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WO2003063177A1 - Systeme pour injecter directement dans la cuve de l'eau de refroidissement d'urgence du coeur au moyen d'un tuyau d'injection vertical, agitateur, tuyau d'injection interne torsade et tuyau d'injection incline - Google Patents

Systeme pour injecter directement dans la cuve de l'eau de refroidissement d'urgence du coeur au moyen d'un tuyau d'injection vertical, agitateur, tuyau d'injection interne torsade et tuyau d'injection incline Download PDF

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Publication number
WO2003063177A1
WO2003063177A1 PCT/KR2003/000161 KR0300161W WO03063177A1 WO 2003063177 A1 WO2003063177 A1 WO 2003063177A1 KR 0300161 W KR0300161 W KR 0300161W WO 03063177 A1 WO03063177 A1 WO 03063177A1
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WO
WIPO (PCT)
Prior art keywords
cooling water
reactor
injection
emergency
injection pipe
Prior art date
Application number
PCT/KR2003/000161
Other languages
English (en)
Inventor
Kune-Yull Suh
Sang-Hyuk Yoon
Original Assignee
Philosophia, Inc.
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 Philosophia, Inc. filed Critical Philosophia, Inc.
Publication of WO2003063177A1 publication Critical patent/WO2003063177A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a direct vessel injection (DVI) system of a nuclear reactor for injecting emergency core cooling water using a vertical injection pipe, a sparger, spiral threads at the inner surface of an injection pipe, an inclined pipe, and a safety injection pipe installed at the upper head of the reactor, and more particularly to a system for injecting the emergency core cooling water into the reactor vessel downcomer utilizing a horizontal safety injection pipe with a vertically downward elbowed tip, a sparger, an injection pipe spirally threaded on the inner surface, an injection pipe connected vertically at the upper head of a nuclear reactor, rather than on the side thereof, for the purpose of enhancing the emergency core coolant penetration capability into the core, or an injection pipe installed at an angle to the reactor vessel wall to allow for the cooling water to flow into the downcomer at a predetermined angle, in a pressurized water reactor (PWR), a boiling water reactor (BWR) or an advanced reactor using a DVI system for which the emergency core cooling water is injected through the safety injection pipe installed separately from a
  • Nuclear reactors resort on reactions within the atomic nuclei to produce energy.
  • a PWR that uses light water as the coolant that acts as a medium for transporting the thermal energy generated by the nuclear reaction within nuclear fuel
  • the pressure inside the reactor is maintained high enough to prevent the coolant from boiling in the reactor vessel, while in a BWR the coolant is allowed to boil in the reactor vessel to produce steam directly.
  • LOCA loss-of-coolant accident
  • ESFs Engineered Safety Features
  • the cold leg injection (CLI) or DVI is applied for injecting emergency cooling water into the core of the nuclear reactor utilizing a safety injection system for the reactor.
  • the safety injection trains are used for injecting the emergency cooling water through a cold leg by connecting the safety injection nozzles to each of the cold legs.
  • the safety injection system consists of two safety injection trains, onto each of which a high-pressure safety injection (HPSI) pump and a low-pressure safety injection (LPSI) pump are arranged, so that the emergency core cooling water can be injected through the remaining unbroken cold legs even if one of the cold legs is broken or one of the two safety injection trains fails.
  • the safety injection system is designed as a mechanical four-safety injection train system, the safety in a nuclear power plant is significantly improved as compared with a two-safety injection train system.
  • the safety injection system is designed as a four-safety injection train system and if the cold leg injection is applied, the number of HPSI and LPSI pumps required is four, respectively, in order to supply the sufficient amount of coolant required for the emergency core cooling.
  • the DVI is adopted in this case, it is possible to design the system with pumps of a smaller capacity than the conventional safety injection capacity for an accident in which the cold legs are broken.
  • the emergency cooling water that must flow into the reactor core through the safety injection nozzles may flow out of the break prior to reaching the downcomer. That is, since the emergency cooling water flowing in through the safety injection nozzles is mixed with the coolant that flows backward through the cold legs due to a pressure differential between the reactor core and the break and thus flows out through the break in the cold legs together with the coolant, the emergency cooling water cannot flood the core.
  • a method has been proposed to connect the safety injection pipes directly to a nuclear reactor vessel to allow for the emergency core cooling water to flow directly into the reactor vessel, so that the emergency cooling water does not flow out of the primary system through the break in the cold legs. Therefore, the emergency cooling water has a higher potential to submerge the core.
  • the safety injection pipes are connected directly to the reactor vessel to allow for the emergency core cooling water to be injected directly into the vessel in the DVI method.
  • the ECCS is designed with the DVI utilizing a four-safety injection train system.
  • the U.S. Electric Power Research Institute (EPRI) recommended designing the safety injection in an emergency core cooling system with direct injection into a downcomer in the reactor vessel, rather than the conventional CLI in the Advanced Light Water Reactor Utility Requirements Document (ALWR URD).
  • the DVI was employed for injecting the emergency core cooling water when designing the APR1400 (Advanced Power Reactor 1400MWe) in Korea.
  • the emergency cooling water may bypass through the break even in the aforementioned DVI system.
