WO1995016879A1 - Commande d'une soupape de suppression de generateur de vapeur - Google Patents

Commande d'une soupape de suppression de generateur de vapeur Download PDF

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Publication number
WO1995016879A1
WO1995016879A1 PCT/SK1994/000005 SK9400005W WO9516879A1 WO 1995016879 A1 WO1995016879 A1 WO 1995016879A1 SK 9400005 W SK9400005 W SK 9400005W WO 9516879 A1 WO9516879 A1 WO 9516879A1
Authority
WO
WIPO (PCT)
Prior art keywords
steam generator
valves
air
shut
pressure
Prior art date
Application number
PCT/SK1994/000005
Other languages
English (en)
Inventor
Jir^¿í NEHN^¿EVSKY^´
Karel BEDNAR^¿ÍK
Josef Faltus
Original Assignee
Vy^´Skumny^´ Ústav Jadrovy^´Ch Elektrární 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 Vy^´Skumny^´ Ústav Jadrovy^´Ch Elektrární A.S. filed Critical Vy^´Skumny^´ Ústav Jadrovy^´Ch Elektrární A.S.
Priority to RU95120602A priority Critical patent/RU2137034C1/ru
Priority to RU95120605/20U priority patent/RU5045U1/ru
Publication of WO1995016879A1 publication Critical patent/WO1995016879A1/fr
Priority to FI950356U priority patent/FIU950356U0/fi
Priority to FI953856A priority patent/FI953856A0/fi
Priority to BG99890A priority patent/BG62343B1/bg

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/42Applications, arrangements, or dispositions of alarm or automatic safety devices
    • F22B37/44Applications, arrangements, or dispositions of alarm or automatic safety devices of safety valves
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Definitions

