WO1993020386A1 - Feed system of a heat exchanger - Google Patents
Feed system of a heat exchanger Download PDFInfo
- Publication number
- WO1993020386A1 WO1993020386A1 PCT/CZ1993/000006 CZ9300006W WO9320386A1 WO 1993020386 A1 WO1993020386 A1 WO 1993020386A1 CZ 9300006 W CZ9300006 W CZ 9300006W WO 9320386 A1 WO9320386 A1 WO 9320386A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- steam generator
- feed
- distribution
- inlet
- tubing
- Prior art date
Links
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/22—Drums; Headers; Accessories therefor
- F22B37/228—Headers for distributing feedwater into steam generator vessels; Accessories therefor
Definitions
- the invention is related to a steam generator feed system as one of the nodes of the secondary circuit of a nuclear power plant and solves, by its appropriate both shape and design arrangement inside the internal area of the steam generator body partly the assurance of an efficent heat protection of the feed nozzle in transient modes at changes of operation states of the block of the nuclear power plat for reasons of failures of the present feed tubing and partly the enabling of its simple disassembly assembly in the steam generator body while simplification of the visual inspection of the feed tubing leads to the prevention of the occurence of leakages especially in the zone of the primary collector, which leads to the prevention of its damage and to the increased operational life of this unit of the nuclear power plant.
- the steam generator itself is formed of a cigar-shaped body whose inside area contains an inlet primary collector, an outlet primary collector, a supporting system of the tube bundle and the feed tubing itself.
- the feed tubing consists of a feed nozzle connected to the central distributing feed tubing led close along the wall of inlet primary collector below the level of secondary water while in the bottom third of the steam generator two horizontal distributing tubes leading into the areas between the tube bundle of heat exchangeing tubes of the steam generator are connected to the central distributing feed tubing.
- a disadvantage of the above arrangement of individual steam generator nodes and particularly its feed system is in the fact that at starting the block of the nuclear power plant undesirable heating-through of the feed nozzle and its proximity, i.e. the steam generator wall, occurs caused by the let in hot feed water while at shutdown of the feed steam generator undesirable cooling of the nozzle and its proximity occurs, on the other hand.
- the cycle of heating-through and cooling is repeated within the course of starting and stopping operation of the nuclear power plant. This state leads to the occurance of undesirable material stress and to the concentration of material tension, particularty in the zone of the weld connecting the nozzle to the body of the steam generator, thus considerably increasing the failure rate of this part of the feed system and reducing the durability of the entire system.
- Another disadvantage is that, due to the considerable amount of continually in let feed water, in the bottom part of the distribution tubing there occur, in the point of connection of the horizontal distribution tubes where the direction and flow rate of feed water is changed, leakages due to the effects of cavitation and erosion activitty of feed water.
- Such untighthess is the cause of undesirable leakages of relatively cool feed water inlet into the close proximity of the inlet part of the primary collector thus leading to the occurance of material stress of the primary collector due to its nonuniform heat loading bringing about, in the extreme case, the occurance of cracks in the wall of the primary collector of the steam generator and premature shutting down of the entire block of the nuclear power plant.
- Another disadvantage is the unfeasibility of visual inspection of the feed system of the steam generator as its most exposed point, i.e. the point of connection of horizontal distribution tubes to the distribution tubing, located in the bottom third of the body of the steam generator, is surrounded by the tube bundle.
- a further disadvantage is that during repairs of the feed tubing it is necessary to perform demanding technological operations requiring long periods of putting the steam generator out of operation and thus also the block of the nuclear power plant while the present location of the feed tubing into the cramped area of the tube bundle makes its disassembly and eventual repairs very difficult.
- a disadvantage is also the impossibility of checking the clearance between the distribution tubing sleeve and the distribution tubing.- The occurance of additional nondesirable stresses in the dilatating distributon tubing causes the reduction of the clearance.
- the mentioned disadvantages are eliminated by the system intended for feeding the heat exchanger, particularly the steam generator, consisting of a feed nozzle attached to the top part of the steam generator body and partly of feed water distribution tubes.