  • the safety injection pipes are situated higher than the cold legs, a considerable amount of the emergency cooling water injected through the safety injection pipes may bypass through the break in the cold legs together with the coolant which flows backward into the cold leg, while flowing down along the internal wall of the reactor vessel when the cold leg, which is an inlet pipe for the coolant, is broken.
  • the safety injection pipes are positioned lower than the cold leg, however, the emergency cooling water at a low temperature injected through the safety injection pipes suddenly strikes onto the reactor vessel at a high temperature and high pressure, causing a pressurized thermal shock (PTS) so that the reactor vessel 1 may be damaged.
  • PTS pressurized thermal shock
  • Method of Injection to or near Core Inlet discloses a method to install a cylindrical or tubular safety injection channel from the safety injection pipe above the cold leg to the bottom of the core support inside the vessel to maximize the effect of the safety injection.
  • the Korean Patent publication No. 10-0319068 titled "Safety Injection Train in Reactor for Blocking Siphon Effect and Contact with Steam Flow", discloses a direct injection nozzle positioned at a higher location than a cold leg of the nuclear reactor and connected to the reactor with a gap, wherein the direct injection nozzle has a safety injection pipe to allow for the emergency cooling water from the injection nozzle to bypass the reactor inlet nozzle and to be injected into the lower plenum of the reactor vessel, so as to minimize the amount of emergency cooling water flowing out through the cold leg, to block the siphon effect by which the coolant continues to flow out through the safety injection pipe and to prevent contact with steam flow, which happens when the cold leg that is an inlet pipe of coolant is broken.
  • NSS nuclear steam supply system
  • DVVI Direct Vessel Vertical Injection
  • the reactor comprises an emergency core cooling water injection system.
  • This system allows for the cooling water entering through the safety injection pipe to flow into the core in a vertical direction by attaching a vertical pipe to the safety injection pipe horizontal with a reactor vessel or installing a sparger, or allows the injected cooling water to flow into the core with less steam resistance by providing spiral threads in the injection pipe, and an emergency core cooling water system in which the safety injection pipe is installed at an angle to the wall of the reactor vessel to allow for the cooling water to flow into the core at a predetermined angle or to maximize the vertical momentum of the injected water by installing the safety injection pipe at the upper head of the reactor, for efficient injection of the emergency cooling water.
  • Fig. 1 is a schematic view of an embodiment of a direct vessel vertical injection (DWI) of a nuclear reactor according to the present invention
  • Fig. 2 is a sectional view of a DVVI for APR1400;
  • Fig. 3 is a schematic diagram of an embodiment of cold leg injection (CLI) and DVI;
  • Fig. 4 is a schematic view of an embodiment of a DVVI using a protection disk, where Fig. 4a shows the protection disk installed in the reactor downcomer, and Fig. 4b is a partially enlarged three-dimensional view illustrating the conical disk as an embodiment of the protection disk;
  • Fig. 5 shows DVVI using a sparger according to an embodiment of the invention, where Fig.5(a) is a bottom perspective view of the sparger installed in the nuclear reactor, Fig.5(b) is a top perspective view of the sparger installed in the reactor and Fig. 5(c) is a schematic sectional view of the sparger;
  • Fig. 6(a) is a sectional view of an embodiment of an inclined DVI
  • Fig. 6(b) is a sectional view of an embodiment of a horizontal DVI to compare against the inclined DVI in Fig. 6(a)
  • Fig. 7 is a perspective view illustrating the spirally threaded injection pipe for injecting the emergency cooling water
  • Fig. 8 is a top view showing an emergency core cooling water injection pipe (DVI pipe) according to one embodiment of the invention installed at the upper head of a nuclear reactor;
  • Figs. 9(a) and 9(b) are perspective views of a downcomer using the CFX code for a multidimensional flow analysis of (a) horizontal injection and (b) vertical injection for the direct vessel injection according to one embodiment of the invention;
  • Fig. 10 compares the downward velocity distributions between (a) the horizontal injection and (b) the vertical injection predicted by the CFX multidimensional flow analysis code according to the downcomer models illustrated in Figs. 9(a) and 9(b), respectively;
  • Fig. 11 shows distributions of the iso-velocities by the horizontal injection and the vertical injection through the multidimensional flow test
  • Fig. 12 shows a schematic diagram for the arrangement of downcomer nozzles used for the multidimensional flow analysis
  • Fig. 13 compares the velocity distributions depending on the height from a safety injection pipe by DVI and DVVI when the emergency core cooling water is injected through each nozzle of Fig. 12;
  • Fig.14 compares the velocity distributions by (a) the horizontal injection and (b) the vertical injection integrated from the graphs of Fig. 13.
  • Fig. 1 shows a system for injecting the emergency core cooling water, in which a vertical pipe 6 is attached to a safety injection pipe 4 horizontal with a reactor vessel to allow for the cooling water injected through the safety injection pipe 4 to flow into the reactor downcomer in a vertical direction, in a PWR, a BWR or an advanced reactor 1 with direct injection of the emergency core cooling water in which the emergency cooling water is injected through the safety injection pipe 4 installed separately from a cold leg 2.
  • the safety injection pipe 4 is located above the cold leg 2.
  • the location is selected so as to prevent the cooling water from flowing out through the safety injection pipe when the safety injection pipe is broken in case where the safety injection pipe 4 is located lower than the cold leg 2, as aforementioned in the prior art.
  • the reactor vessel of the present system employs the same structure as the conventional horizontal DVI system outside the reactor but has a further structure for vertical injection unlike the structure for the horizontal injection inside the reactor.