  • the technical solution deals with the management of accident situations at nuclear power plants with VVER reactors resulting from a loss of coolant through the pressure boundary of reactor coolant system (interfacing LOCA) into steam generator.
  • the ractor coolant system of a such nuclear power plant is not equipped with main isolation valves so that a danger of a widespread contamination of the secondary system of the nuclear power plant and a release of activity into plant environment in case of an interfacing LOCA into steam generator are directly imminent.
  • the hazard of the activity release into environment exists due to a significant operational difficulty how to depressurize the reactor coolant system rapidly and reliably down to the level of the opening pressure ot the relief valves of the affected steam generator, or of the steam dump station to atmosphere.
  • the existing status of the distribution system of the control air to steam generator relief valves at the VVER 440 (V-213) nuclear units is shown in Fig. 1.
  • the loading and lifting control airs that are supplied to the differential piston of the pressurized cilinder _ of the appropriate relief valve, are provided from the distribution system of the sourse pressurized air of 0.6 MPa by means of the control devices RP calibrated to the opening pressure of 5.69 MPa or 5.78 MPa. If the pressure in the instrument impulse line, connected to the protected equipment, increases up to the setpoint ⁇ value of the opening pressure, the loading air is relieved in the control device which results in the loss of pressure above the differential piston of the cylinder with pressurized air, and the relief valve opens.
  • the distribution system is equipped with a venting system of the N2- . 1 type which is designed to connect the control device with the relief valves and to open the individual relief valves in a forced way at a lower opening pressure than is the rated value.
  • the modification of the distribution system of the control air according to Fig. 2 which enables to readjust the opening pressure at a defected steam generator close to the value of the pressure inspection test in the course of coping with an interfacing LOCA into the steam generator at an appropriate time, consists in that the as-built distribution system of the control air is supplemented with the control device RP3-air volume tank 4 with the air storage supply for aproximately 3 hours of the operation of control devices, and with the shut-off valves UV1-UV4 or EV1-EV4.
  • the transition to the increased opening pressure can be performed by a simple manipulation - by opening the valves EV4 or UV4 and by closing the valves EV2,3 or UV 2,3 (remotely, or locally).
  • the impulse pilot valves IPV 1,2,3 open simultaneously when the pressure of 7.37 MPa is reached in the steam generator; the value of the pressure of either the inspection pressure test or the pressure test of relief valve body is this not exceeded in the protected equipment.
  • the new arrangement maintains all existing safety functions. For example, in case of a failure of RP1 or 2 if it will be necessary to close the valves EV1 , UV1 , the impulse pilot valves IPV 1,2,3 are transferred to the direct opening function, i.e., to "spring" at the pressure of 5.69 or 5.78 MPa.Possible operating modes of the impulse pilot valve system and their performance characteristics are summarized in Table 1.
  • the used shut-off valves UV1-UV4 provide a back - up in case of a failure of motor operated valves EV1-EV4.
  • all motor operated valves are provided with a "handle" to enable manual control for changing the position OPEN-CLOSE.
  • provision 13 which limits the number of impulse pilot valves for one control device.
  • the control device RP3 for the control of the opening pressure close to the pressure of the inspection pressure test should be differentiated in color, e.g., by red spray, colored strips, etc.
  • VVER 440 /V-213/ The disadvantages at VVER 440 /V-213/ are the nece ⁇ ssity to modify the distribution system of the control air for steam generator relief valves with the total costs per one main steam line up to the amount of 220 thousand Kc, i.e. 1320 thousands Kc per one reactor unit, and increased costs for maintenance and revision works (once per year) at the control device RP3 including a check of integrity of the shut-off motor operated valves EV1-EV4.
  • IPV 1,2,3 EV1/UV1-0PEN When closed, transition to springs closed - EV2/UV2-0PEN When closed, IPV open pressure in EV3/UV3-OPEN When closed, IPV open steam line EV4/UV4-CL0SED When closed and pressu ⁇ re rises to 5.69 MPa, also IPV 2,3 open
  • IPV 1 open EV1/UV1-0PEN When pressure 5.69 MPa is reached, (5.69 MPa) EV2/UV2-OPEN IPV 1 opens, if the pre ⁇ ssure rises
  • IPV 2,3 open EV3/UV3-OPEN further, IPV 2,3 open at
  • IPV 1,2,3 EV1/UV1-0PEN When pressure of 7.37
  • IPV impulse pilot valves

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Food Preservation Except Freezing, Refrigeration, And Drying (AREA)

Abstract

L'invention permet d'augmenter temporairement la pression d'ouverture des soupapes de surpression d'un générateur de vapeur dans une centrale nucléaire comportant un réacteur VVER 440 /V-213/ dans le cas d'une fuite de réfrigérant du système de réfrigération du réacteur dans le réfrigérateur de vapeur. L'invention est caractérisée par le fait que le système de distribution existant de l'air de régulation des soupapes de surpression SiZ 1508 est complémentarisé par un dispositif de commande de R^¿P3 effectuant le transport et le chargement de l'air à travers de nouvelles soupapes d'arrêt UV4, EV4 vers le système de distribution existant d'air de régulation complémentarisé par les soupapes d'arrêt UV2, EV2, UV3, EV3 dans la section de chargement d'air depuis R^¿P 1,2 et par un réservoir d'emmagasinage d'air depuis le côté alimentation en air et équipé des soupapes d'arrêt UV1, EV1.
PCT/SK1994/000005 1993-12-15 1994-12-14 Commande d'une soupape de suppression de generateur de vapeur WO1995016879A1 (fr)

Priority Applications (5)

Application Number Priority Date Filing Date Title
RU95120602A RU2137034C1 (ru) 1993-12-15 1994-12-14 Средство повышения давления открытия предохранительных клапанов парогенератора
RU95120605/20U RU5045U1 (ru) 1993-12-15 1994-12-14 Средство повышения давления открытия предохранительных клапанов парогенератора
FI950356U FIU950356U0 (fi) 1993-12-15 1995-08-15 Anordning foer oekning av oeppningstrycket i oevertrycksventilrna i en defekt aonggenerator
FI953856A FI953856A0 (fi) 1993-12-15 1995-08-15 Laite viallisen höyrynkehittimen ylipaineventtiilien avautumispaineen lisäämiseksi
BG99890A BG62343B1 (bg) 1993-12-15 1995-08-29 Разпределителна въздушна система за управление на предпазнитеклапани на парогенератор в атомна електроцентрала с реактори типввер-440