- the substance of the invention is in the inlet of feed water to which a distribution piece is connected. Shape pieces are connected to the distribution piece such that peak points of shaped pieces are located at least in the horizontal level of the top adge of the inlet part of the intake of feed water, while branches of the distribution tubing run above the tube bundle, and where a system of outlet tubes is extracted from the distribution tubing and led out above the tube bundle of heat exchange tubes and/or in the area between the steam generator heat exchange tubes in the tube bundle. Its substance is also in that free ends of outlet tubes are provided with a blending box. Another substance is in that at least one feed water flow rectifier is placed under a blending box.
- An advantage of the feed system of a heat exchanger, particularly a steam generator is in that due to the design and shape of the distribution piece and of the inlet part of both branches of the feed tubing there is no occurance of heat shocks in the material of the feed nozzle during changes of operational states of the block of the nuclear power plant caused by cyclic repeating of heat and cooling ofmaterial at starting and stopping operation of the nuclear power plant block.
- Another advantage is that by location of the feed system above the tube bundle a rapid and explicit visual inspection of the feed system of the steam generator may be performed for the evaluation of eventual damage caused to the tubing.
- a furtner advantage is that the design of the equipment enables its very easy assembly and disassembly leading to the raduction of fitting time and thus to the total reduction of shut downs of blocks of nuclear power plants; leading out the feed water tubing in the top part of the steam generator body, eventually its leading out closely below the nominal level leads to enhanced circulation of "boiler water” thus providing the required blending of inlet feed water with present "boiler” water.
- a further advantage is that the checking of the clearance between the distribution tubing sleeve and the distribution tubing is enabled thus preventing the occurance of undesirable additional stress.
- Fig. 1 is a front view of the steam generator body
- Fig. 2 is a top view of the steam generator body
- Fig. 3 is a side view of the distribution tubing with the system of outlet tubes
- Fig. 4 is a side view into the inside area of the steam generator in the point of the inlet of feed water to which the distribution piece is connected with the attached shape pieces.
- the feed system of a heat exchanger particularly a steam generator according to the construction example consists of an inlet 1_ of feed water, e.g. a feed nozzle with a connecting piece attached to the wall 2_ of the top half of the steam generator body 3 opposite to the inlet primary steam generator collector.
- the inlet _1_ of feed water is connected to the inlet of a distribution piece 5_ whose two outlets, leading aslant upwards, are connected to shape pieces &_, such as elbows, of the distribution tubing T_ whose one branch is led between the inlet part of the primary collector and the outlet part 8_ of the steam generator primary collector while the second branch is led around the inlet part 4_ of the primary collector and where both branches of the distribution tubing 7 are located and fixed to the supporting and dilatation structure 9 and run above the tube bundle 10 of steam generator heat exchange tubes.
- Nozzle 1 and shape piece 6 are mutually arranged such that the peak point of each of the shape pieces 6 ⁇ is placed at least in the horizontal level of the top edge of the inlet 3. of feed water thus forming a water closure.
- a system of outlet tubes 12, having the form of a reversed J, is led into the intermediate area of the tube bundle ]L£ of steam generator heat exchange tubes from direct sections of ' the distribution tubing 7.
- outlet tubes 12 are provided with a blending box 13 formed partly of sideplates 14 attached to the ends of outlet tubes 12 and partly by a flow rectifier 15 intended for enhancing the blending of boiler water and feed water.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The substance of the design solution is in that the inlet (1) of feed water is connected to a distribution piece (5) which is attached to shape pieces (6) of a distribution tubing (7) while the peak point of shape pieces (6) are situated at least in the horizontal level of the top edge of the inlet part of the inlet (1) of feed water. Branches of a distribution tubing (7) run above the bundle (10) of heat exchange tubes and/or in the intermediate space of the tube bundle (10) of steam generator heat exchange tubes.
Description
Feed system of a heat exchanger Field of the Invention
The invention is related to a steam generator feed system as one of the nodes of the secondary circuit of a nuclear power plant and solves, by its appropriate both shape and design arrangement inside the internal area of the steam generator body partly the assurance of an efficent heat protection of the feed nozzle in transient modes at changes of operation states of the block of the nuclear power plat for reasons of failures of the present feed tubing and partly the enabling of its simple disassembly assembly in the steam generator body while simplification of the visual inspection of the feed tubing leads to the prevention of the occurence of leakages especially in the zone of the primary collector, which leads to the prevention of its damage and to the increased operational life of this unit of the nuclear power plant.
