Patent Number: 
Section: claims

1. A high-temperature nuclear gas-cooled reactor (HTGR) steam generating system, comprising:a plurality of nuclear steam supply systems connected in parallel, wherein each nuclear steam supply system comprises an HTGR connected to a steam generator;a dedicated steam reheater comprising another HTGR separate from the plurality of nuclear steam supply systems;a high-pressure turbine connected to the plurality of nuclear steam supply systems;an intermediate-pressure turbine connected to the high-pressure turbine and the dedicated steam reheater;a low-pressure turbine connected to the intermediate-pressure turbine and a generator;a condenser connected to the low-pressure turbine;a condensate pump connected to the condenser;a low-pressure heater connected to the condenser and the condensate pump;a deaerator connected to the low-pressure heater and the high-pressure turbine;a water supply pump connected to the deaerator; anda high-pressure heater connected to the water supply pump, the plurality of nuclear steam supply systems reactors and corresponding steam generators and the deaerator,wherein the high-pressure turbine, the dedicated steam reheater, the intermediate-pressure turbine, the low-pressure turbine, the condenser, the condensate pump, the low-pressure heater, the deaerator, the water supply pump, the high-pressure heater and the plurality of nuclear steam supply systems are connected in series to form a closed steam loop. 2. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 1, wherein the high-pressure heater is first connected to the dedicated steam reheater which is then connected to the plurality of nuclear steam supply systems. 3. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 2, wherein an outlet of the high-pressure heater is connected to a preliminary heating section of the dedicated steam reheater, and an inlet of the plurality of nuclear steam supply systems is connected to the preliminary heating section of the dedicated steam reheater. 4. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 1, wherein an outlet of the high-pressure turbine is connected to a reheating portion of each steam generator of each of the nuclear steam supply systems. 5. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 1, wherein the high-pressure turbine is connected to the dedicated steam reheater and the intermediate-pressure turbine, and wherein an outlet of the intermediate-pressure turbine is connected to the dedicated steam reheater and the dedicated steam reheater is connected to the low-pressure turbine. 6. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 1wherein each HTGR and steam generator of the plurality of nuclear steam supply systems are separately disposed in a pressure vessel, and further comprising a hot gas duct connected between the pressure vessel of each HTGR and steam generator of the plurality of nuclear steam supply systems and a primary helium circulator provided on an upper part of a shell of each of the corresponding steam generators. 7. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 6, wherein the HTGR has a core designed as a pebble-bed structure, and wherein fuel elements are located in the core. 8. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 6, wherein the HTGR has a fixed arrangement core of prismatic structure, and further comprising fuel elements located inside the core. 9. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 7, wherein the fuel elements comprise full ceramic type coated particle fuel elements. 10. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 6, wherein each of the plurality of steam generators comprise a once-through steam generator having a spiral tube structure. 11. The nuclear high-temperature gas-cooled reactor (HTGR) steam generating system according to claim 6,wherein the hot gas duct comprises a ring structure, in which an outer ring comprises a cold helium flow channel for helium flowing from the steam generator to the HTGR for each of the plurality of HTGRs corresponding steam generators, and an inner ring comprises a hot helium flow channel for helium flowing from the HTGR to the steam generator for each of the plurality of HTGRs and corresponding steam generators. 12. A method for nuclear high-temperature gas-cooled reactor (HTGR) steam generation, comprising:generating steam by a plurality of nuclear steam supply systems connected in parallel, wherein each nuclear steam supply system comprises: an HTGR and a steam generator;driving a high-pressure turbine with steam from the plurality of nuclear steam supply systems;utilizing a dedicated steam reheater comprising another HTGR separate from the plurality of nuclear steam supply systems;utilizing an intermediate-pressure turbine connected to the dedicated steam reheater and the high-pressure turbine;driving a low-pressure turbine connected to the high pressure intermediate-pressure turbine;utilizing a condenser connected to the low-pressure turbine;utilizing a condensate pump connected to the condenser;utilizing a low-pressure heater connected to the condenser and the condensate pump;utilizing a deaerator connected to the low-pressure heater;utilizing a water supply pump connected to the deaerator; andutilizing a high-pressure heater connected to the water supply pump, the plurality of nuclear steam supply systems and the deaerator,wherein the high-pressure turbine, the dedicated steam reheater, the intermediate-pressure turbine, the low-pressure turbine, the condenser, the condensate pump, the low-pressure heater, the deaerator, the water supply pump, the high-pressure heater and each of the plurality of nuclear steam supply systems are connected to form a closed steam loop;driving a generator with the low-pressure turbine; andfeeding steam from the low-pressure turbine to the condenser for heat release, then to the low-pressure heater, the deaerator, the water supply pump and the high-pressure heater, to complete a thermodynamic cycle. 13. The method according to claim 12, further comprising feeding steam flowing out of the high-pressure turbine to the dedicated steam reheater to reheat the steam, and then feeding the steam to the intermediate-pressure turbine and the low-pressure turbine. 14. The method according to claim 13, further comprising feeding wet steam from the low-pressure turbine to a preliminary section of the dedicated steam reheater. 15. The method according to claim 12, further comprising feeding the steam flowing out of the high-pressure turbine to a reheating portion of dedicated steam reheater to reheat the steam. 16. The method according to claim 12, further comprising feeding a part of the steam flowing out of the high-pressure turbine to the dedicated steam reheater to directly heat the steam, and feeding another part of the steam flowing out of the high-pressure turbine to the intermediate-pressure turbine, the steam exiting the intermediate-pressure turbine being heated by the dedicated steam reheater, with the steam heated directly as well as the steam is fed into the low-pressure turbine.