy storage system connected to both a nuclear reactor and a power generator
An integrated energy system includes a nuclear thermal plant situated on a nuclear site. The nuclear thermal plant produces thermal energy that is transported to a thermal energy storage system located outside the nuclear site. The thermal storage system is thermally coupled to a power generation system which is also remote to the nuclear site. By this arrangement, the nuclear thermal plant is isolated and decoupled from the power generation system. The nuclear thermal plant may supply thermal energy upwards of 800° C. or more to be stored at the thermal energy storage system until needed such as for industrial heat, power generation, or other uses. The thermal storage system is source agnostic, and one or more additional thermal energy generators, such as additional nuclear reactors, solar thermal plants, or other thermal energy generators can be coupled to a common thermal storage system and power generation system.
1. A system, comprising:
a sodium cooled fast spectrum nuclear reactor, the nuclear reactor comprising a reactor vessel and a sodium to salt plate heat exchanger within the reactor vessel, the nuclear reactor on a nuclear site and having a first nameplate capacity;
a nuclear site boundary surrounding the nuclear reactor, the nuclear site boundary defined by one or more barriers inhibiting access to the nuclear site;
a thermal energy storage system located outside the nuclear site boundary, the thermal energy storage system in thermal communication with the nuclear reactor and comprising a salt working fluid;
a fluid loop extending between the thermal energy storage system and the sodium to salt plate heat exchanger within the reactor vessel, the fluid loop configured to carry the salt working fluid; and
a power generator in thermal communication with the thermal energy storage system, the power generator situated outside the nuclear site boundary and having a second nameplate capacity, the second nameplate capacity greater than the first nameplate capacity of the nuclear reactor.
2. The system of claim 1 , wherein the thermal energy storage system is in thermal communication with the nuclear reactor by an energy transfer system.
3. The system of claim 2 , wherein the energy transfer system comprises the fluid loop, the fluid loop creating a closed loop between the nuclear reactor and the thermal energy storage system.
4. The system of claim 3 , wherein the fluid loop is in thermal communication with the nuclear reactor by the sodium to salt plate heat exchanger and is in thermal communication with the thermal energy storage system by a second heat exchanger.
5. The system of claim 4 , wherein the fluid loop contains salt as a working fluid.
6. The system of claim 1 , wherein the nuclear site boundary comprises a fence.
7. The system of claim 1 , wherein the thermal energy storage system has a thermal energy storage capacity that is greater than the first nameplate capacity of the nuclear reactor.
8. The system of claim 1 , wherein the power generator is in thermal contact with the thermal energy storage system by an energy delivery system utilizing molten salt as a working fluid.
9. The system of claim 1 , wherein the nuclear reactor is a first nuclear reactor and further comprising a second nuclear reactor in thermal communication with the thermal energy storage system.
10. The system of claim 9 , wherein the second nuclear reactor is located on a second nuclear site within a second nuclear site boundary, and the thermal energy storage system and the power generator are located outside the second nuclear site boundary.
11. The system of claim 1 , further comprising a solar thermal energy system in thermal communication with the thermal energy storage system.
12. The system of claim 1 , further comprising an emergency planning zone around the nuclear reactor, and wherein the thermal energy storage system and the power generator are located outside the emergency planning zone.
13. The system of claim 1 , wherein the nuclear reactor comprises:
a primary sodium coolant loop disposed within the reactor vessel; and wherein
the sodium to salt plate heat exchanger is in thermal communication with the primary sodium coolant loop.
14. The system of claim 13 , wherein the sodium to salt heat exchanger is located within an upper half of the reactor vessel.