State of the Art
Presently known are steam generators operated as heat exchangers between the first and second circuits of a nuclear power plant. The steam generator itself is formed of a cigar-shaped body whose inside area contains an inlet primary collector, an outlet primary collector, a supporting system of the tube bundle and the feed tubing itself. The feed tubing consists of a feed nozzle connected to the central distributing feed tubing led close along the wall of inlet primary collector below the level of secondary water while in the bottom third of the steam generator two horizontal distributing tubes leading into the areas between the tube bundle of heat exchangeing tubes of the steam generator are connected to the central distributing feed tubing. A disadvantage of the above arrangement of individual steam generator nodes and particularly its feed system is in the fact that at starting the block of the nuclear power plant undesirable heating-through of the feed
nozzle and its proximity, i.e. the steam generator wall, occurs caused by the let in hot feed water while at shutdown of the feed steam generator undesirable cooling of the nozzle and its proximity occurs, on the other hand. The cycle of heating-through and cooling is repeated within the course of starting and stopping operation of the nuclear power plant.This state leads to the occurance of undesirable material stress and to the concentration of material tension, particularty in the zone of the weld connecting the nozzle to the body of the steam generator, thus considerably increasing the failure rate of this part of the feed system and reducing the durability of the entire system. Another disadvantage is that, due to the considerable amount of continually in let feed water, in the bottom part of the distribution tubing there occur, in the point of connection of the horizontal distribution tubes where the direction and flow rate of feed water is changed, leakages due to the effects of cavitation and erosion activitty of feed water. Such untighthess is the cause of undesirable leakages of relatively cool feed water inlet into the close proximity of the inlet part of the primary collector thus leading to the occurance of material stress of the primary collector due to its nonuniform heat loading bringing about, in the extreme case, the occurance of cracks in the wall of the primary collector of the steam generator and premature shutting down of the entire block of the nuclear power plant. Another disadvantage is the unfeasibility of visual inspection of the feed system of the steam generator as its most exposed point, i.e. the point of connection of horizontal distribution tubes to the distribution tubing, located in the bottom third of the body of the steam generator, is surrounded by the tube bundle. A further disadvantage is that during repairs of the feed tubing it is necessary to perform demanding technological operations requiring long periods of putting the steam generator out of operation and thus also the block of the nuclear power plant while the present location of the feed tubing into the cramped area of the tube bundle makes its disassembly and eventual repairs very difficult. A disadvantage is also the impossibility of
checking the clearance between the distribution tubing sleeve and the distribution tubing.- The occurance of additional nondesirable stresses in the dilatating distributon tubing causes the reduction of the clearance.
Summary of the Invention
The mentioned disadvantages are eliminated by the system intended for feeding the heat exchanger, particularly the steam generator, consisting of a feed nozzle attached to the top part of the steam generator body and partly of feed water distribution tubes. The substance of the invention is in the inlet of feed water to which a distribution piece is connected. Shape pieces are connected to the distribution piece such that peak points of shaped pieces are located at least in the horizontal level of the top adge of the inlet part of the intake of feed water, while branches of the distribution tubing run above the tube bundle, and where a system of outlet tubes is extracted from the distribution tubing and led out above the tube bundle of heat exchange tubes and/or in the area between the steam generator heat exchange tubes in the tube bundle. Its substance is also in that free ends of outlet tubes are provided with a blending box. Another substance is in that at least one feed water flow rectifier is placed under a blending box.
