Steam cooled nuclear reactor
阅读：55发布：2022-12-16
专利汇可以提供Steam cooled nuclear reactor专利检索，专利查询，专利分析的服务。并且A nuclear reactor pressure vessel internals arrangement including a core assembly, control means and steam flow directing means is disclosed. The reactor utilizes a two-pass steam flow scheme in which steam flows downwardly through non-fueled core components and then flows upwardly through the fuel assemblies. The reactor internals are located within a shroud which forms a second pressure-tight vessel. Water located in an annular space between the internal shroud and the main pressure vessel provides additional shielding and is readily available for core flooding. The arrangement provides improved safety, simplicity and reliability in steam cooled reactor operation.，下面是Steam cooled nuclear reactor专利的具体信息内容。
1. An electrical power generating system including a steam cooled nuclear reactor producing superheated steam; means to pass a fixed portion of said superheated steam to steam utilization means; means to pass a second portion of said superheated steam to at least one contact boiler; at least one turbine drive pump means to pump condensate from said utilization means to said contact boiler wherein said condensate is evaporated and said second portion of said superheated steam is desuperheated, producing a large quantity of substantially saturated steam; and at least one turbine driven steam circulator to pump said saturated steam back to said reactor for resuperheating; said reactor comprising a core comprising a plurality of fuel assemblies containing fissile fuel, and a plurality of control assemblies containing neutron absorption material interspersed among said fuel assemblies, an inlet plenum located at one end of said core to receive steam from said steam circulator, means directing said steam through said control assemblies from said inlet plenum to an intermediate steam plenum at the other end of said core, and means directing said steam from said intermediate plenum through said fuel assemblies to an outlet plenum whereby said steam is superheated.
2. The reactor of claim 1 wherein said means directing said steam from said intermediate plenum to said outlet plenum includes a plurality of tubular members passing through said inlet plenum and connecting each fuel assembly with said outlet plenum in fluid flow relationship.
3. The reactor of claim 1 wherein said outlet plenum is divided into a plurality of segments, each segment receiving superheated steam from a portion of said fuel assemblies and each segment including an individual means permitting said superheated steam to leave said reactor.
4. The reactor of claim 1 wherein said core comprises a substantially right cylindrical array of closely packed hexagonal assemblies, with fuel assemblies and control assemblies adjacent the core axis surrounded by a ring-shaped array of reflector and reflector-control assemblies; the outermost ring of reflector assemblies including clamping means adapted to tightly clamp said assemblies together.
5. The reactor according to claim 1 further including an independent saturated steam inlet line and an independent superheated steam outlet line connected in fluid flow relationship to a single fuel assembly whereby said lines and fuel assembly constitute an isolated test loop.
6. The reactor of claim 1 wherein said control assemblies include neutron poison material containing portions adapted to be moved between a position within the active fuel region to a position above said active fuel region and drive means located below said reactor to move said portions between said positions; whereby hydraulic forces resulting from steam passing through said control assemblies between said inlet plenum and said intermediate plenum tend to move said portions into said active fuel region.
7. The reactor of claim 1 wherein said core, said inlet plenum, said intermediate plenum and said outlet plenum are contained within a pressure tight shroud surrounded by a shield water space within a reactor pressure vessel.
8. The reactor according to claim 7 further including a flooding water plenum located adjacent said intermediate plenum within said shroud, valve means adapted to admit water from said shield water space to said flooding water plenum, and a plurality of nozzles positioned to direct flooding water from said flooding water plenum directly into each fuel assembly.
9. In a nuclear power generating system comprising a nuclear reactor producing superheated steam, a main turbine drIven by a first portion of said steam, a main condenser for condensing exhaust from said main turbine; a turbine driven pump to pump condensate from said main condenser through a series of feedwater heaters to a contact boiler; a contact boiler to bring a second portion of said superheated steam into contact with said condensate whereby said condensate evaporates while desuperheating said second portion of superheated steam producing a large quantity of substantially saturated steam and turbine driven steam circulating means for pumping said saturated steam to said reactor; the improvement wherein said reactor comprises a core comprising a plurality of fuel assemblies containing fissile fuel, and a plurality of control assemblies containing neutron absorbing material interspersed among said fuel assemblies; an inlet plenum located immediately above said core to receive steam from said steam circulator; means permitting steam to pass downwardly through said control assemblies from said inlet plenum to an intermediate steam plenum immediately below said core; means permitting steam to pass upwardly from said intermediate plenum to an outlet plenum located above said inlet plenum, through said fuel assemblies whereby said steam is superheated.
10. The reactor of claim 9 wherein said means permitting steam to pass upwardly from said intermediate plenum to said outlet plenum includes a plurality of tubular members passing through said inlet plenum and connecting each fuel assembly with said outlet plenum in fluid flow relationship.
11. The reactor of claim 9 wherein said outlet plenum is divided into a plurality of sgements, each segment receiving superheated steam from a portion of said fuel assemblies and each segment including an individual means permitting said superheated steam to leave said reactor.
12. The reactor of claim 9 wherein said core comprises a substantially right cylindrical array of closely packed hexagonal assemblies, with fuel assemblies and control assemblies adjacent the core axis surrounded by a ring-shaped array of reflector and reflector-control assemblies; the outermost ring of reflector assemblies including clamping means adapted to tightly clamp said assemblies together.
13. The reactor according to claim 9 further including an independent saturated steam inlet line and an independent superheated steam outlet line connected in fluid flow relationship to a single fuel assembly whereby said lines and fuel assembly constitute an isolated test loop.
14. The reactor of claim 9 wherein said control assemblies include neutron poison material containing portions, adapted to be moved between a position within the active fuel region to a position above said active fuel region, and drive means located below said reactor to move said portions between said positions; whereby hydraulic forces resulting from steam passing through said control assemblies between said inlet plenum and said intermediate plenum tend to move said portions into said active fuel region.
15. The reactor of claim 9 wherein said core, said inlet plenum, said intermediate plenum and said outlet plenum are contained within a pressure tight shroud surrounded by a shield water space within a reactor pressure vessel.
16. The reactor according to claim 15 further including a flooding water plenum located adjacent said intermediate plenum within said shroud, valve means adapted to admit water from said shield water space to said flooding water plenum, and a plurality of nozzles positioned to direct flooding water from said flooding water plenum directly into each fuel assembly.
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