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SKPV1428-93 1993-12-15
SK142893 1993-12-15

Publications (1)

Publication Number Publication Date
WO1995016879A1 true WO1995016879A1 (fr) 1995-06-22

Family

ID=20434551

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/SK1994/000005 WO1995016879A1 (fr) 1993-12-15 1994-12-14 Commande d'une soupape de suppression de generateur de vapeur

Country Status (6)

Country Link
BG (1) BG62343B1 (fr)
CZ (1) CZ284623B6 (fr)
FI (2) FIU950356U0 (fr)
HU (1) HU1257U (fr)
RU (2) RU2137034C1 (fr)
WO (1) WO1995016879A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109712733A (zh) * 2018-12-05 2019-05-03 深圳中广核工程设计有限公司 核电站蒸汽大气排放系统的安全级功能控制系统及方法

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110148480B (zh) * 2019-05-28 2021-01-12 中广核研究院有限公司 一种核电二回路系统

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2362046A1 (de) * 1973-12-13 1975-08-21 Kraftwerk Union Ag Einrichtung zur verringerung der rueckwirkung eines bruches der frischdampfleitung eines kernkraftwerkes
DE2430787A1 (de) * 1974-06-26 1976-01-15 Kraftwerk Union Ag Druckwasserreaktor
FR2381964A1 (fr) * 1977-02-28 1978-09-22 Kraftwerk Union Ag Circuit de vapeur perfectionne pour une centrale thermo-electrique, notamment une centrale nucleaire
EP0114519A2 (fr) * 1982-12-24 1984-08-01 BROWN BOVERI REAKTOR GmbH Dispositif de contrôle des fuites entre les circuits primaires et secondaires d'un réacteur à eau sous pression
US4687626A (en) * 1985-01-18 1987-08-18 Tong Long S Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2362046A1 (de) * 1973-12-13 1975-08-21 Kraftwerk Union Ag Einrichtung zur verringerung der rueckwirkung eines bruches der frischdampfleitung eines kernkraftwerkes
DE2430787A1 (de) * 1974-06-26 1976-01-15 Kraftwerk Union Ag Druckwasserreaktor
FR2381964A1 (fr) * 1977-02-28 1978-09-22 Kraftwerk Union Ag Circuit de vapeur perfectionne pour une centrale thermo-electrique, notamment une centrale nucleaire
EP0114519A2 (fr) * 1982-12-24 1984-08-01 BROWN BOVERI REAKTOR GmbH Dispositif de contrôle des fuites entre les circuits primaires et secondaires d'un réacteur à eau sous pression
US4687626A (en) * 1985-01-18 1987-08-18 Tong Long S Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109712733A (zh) * 2018-12-05 2019-05-03 深圳中广核工程设计有限公司 核电站蒸汽大气排放系统的安全级功能控制系统及方法
CN109712733B (zh) * 2018-12-05 2020-11-06 深圳中广核工程设计有限公司 核电站蒸汽大气排放系统的安全级功能控制系统及方法

Also Published As

Publication number Publication date
FI953856A (fi) 1995-08-15
HU1257U (en) 1998-01-28
FIU950356U0 (fi) 1995-08-15
FI953856A0 (fi) 1995-08-15
BG99890A (bg) 1996-04-30
RU5045U1 (ru) 1997-09-16
HU9500205V0 (en) 1995-09-28
RU2137034C1 (ru) 1999-09-10
CZ284623B6 (cs) 1999-01-13
CZ317194A3 (en) 1995-07-12
BG62343B1 (bg) 1999-08-31

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