An advantage of the feed system of a heat exchanger, particularly a steam generator is in that due to the design and shape of the distribution piece and of the inlet part of both branches of the feed tubing there is no occurance of heat shocks in the material of the feed nozzle during changes of operational states of the block of the nuclear power plant caused by cyclic repeating of heat and cooling ofmaterial at starting and stopping operation of the nuclear power plant block. Another advantage is that by location of the feed system above the tube bundle a rapid and explicit visual inspection of the feed system of the steam generator may be performed for the evaluation of eventual damage caused to the tubing. Detection of eventual damage may lead to the prevention of undesirable leakeges of
relatively cool feed water into the area close to the inlet primary collector which are the reason for the occurance of materal stress of the collector wall due to its non uniform heat loading. Such timely evaluation of the technical state of the feed tubing contributes to the prevention of the occurance of cracks in the wall of the primary collector and thus prevents undesirable failures of the primary circuit of the nuclear power plant into which a steam generator is connected while this desing solution considerably contributes to the anhancement of durability of this unit and to prolonged operation life of this node of the nuclear power plant. Another advantage is that during repairs of the feed system there is no need of the performance of demanding technological operations using special technology normally applied only in the replacement of defective parts of the present equipment in the cramped area inside the tube bundle. A furtner advantage is that the design of the equipment enables its very easy assembly and disassembly leading to the raduction of fitting time and thus to the total reduction of shut downs of blocks of nuclear power plants; leading out the feed water tubing in the top part of the steam generator body, eventually its leading out closely below the nominal level leads to enhanced circulation of "boiler water" thus providing the required blending of inlet feed water with present "boiler" water. A further advantage is that the checking of the clearance between the distribution tubing sleeve and the distribution tubing is enabled thus preventing the occurance of undesirable additional stress.
BRIEF DESCRIPTION OF THE DRAWINGS
The enclosed Drawings show the equipment according to the invention where Fig. 1 is a front view of the steam generator body, Fig. 2 is a top view of the steam generator body, Fig. 3 is a side view of the distribution tubing with the system of outlet tubes and Fig. 4 is a side view into the inside area of the steam generator in the point of the inlet of feed water to which the distribution piece is
connected with the attached shape pieces.
DESCRIPTION OF THE PREFERRED EMBODIMENTS
The feed system of a heat exchanger, particularly a steam generator according to the construction example consists of an inlet 1_ of feed water, e.g. a feed nozzle with a connecting piece attached to the wall 2_ of the top half of the steam generator body 3 opposite to the inlet primary steam generator collector. The inlet _1_ of feed water is connected to the inlet of a distribution piece 5_ whose two outlets, leading aslant upwards, are connected to shape pieces &_, such as elbows, of the distribution tubing T_ whose one branch is led between the inlet part of the primary collector and the outlet part 8_ of the steam generator primary collector while the second branch is led around the inlet part 4_ of the primary collector and where both branches of the distribution tubing 7 are located and fixed to the supporting and dilatation structure 9 and run above the tube bundle 10 of steam generator heat exchange tubes. Nozzle 1 and shape piece 6 are mutually arranged such that the peak point of each of the shape pieces 6^ is placed at least in the horizontal level of the top edge of the inlet 3. of feed water thus forming a water closure. A system of outlet tubes 12, having the form of a reversed J, is led into the intermediate area of the tube bundle ]L£ of steam generator heat exchange tubes from direct sections of ' the distribution tubing 7.
Another alternative of this design solution is that free ends of outlet tubes 12 are provided with a blending box 13 formed partly of sideplates 14 attached to the ends of outlet tubes 12 and partly by a flow rectifier 15 intended for enhancing the blending of boiler water and feed water.
Claims
1. Feed system of a heat exchanger, particularly a steam generator, consisting partly of a feed nozzle attached to the top part of the steam generator body and partly of a distribution tubing and feed water distribution tubes significant by that the inlet 111 of feed water is connected to a distribution piece /5/ attached to the shape pieces /6/ of the distribution tubing 11/ while the peak points of shape pieces /6/ are at least in the horizontal level of the top edge of the inlet part of the inlet /I/ of feed water while the branches of the distribution tubing 111 run above the tube bundle /10/ and where from the distribution tubing HI a system of outlet tubes /12/ is led out above the tube bundle /10/ of head exchange tubes and/or into the space between the tube bundle /10/ of steam generator heat exchange tubes.
2. Feed system of a heat exchanger, particularly a steam generator, according to item 1 above, significant by that free ends of outlet tubes /12/ are provided with a blending box /13/.
