WO1993020385A1 - Equipment intended for feeding a heat exchanger - Google Patents

Equipment intended for feeding a heat exchanger Download PDF

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Publication number
WO1993020385A1
WO1993020385A1 PCT/CZ1993/000005 CZ9300005W WO9320385A1 WO 1993020385 A1 WO1993020385 A1 WO 1993020385A1 CZ 9300005 W CZ9300005 W CZ 9300005W WO 9320385 A1 WO9320385 A1 WO 9320385A1
Authority
WO
WIPO (PCT)
Prior art keywords
steam generator
tubes
distribution
tubing
tube bundle
Prior art date
Application number
PCT/CZ1993/000005
Other languages
French (fr)
Inventor
Ivo KUSÁK
Milan Franz
Frantis^¿ek CIKRYT
Ladislav BEDNÁREK
Original Assignee
Vítkovice A.S.
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Vítkovice A.S. filed Critical Vítkovice A.S.
Publication of WO1993020385A1 publication Critical patent/WO1993020385A1/en

Links

Classifications

    • 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
    • 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

Definitions

  • the invention is related to equipment intended for feeding a steam generator connected into the primary and secondary circuit of a nuclear power plant and its convenient desing arrangement within the inside area of the body of the steam generator enables a significant reduction of the total time intended for shutting down the block of the nuclear power plant due to failure of the present feed tubing bz simplification of its fitting into the body of the steam generator while facilitating the visual inspection of the feed tubing contributes to the prevention of the occurance of leakeges of the feed tubing, followed by the undesirable effect of secondary water on the wall of the primary collector thus preventing damage caused to it, which leads to increased durability of this unit and to the increased operation life of this node of the nuclear 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 the 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 tube bundle of heat exchanging tubes of the steam generator are connected to the central distributing feed tubing.
  • the relatively cool feed water washing wall of the inlet primary collector from one entails the occurance of material stress due to non-uniform temperature loading over the circumference of the wall in the point in question thus leading, in the extreme case, to the occurance of cracks in the wall of the primary collector of the steam generator and to the 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 repair very difficult.
  • the mentioned disadvantages are eliminated by the equipment intended for feeding the heat exchanger, particularly the steam generator, with secondary water, consisting of a feed nozzle attached to the top part of the steam generator body and partly of distribution feed water tubes.
  • the substance of the invention is in the inlet of feed water to which a distribution piece is connected from a distribution tubing whose branches are led over the tube bundle of heat exchange tubes of the steam generator 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 tube bundle of steam generator heat exchange tubes. Its substance is also in that the free ends of oulet tubes are each provided with a blending box. Another substance is that at least one feed water flow rectifier is placed under a blending box.
  • An advantage of the equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water is that by location of the feed tubing above the tube bundle of the steam generator an explicit and rapid visual inspection of the steam generator feed system may be performed and the extent of eventual damage caused to this tubing evaluated to thus prevent undesirable leakage of cool feed water into the area close to the inlet primary collector, which is the reason for the occurance of material stress due to non-uniform heat loading over the circumference of the collector wall.
  • Such timely evaluation of the technical condition 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 design solution consideraoly contributes to the enhancement of durability of this unit and to prolonged operation life of this node of the nuclear power plant.
  • Another advantage of the invention is that during repairs of the feed tubing there is no need for 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 further advantage is that the design of the equipment enables its very easy assembly and disassembly leading to the reduction 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 level of continually let in feed water leads to' enhanced circulation of "boiler water” thus providing the required blending of inlet feed water with present boiler water.
  • Fig. 1 a side view of the steam generator body.
  • Fig. 2 is a top view into the steam generator body and
  • Fig. 3 is a side view of the distribution tubing with the system of outlet tubes.
  • the equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water as shown in the construction example consists of a feed water inlet 4_ attached to the wall of the body 2 of the steam generator and an opposite inlet . part 3 of the primary steam generator collector.
  • the inlet 1 of feed water is connected to a U-shaped distribution piece _ ⁇ while this distribution piece 4 is connected to a distribution tubing 5 whose one branch is led out between the inlet part 3 of the primary collector __ and the outlet part 6_ of the steam generator primary collector.
  • the second • branch of the distribution tubing 5 is led around the inlet part 3 of the primary collector while both branches of the distribution tubing 5 are placed on and fixed to a supporting and dilatating structure T_ and run over the tube bundle 8 of steam generator heat exchange tubes. From the direct sections of the distribution tubing 5 a system of outlet tubes 9_ is led out in a reversed J shape into the area between two sections of the tube bundle 8 of heat exchange tubes of the steam generator.
  • outlet tubes _9 are provided with a blending box 10 formed of sideplates 11 ⁇ attached to ends of outlet tubes 9_ and a flow rectifier 12_ inntended 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 invention is in that the inlet (1) of feed water is connected to a distribution piece (4) which is attached to a distribution tubing (5) whose branches run above the tube bundle (8) of steam generator heat exchange tubes and where a system of outlet tubes (9) is led out of the distribution tubing (5) above the tube bundle (8) of heat exchange tubes and/or into the area between the tube bundle (8) of heat exchange tubes of the steam generator.