  • Such a vertical pipe 6 has almost the same diameter as that of the safety injection pipe 4 and the lower end of the vertical pipe 6 is located above the upper end of the cold leg 2.
  • the vertical pipe 6 Since the vertical pipe 6 has almost the same diameter as that of the safety injection pipe 4, the horizontal momentum of the injected emergency cooling water gets transformed to the vertical momentum without loss at the vertical pipe 6, so that the emergency cooling water can easily penetrate the downcomer. If the diameter of the vertical pipe 6 is smaller than that of the safety injection pipe 4 or the width of the downcomer, the cooling water may flow out by the siphon effect through the vertical pipe 6. To prevent such outflow, the diameter of the vertical pipe 6 is designed to take almost the same value as that of the safety injection pipe 4. The length of the vertical pipe 6 may vary within the range that the lower end of the vertical pipe 6 does not extend lower than the top of the cold leg 2.
  • the cooling water flows into the reactor at a location overly proximate to the core, thereby possibly causing a pressurized thermal shock (PTS).
  • PTS pressurized thermal shock
  • the safety injection pipe 4 When the safety injection pipe 4 is broken, the cooling water flows out through the safety injection pipe 4 that must supply the cooling water, until the level of the cooling water in the reactor vessel recedes below the lower portion of the vertical pipe 6, and even the cooling water which flows in through the cold leg 2 may also flow out through the safety injection pipe. Since more cooling water thereby flows out, the cooling water is depleted to the extent proper cooling of the heated reactor core is jeopardized.
  • Fig. 2 is a schematic view for vertical injection of the emergency cooling water into the APR1400 vessel, which is an example of a nuclear reactor according to the invention that illustrates the shape and dimensions of the entire reactor to show the installation height of a safety injection pipe to which a vertical pipe is attached.
  • Fig. 3 is a schematic diagram of an embodiment for illustrating the cold leg injection and the direct vessel injection, and shows a safety injection pipe 4 for the direct injection and the safety injection trains 3 connected to cold leg 2 according to the prior art.
  • Fig. 4 shows a schematic diagram of an embodiment for a direct vessel vertical injection (DVVI), using a protection disk. More specifically, Fig. 4(a) shows a diagram of a nuclear reactor in which the protection disk is installed, and Fig.
  • FIG. 4(b) shows a partially enlarged diagram illustrating the attached conical disk that is an embodiment of the protection disk.
  • the protection disk 7 is attached to the inlet of the vertical pipe 6 to minimize steam resistance and maximize the inflow of cooling water into the reactor core.
  • the disk 7 is installed at the inlet of the vertical pipe 6 to minimize resistance by upcoming steam and maximize penetration of the emergency cooling water into the core, since a considerable amount of steam may be generated from the overheated core which is not being properly cooled, and the steam in turn acts against injection of the emergency core cooling water into the core when a LOCA occurs.
  • Fig. 4(b) shows an embodiment of such a conical protection disk which is fixed at the inlet of the vertical pipe 6 using three supporting bars. Use of such a conical disk minimizes resistance by the upcoming steam to the flow of the injected cooling water into a downcomer.
  • Figs. 5(a) through 5(c) show diagrams illustrating the vertical injection using a sparger 10 according to one embodiment of the invention.
  • Fig. 5(a) is a bottom perspective view of the sparger 10 installed in the reactor.
  • Fig. 5(b) is a top perspective of the sparger 10 installed in the reactor.
  • Fig. 5(c) shows schematically the cross section of the sparger 10.
  • Figs. 5(a) and 5(b) show an embodiment according to the invention to combine the direct injection from the upper head of the reactor with the injection using the sparger 10.
  • a toroidal pipe installed at the location where the emergency core cooling water is injected serves for the water to be uniformly sprinkled in a downcomer.
  • Fig. 5(c) discloses a system for injecting the emergency core cooling water by installing a sparger 10 on the safety injection pipe horizontal with a reactor vessel to allow for the cooling water injected through the safety injection pipe to flow into the downcomer in a vertical direction, in a PWR, a BWR, or an advanced reactor with safety injection of a DVI system for injecting the emergency core cooling water through a safety injection pipe installed separately from a cold leg.
  • Figs. 6(a) and 6(b) show sectional views of an embodiment according to the invention for the inclined injection of cooling water.
  • the present invention discloses a system for injecting the emergency core cooling water in which a safety injection pipe 4 is installed at an angle to the reactor vessel wall so that the injected cooling water may flow into a core at a predetermined angle, in a PWR, a BWR, or an advanced reactor with direct vessel injection for injecting the emergency core cooling water through a safety injection pipe 4 installed separately from a cold leg 2.
  • the angle ⁇ may vary within the range from 0° to 90°. As the angle ⁇ increases, more efficient inflow of the cooling water into the core is achieved.
  • Fig. 6(b) shows a sectional view of an embodiment for the horizontal injection of cooling water in a conventional manner in comparison to the inclined injection in Fig. 6(a).
  • the inclined injection according to the invention is preferred to the conventional horizontal injection.
  • Fig. 7 shows a three-dimensional diagram illustrating spirally threaded injection pipe for supplying the emergency cooling water.
  • Fig. 8 is a top view illustrating a direct injection pipe for injecting the emergency core cooling water according to an embodiment of the invention installed at the upper head of a nuclear reactor.
  • the injection pipe installed at the upper head according to an embodiment of the invention is made by attaching a vertical pipe to the horizontal direct injection pipe.