3. Feed system of a heat exchanger, particularly a steam generator, according to item-2 above, significant by that at least one flow rectifier /15/ of feed water is placed under the blending box /13/.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CSPV1005-92 | 1992-04-03 | ||
| CS921005A CZ100592A3 (en) | 1992-04-03 | 1992-04-03 | Supply system of a heat-exchange apparatus, particularly of a steam producer |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO1993020386A1 true WO1993020386A1 (en) | 1993-10-14 |
Family
ID=5343307
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/CZ1993/000006 WO1993020386A1 (en) | 1992-04-03 | 1993-03-30 | Feed system of a heat exchanger |
Country Status (2)
| Country | Link |
|---|---|
| CZ (2) | CZ100592A3 (en) |
| WO (1) | WO1993020386A1 (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2471771A (en) * | 2009-07-07 | 2011-01-12 | Dumitru Fetcu | Heat recovery steam generator with heat pipes and distributed water inlet |
| RU2570992C1 (en) * | 2014-12-12 | 2015-12-20 | Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") | Horizontal steam generator for nuclear power plant and method of its assembly |
| FR3022676A1 (en) * | 2014-06-23 | 2015-12-25 | Dcns | NUCLEAR REACTOR STRUCTURE |
| RU2583324C1 (en) * | 2014-12-12 | 2016-05-10 | Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") | Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator |
| RU180906U1 (en) * | 2017-09-18 | 2018-06-29 | Сергей Леонидович Лякишев | Horizontal steam generator housing |
| EP3236148A4 (en) * | 2014-12-12 | 2018-11-21 | Joint Stock Company "Experimental And Design Organisation "Gidropress" Awarded The Order of The Red Banner of Labour And Czsr Order of Labour | Steam generator coolant reservoir and method for manufacturing same |
| EP3321577A4 (en) * | 2015-07-07 | 2019-05-01 | Joint Stock Company "Experimental And Design Organisation "Gidropress" Awarded The Order of The Red Banner of Labour And Czsr Order of Labour | Steam generator |
| WO2020122770A3 (en) * | 2018-12-14 | 2020-08-06 | Российская Федерация от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Inverse steam generator for fast neutron reactor having lead coolant |
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|---|---|---|---|---|
| FR2161592A5 (en) * | 1971-11-17 | 1973-07-06 | Siemens Ag | |
| EP0045034A1 (en) * | 1980-07-21 | 1982-02-03 | Kraftwerk Union Aktiengesellschaft | Device to avoid the formation of fissures on the inner side of feedwater inlet nozzles of a pressure vessel |
| SU1168771A1 (en) * | 1984-01-06 | 1985-07-23 | Южный Филиал Всесоюзного Дважды Ордена Трудового Красного Знамени Теплотехнического Научно-Исследовательского Института Им.Ф.Э.Дзержинского | Steam generator |
| GB2157407A (en) * | 1984-04-09 | 1985-10-23 | Westinghouse Electric Corp | Open channel steam generator feedwater system |
| EP0297968A1 (en) * | 1987-06-30 | 1989-01-04 | Framatome | Steam generator with a feedwater tube with a device for inhibiting thermal stratification |
| SU1714290A1 (en) * | 1989-05-26 | 1992-02-23 | Всесоюзный Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского | Method of operation of horizontal steam generator |
-
1992
- 1992-04-03 CZ CS921005A patent/CZ100592A3/en unknown
- 1992-04-03 CZ CZ1993319U patent/CZ288U1/en unknown
-
1993
- 1993-03-30 WO PCT/CZ1993/000006 patent/WO1993020386A1/en unknown
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2161592A5 (en) * | 1971-11-17 | 1973-07-06 | Siemens Ag | |
| EP0045034A1 (en) * | 1980-07-21 | 1982-02-03 | Kraftwerk Union Aktiengesellschaft | Device to avoid the formation of fissures on the inner side of feedwater inlet nozzles of a pressure vessel |
| SU1168771A1 (en) * | 1984-01-06 | 1985-07-23 | Южный Филиал Всесоюзного Дважды Ордена Трудового Красного Знамени Теплотехнического Научно-Исследовательского Института Им.Ф.Э.Дзержинского | Steam generator |
| GB2157407A (en) * | 1984-04-09 | 1985-10-23 | Westinghouse Electric Corp | Open channel steam generator feedwater system |