Description

Equipment intended for feeding a heat exchanger Field of the Invention
The invention is related to equipment intended for feeding a steam generator connected into the primary and secondary circuit of a nuclear power plant and its convenient desing arrangement within the inside area of the body of the steam generator enables a significant reduction of the total time intended for shutting down the block of the nuclear power plant due to failure of the present feed tubing bz simplification of its fitting into the body of the steam generator while facilitating the visual inspection of the feed tubing contributes to the prevention of the occurance of leakeges of the feed tubing, followed by the undesirable effect of secondary water on the wall of the primary collector thus preventing damage caused to it, which leads to increased durability of this unit and to the increased operation life of this node of the nuclear plant.
State of the Art
Presently known are steam generators operated as heat exchagers 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 the 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 tube bundle of heat exchanging tubes of the steam generator are connected to the central distributing feed tubing. The disadvantage of the above arrangement of individual steam generator nodes and particularly its feed system is in the fact that due to the considerable amount of continually let in feed water leakages or eventually cracks occur, due to cavitation and erosion activity of water, in the bottom part of the distribution tubing just in the point of connection of horizontal distribution tubes where the direction and flow rate of feed water is changed. Such untightness is the cause of undesirable leakage of secondary water in close proximity of the inlet primary collector. The relatively cool feed water washing wall of the inlet primary collector from one entails the occurance of material stress due to non-uniform temperature loading over the circumference of the wall in the point in question thus leading, in the extreme case, to the occurance of cracks in the wall of the primary collector of the steam generator and to the 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 repair very difficult.
Summary of the Invention
The mentioned disadvantages are eliminated by the equipment intended for feeding the heat exchanger, particularly the steam generator, with secondary water, consisting of a feed nozzle attached to the top part of the steam generator body and partly of distribution feed water tubes. The substance of the invention is in the inlet of feed water to which a distribution piece is connected from a distribution tubing whose branches are led over the tube bundle of heat exchange tubes of the steam generator 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 tube bundle of steam generator heat exchange tubes. Its substance is also in that the free ends of oulet tubes are each provided with a blending box. Another substance is that at least one feed water flow rectifier is placed under a blending box.
An advantage of the equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water is that by location of the feed tubing above the tube bundle of the steam generator an explicit and rapid visual inspection of the steam generator feed system may be performed and the extent of eventual damage caused to this tubing evaluated to thus prevent undesirable leakage of cool feed water into the area close to the inlet primary collector, which is the reason for the occurance of material stress due to non-uniform heat loading over the circumference of the collector wall. Such timely evaluation of the technical condition 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 design solution consideraoly contributes to the enhancement of durability of this unit and to prolonged operation life of this node of the nuclear power plant. Another advantage of the invention is that during repairs of the feed tubing there is no need for 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 further advantage is that the design of the equipment enables its very easy assembly and disassembly leading to the reduction 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 level of continually let in feed water leads to' enhanced circulation of "boiler water" thus providing the required blending of inlet feed water with present boiler water.
BRIEF DESCRIPTION OF THE DRAWINGS
The enclosed Drawings show the equipment according to the invention where Fig. 1 a side view of the steam generator body. Fig. 2 is a top view into the steam generator body and Fig. 3 is a side view of the distribution tubing with the system of outlet tubes.
DESCRIPTION OF THE PREFERRED EMBODIMENTS
The equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water as shown in the construction example consists of a feed water inlet 4_ attached to the wall of the body 2 of the steam generator and an opposite inlet . part 3 of the primary steam generator collector. The inlet 1 of feed water is connected to a U-shaped distribution piece _^ while this distribution piece 4 is connected to a distribution tubing 5 whose one branch is led out between the inlet part 3 of the primary collector __ and the outlet part 6_ of the steam generator primary collector. The second•branch of the distribution tubing 5 is led around the inlet part 3 of the primary collector while both branches of the distribution tubing 5 are placed on and fixed to a supporting and dilatating structure T_ and run over the tube bundle 8 of steam generator heat exchange tubes. From the direct sections of the distribution tubing 5 a system of outlet tubes 9_ is led out in a reversed J shape into the area between two sections of the tube bundle 8 of heat exchange tubes of the steam generator.
Another alternative of this design is that the free ends of the outlet tubes _9 are provided with a blending box 10 formed of sideplates 11^ attached to ends of outlet tubes 9_ and a flow rectifier 12_ inntended for enhancing the blending of boiler water and feed water.