  • the direct injection pipe installed at the upper head of the reactor is highly effective in that it can be combined with the structures according to the invention, such as a vertical pipe, a sparger, an inclined injection pipe and internal spirally threaded injection pipe.
  • Results of the multidimensional flow simulation are presented for the horizontal injection and the vertical injection.
  • Such simplistic code analysis which partly depends on models not necessarily supported by experimental results, nonetheless provides enough information about how the multidimensional flow actually develops in a downcomer.
  • the CFX code used in the analysis of the multidimensional flow is a well-known commercial computational fluid dynamics tool, and the analysis was carried out by means of simple virtual replicas of a downcomer as shown in Fig. 9.
  • the analysis was performed for a turbulent flow in a three-dimensional, orthogonal coordinate system. For this analysis the assumption of incompressible fluid was applied and the gravity effect was taken into account. Only the single-phase liquid flow was considered.
  • the system pressure was set equal to the atmospheric pressure, the system temperature to 350K, the temperature of the emergency cooling water to 288K and the individual injection velocity to 12m/s.
  • the vector distribution of the emergency cooling water for two types of (a) horizontal injection and (b) vertical injection of Fig. 9 is shown in Fig. 10. It is seen that the downward velocity distribution is more pronounced in the vertical injection.
  • Fig. 11 shows the contours of the iso-velocities in a flow field on the assumption that the initial injection velocity of the emergency cooling water is 12m/s, wherein (a) shows the iso-velocity contour for flow velocity of 2.5m/s in the horizontal injection;
  • (b) shows the iso-velocity contour for flow velocity of 2.5m/s in the vertical injection
  • (d) shows the iso-velocity contour for flow velocity of 5m/s in the vertical injection
  • (e) shows the iso-velocity contour for flow velocity of lOm/s in the horizontal injection
  • (f) shows the iso-velocity contour for flow velocity of lOm/s in the vertical injection.
  • the difference between the vertical injection and the horizontal injection becomes more apparent when the iso-velocity contours for (a), (c), (e) and (b), (d), (f) are examined. That is, in the vertical injection, a high downward velocity contour extends more broadly than in the horizontal injection.
  • the contour in which the emergency cooling water in the flow field is at 5m/s is shown to be broader in the vertical injection, which signifies that the vertical injection is a secure method to maximize downward penetration of the emergency cooling water so that it can reach a core.
  • Results of the analysis for the vertical and horizontal injection of the emergency cooling water can be evaluated for their comparative integral performance only when performance of individual injection pipes are examined and compared.
  • Fig. 12 shows a schematic diagram of an arrangement of downcomer nozzles used in the analysis and the break in a cold leg.
  • Fig. 13 shows velocity distributions depending on heights from each DVI line (DVI 1, 2, 3 and 4).
  • Fig. 13(a) illustrates velocity distributions in the horizontal injection (DVI 1) and the vertical injection (DVVI 1) for the injection line 1.
  • Fig. 13(b) shows velocity distributions depending on heights in the horizontal injection (DVI 2) and the vertical injection (DVVI 2) for the injection line 2.
  • Fig. 13(c) shows velocity distributions depending on heights in the horizontal injection (DVI 3) and the vertical injection (DVVI 3) for the injection line 3.
  • Fig. 13 shows velocity distributions depending on heights from each DVI line (DVI 1, 2, 3 and 4).
  • Fig. 13(a) illustrates velocity distributions in the horizontal injection (DVI 1) and the vertical injection (DVVI 1) for the injection line 1.
  • Fig. 13(b) shows velocity distributions depending on heights in
  • FIG. 13(d) shows velocity distributions depending on heights in the horizontal injection (DVI 4) and the vertical injection (DVVI 4) for the injection line 4.
  • the highest velocity is indicated at the injection point of the emergency cooling water by the DVI, and a break in the cold leg is located at about 5.5m in height.
  • Fig. 14 presents velocity distributions in each of the injection lines for the vertical and horizontal injections, respectively.
  • Fig. 14(a) shows velocity distributions in each line in the horizontal injection
  • Fig. 14(b) shows velocity distributions in each line in the vertical injection.
  • a system for injecting the emergency core cooling water directly into a reactor vessel using a vertical pipe, a sparger, an internal spirally threaded injection pipe, and an inclined injection pipe of the invention, and a direct injection system where such injection pipes are installed at the upper head of a reactor vessel employ passive injection for which the gravity is used when injecting the emergency core cooling water into the core. Therefore, according to the invention, it is possible to prevent degradation of performance in the direct vessel injection system due to thermal hydraulic phenomena such as impingement, breakup and bypass that take place in a downcomer of the reactor vessel after injecting the emergency core cooling water, and to allow for the emergency core cooling water to flow more efficiently and stably into the lower plenum than by the convention horizontal injection.
  • the invention can contribute significantly to improving economics as well as enhancing safety in a system of a nuclear power plant. It is undesirable from the economics point of view to design a large-capacity ESF that would not be used at all in most cases during the life time of a nuclear power plant. Since it is possible to ensure safety even by injecting relatively a small amount of the emergency core cooling water according to the invention, it is possible to reduce the size of an arrangement that occupies larger areas than required, when designing the arrangement, so that the initial construction cost can be reduced.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