| EP0297968A1 (en) * | 1987-06-30 | 1989-01-04 | Framatome | Steam generator with a feedwater tube with a device for inhibiting thermal stratification |
| SU1714290A1 (en) * | 1989-05-26 | 1992-02-23 | Всесоюзный Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского | Method of operation of horizontal steam generator |
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|---|
| KERNENERGIE vol. 16, no. 5, May 1973, BERLIN DD pages 155 - 158 SAUERMANN 'Stehende oder liegende Damperzeuger in Kernkraftwerken mit Druckwasserreaktoren' * |
| KERNENERGIE vol. 18, no. 8, August 1975, BERLIN DD pages 240 - 248 KRIZEK 'Die Entwicklungsrichtungen von Dampferzeugern für Druckwasserreaktoren' * |
| SOVIET PATENTS ABSTRACTS Section Ch, Week 8607, 25 February 1986 Derwent Publications Ltd., London, GB; Class K, AN 86047306/07 & SU,A,1 168 771 (S HEAT TECHN RES IN) 23 July 1985 * |
| SOVIET PATENTS ABSTRACTS Section Ch, Week 9302, 3 March 1993 Derwent Publications Ltd., London, GB; Class K, AN 93016633/02 & SU,A,1 714 290 (KOZLOV) 23 February 1992 * |
Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2471771B (en) * | 2009-07-07 | 2013-12-11 | ECONOTHERM UK Ltd | Heat exchanger |
| GB2471771A (en) * | 2009-07-07 | 2011-01-12 | Dumitru Fetcu | Heat recovery steam generator with heat pipes and distributed water inlet |
| WO2015197611A1 (en) * | 2014-06-23 | 2015-12-30 | Dcns | Nuclear reactor structure |
| FR3022676A1 (en) * | 2014-06-23 | 2015-12-25 | Dcns | NUCLEAR REACTOR STRUCTURE |
| CN107250664A (en) * | 2014-12-12 | 2017-10-13 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Horizontal steam generator for reactor plant |
| RU2583324C1 (en) * | 2014-12-12 | 2016-05-10 | Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") | Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator |
| CN107407480B (en) * | 2014-12-12 | 2019-06-21 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Horizontal steam generator and its assemble method for nuclear power station |
| CN107407480A (en) * | 2014-12-12 | 2017-11-28 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Horizontal steam generator and its assemble method for nuclear power station |
| CN107250664B (en) * | 2014-12-12 | 2019-10-11 | 获劳动红旗勋章和Czsr劳动勋章的水压试验设计院联合股份公司 | Horizontal steam generator for reactor plant |
| EP3236150A4 (en) * | 2014-12-12 | 2018-10-31 | Aktsyonernoe Obshchestvo "Ordena Trudovogo Krasnogo Znameni i Ordena Truda CHSSR Opytnoe Konstructorskoe Byuro "Gidropress" | Horizontal steam generator for a reactor plant |
| EP3236147A4 (en) * | 2014-12-12 | 2018-10-31 | Joint Stock Company "Experimental And Design Organisation "Gidropress" Awarded The Order of The Red Banner of Labour And Czsr Order of Labour | Horizontal steam generator for a nuclear power station and method for assembling same |
| EP3236148A4 (en) * | 2014-12-12 | 2018-11-21 | Joint Stock Company "Experimental And Design Organisation "Gidropress" Awarded The Order of The Red Banner of Labour And Czsr Order of Labour | Steam generator coolant reservoir and method for manufacturing same |
| RU2570992C1 (en) * | 2014-12-12 | 2015-12-20 | Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") | Horizontal steam generator for nuclear power plant and method of its assembly |
| EP3321577A4 (en) * | 2015-07-07 | 2019-05-01 | Joint Stock Company "Experimental And Design Organisation "Gidropress" Awarded The Order of The Red Banner of Labour And Czsr Order of Labour | Steam generator |
| RU180906U1 (en) * | 2017-09-18 | 2018-06-29 | Сергей Леонидович Лякишев | Horizontal steam generator housing |
| WO2020122770A3 (en) * | 2018-12-14 | 2020-08-06 | Российская Федерация от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Inverse steam generator for fast neutron reactor having lead coolant |
| US11802686B2 (en) | 2018-12-14 | 2023-10-31 | State Atomic Energy Corporation “Rosatom” Acts on Behalf of the Russian Federation | Reverse steam generator for a lead-cooled fast reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| CZ288U1 (en) | 1993-04-28 |
| CZ100592A3 (en) | 1993-10-13 |
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