Claims

Claims
1. Equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water, consisting of a feed nozzle attached to the top part of the steam genarator body and of a distribution tubing and feed water distribution tubes significant by that the inlet /1/of feed water is connected to a distribution piece /4/ attached to the distribution tubing /5/ whose branches are led over the tube bundle /8/ of heat exchange steam generator tubes and where from the distribution tubing /5/ a system of outlet tubes /9/ is led out above the tube bundle /8/ of heat exchange tubes and/or into the space between the tube bundle /8/ of heat exchange tubes.
2. Equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water according to item 1 above, significant by that free ends of butlet tubes /9/ are provided with a blending box /10/.
3. Equipment intended for feeding a heat exchanger, particularly a steam generator, with secondary water according to item 2 above, significant by that at least one flow rectifier /12/ is placed the blending box /10/.
PCT/CZ1993/000005 1992-04-03 1993-03-30 Equipment intended for feeding a heat exchanger WO1993020385A1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CSPV1007-92 1992-04-03
CS921007A CZ280452B6 (en) 1992-04-03 1992-04-03 Device for supplying secondary water to a heat-exchange apparatus, particularly of a stem producer

Publications (1)

Publication Number Publication Date
WO1993020385A1 true WO1993020385A1 (en) 1993-10-14

Family

ID=5343330

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CZ1993/000005 WO1993020385A1 (en) 1992-04-03 1993-03-30 Equipment intended for feeding a heat exchanger

Country Status (3)

Country Link
CZ (2) CZ281U1 (en)
SK (1) SK279470B6 (en)
WO (1) WO1993020385A1 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2696137A1 (en) * 2011-04-07 2014-02-12 Mitsubishi Heavy Industries, Ltd. Water supply pipe for vapor generator
WO2017010906A1 (en) * 2015-07-15 2017-01-19 Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" (Ао "Концерн Росэнергоатом") Steam generator
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

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
EP0161894A2 (en) * 1984-05-14 1985-11-21 Westinghouse Electric Corporation Discharge tube for inhibiting stratification in feedwater headers of a steam generator
EP0309361A1 (en) * 1987-09-25 1989-03-29 Framatome Fluid distributor in a pressurized container preventing thermal stratification
EP0389361A1 (en) * 1989-03-22 1990-09-26 Framatome Preheated steam generator
SU1714290A1 (en) * 1989-05-26 1992-02-23 Всесоюзный Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского Method of operation of horizontal steam generator

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
EP0161894A2 (en) * 1984-05-14 1985-11-21 Westinghouse Electric Corporation Discharge tube for inhibiting stratification in feedwater headers of a steam generator
EP0309361A1 (en) * 1987-09-25 1989-03-29 Framatome Fluid distributor in a pressurized container preventing thermal stratification
EP0389361A1 (en) * 1989-03-22 1990-09-26 Framatome Preheated steam generator
SU1714290A1 (en) * 1989-05-26 1992-02-23 Всесоюзный Теплотехнический Научно-Исследовательский Институт Им.Ф.Э.Дзержинского Method of operation of horizontal steam generator

Non-Patent Citations (4)

* Cited by examiner, † Cited by third party
Title
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 (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2696137A1 (en) * 2011-04-07 2014-02-12 Mitsubishi Heavy Industries, Ltd. Water supply pipe for vapor generator
EP2696137A4 (en) * 2011-04-07 2015-04-01 Mitsubishi Heavy Ind Ltd Water supply pipe for vapor generator
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
WO2017010906A1 (en) * 2015-07-15 2017-01-19 Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" (Ао "Концерн Росэнергоатом") Steam generator

Also Published As

Publication number Publication date
CZ100792A3 (en) 1993-10-13
SK100792A3 (en) 1995-06-07
CZ280452B6 (en) 1996-01-17
SK279470B6 (en) 1998-11-04
CZ281U1 (en) 1993-04-28

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