L'invention concerne système qui permet d'injecter de l'eau de refroidissement d'urgence du coeur, dans lequel l'eau injectée au travers d'un tuyau d'injection de sécurité peut s'écouler dans le tube de descente d'eau du réacteur dans une direction verticale, par fixation d'un tuyau vertical au tuyau d'injection de sécurité horizontal par rapport à la cuve du réaction, ou par installation d'un agitateur. L'invention concerne un système d'injection de l'eau de refroidissement d'urgence du coeur, dans lequel le tuyau d'injection de sécurité est installé au niveau de la tête d'une cuve de réaction afin d'optimiser la vitesse de l'eau injectée dans la direction verticale. L'invention concerne un système d'injection de l'eau de refroidissement d'urgence du coeur destiné à optimiser l'efficacité d'écoulement de l'eau de refroidissement d'urgence dans un tube de descente d'eau du réacteur dans les tuyaux torsadés. Ces systèmes sont disposés à l'entrée d'un tuyau vertical pour l'injection de l'eau, laquelle eau tourbillonne avec moins de résistance à la vapeur. L'invention concerne en outre un système d'injection de l'eau de refroidissement d'urgence du coeur, dans lequel un tuyau d'injection de sécurité est installé à un angle préétabli relativement à la paroi de la cuve de réaction, de sorte que l'eau de refroidissement injectée puisse s'écouler, selon un angle préétabli relativement au tube de descente d'eau du réacteur, d'un réacteur à eau sous pression, d'un réacteur à eau bouillante ou d'un réacteur perfectionné, par injection directe dans la cuve (DVI) grâce à laquelle l'eau de refroidissement d'urgence est injectée au travers du tuyau d'injection de sécurité installé séparément d'une voie froide.
PCT/KR2003/000161 2002-01-24 2003-01-24 Systeme pour injecter directement dans la cuve de l'eau de refroidissement d'urgence du coeur au moyen d'un tuyau d'injection vertical, agitateur, tuyau d'injection interne torsade et tuyau d'injection incline WO2003063177A1 (fr)

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KR20020004121 2002-01-24
KR10-2002-0004121 2002-01-24

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WO2003063177A1 true WO2003063177A1 (fr) 2003-07-31

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Cited By (3)

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JP2009175109A (ja) * 2008-01-21 2009-08-06 Korea Atom Energ Res Inst 非常炉心冷却水の原子炉容器直接注入装置及び直接注入方法
EP2133884A1 (fr) * 2008-03-17 2009-12-16 Korea Atomic Energy Research Institute Système de refroidissement de secours du coeur muni de conduits d'alimentation disposés sur l'enveloppe du coeur
CN103824604A (zh) * 2013-11-18 2014-05-28 国核（北京）科学技术研究院有限公司 堆芯紧急冷却热混合试验装置及其试验方法

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KR101504628B1 (ko) * 2014-01-15 2015-03-20 한국수력원자력 주식회사 깔대기형 안전주입 냉각수 안내관
CA3046169C (fr) 2016-12-14 2022-08-16 Otsuka Pharmaceutical Factory, Inc. Liquide de cryoconservation de cellules de mammifere
KR102289422B1 (ko) 2019-08-20 2021-08-17 한국원자력연구원 스파저 및 이를 구비하는 원전

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KR20000074521A (ko) * 1999-05-21 2000-12-15 이호림 사이펀 효과 차단 및 증기유량과의 접촉을 차단하기 위한 원자로내 안전주입수로
KR20010076568A (ko) * 2000-01-26 2001-08-16 이종훈 원자로의 안전주입 시스템

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009175109A (ja) * 2008-01-21 2009-08-06 Korea Atom Energ Res Inst 非常炉心冷却水の原子炉容器直接注入装置及び直接注入方法
JP4731577B2 (ja) * 2008-01-21 2011-07-27 韓國原子力研究所 非常炉心冷却水の原子炉容器直接注入装置
EP2133884A1 (fr) * 2008-03-17 2009-12-16 Korea Atomic Energy Research Institute Système de refroidissement de secours du coeur muni de conduits d'alimentation disposés sur l'enveloppe du coeur
CN103824604A (zh) * 2013-11-18 2014-05-28 国核（北京）科学技术研究院有限公司 堆芯紧急冷却热混合试验装置及其试验方法
CN103824604B (zh) * 2013-11-18 2016-04-06 国核（北京）科学技术研究院有限公司 堆芯紧急冷却热混合试验装置及其试验方法

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