WO2021137718A1 - Système pour retenir un bain de fusion dans un réacteur - Google Patents
Système pour retenir un bain de fusion dans un réacteur Download PDFInfo
- Publication number
- WO2021137718A1 WO2021137718A1 PCT/RU2020/000208 RU2020000208W WO2021137718A1 WO 2021137718 A1 WO2021137718 A1 WO 2021137718A1 RU 2020000208 W RU2020000208 W RU 2020000208W WO 2021137718 A1 WO2021137718 A1 WO 2021137718A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- reactor vessel
- reactor
- storage tank
- melt
- coolant
- Prior art date
Links
- 239000002826 coolant Substances 0.000 claims abstract description 35
- 239000000155 melt Substances 0.000 claims abstract description 25
- 230000014759 maintenance of location Effects 0.000 claims abstract description 12
- 238000003860 storage Methods 0.000 claims description 36
- 238000009833 condensation Methods 0.000 claims description 10
- 230000005494 condensation Effects 0.000 claims description 10
- 230000004907 flux Effects 0.000 claims description 6
- 239000007788 liquid Substances 0.000 abstract description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 23
- 238000001816 cooling Methods 0.000 description 16
- 238000013461 design Methods 0.000 description 6
- 239000004327 boric acid Substances 0.000 description 5
- 238000002844 melting Methods 0.000 description 4
- 230000008018 melting Effects 0.000 description 4
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 3
- 239000000110 cooling liquid Substances 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 3
- 230000008021 deposition Effects 0.000 description 3
- 238000009413 insulation Methods 0.000 description 3
- 238000009825 accumulation Methods 0.000 description 2
- 125000005619 boric acid group Chemical group 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 230000003213 activating effect Effects 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000004807 localization Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
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
-
- 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 invention relates to the field of nuclear energy and safety devices for nuclear power plants (NPP) in severe accidents.
- NPP nuclear power plants
- the invention is intended for use at various types of nuclear power plants.
- Known nuclear reactor containing a tank in which the reactor core is located, a primary circuit for cooling the reactor, a tank well in which the tank is located, an annular channel surrounding the lower part of the tank in the well tank, means capable of filling the well of the tank with liquid, a sealed reactor vessel in which the well of the tank and the tank are located, the reactor contains means for collecting steam generated at the upper end of the well of the tank, located in a sealed casing and forming a volume separated from the volume of the sealed casing , providing the appearance of excess vapor pressure, means adapted to create forced convection of the liquid in the annular channel, and means for activating the means adapted to create forced convection using said collected steam.
- RF patent for invention 2496163, publ. 11/27/2011 containing a tank in which the reactor core is located, a primary circuit for cooling the reactor, a tank well in which the tank is located, an annular channel surrounding the lower part of the tank in the well tank, means capable of filling the well of the tank with liquid
- Such a reactor makes it possible to increase the safety of its autonomous operation, without supplying external energy. Its disadvantage, however, is the insufficient safety of its use in an autonomous mode in a severe accident due to the use of complex devices for converting thermal energy into mechanical energy and further transferring mechanical energy.
- the closest to the claimed invention is a system for removing heat from a nuclear reactor vessel (RF patent N ° 2649417 for invention, publ. 03.04.2018), containing at least one pump connected to a cooling water source, designed for forced pumping of cooling water from the outside housings for thermoelectric converters for direct conversion of thermal energy into electrical energy, installed on the outer surface of the reactor vessel, and at least at least one electric motor to drive the pump, powered by thermoelectric converters.
- RF patent N ° 2649417 for invention, publ. 03.04.2018 containing at least one pump connected to a cooling water source, designed for forced pumping of cooling water from the outside housings for thermoelectric converters for direct conversion of thermal energy into electrical energy, installed on the outer surface of the reactor vessel, and at least at least one electric motor to drive the pump, powered by thermoelectric converters.
- the objective of the present invention is to develop a system for keeping the melt in the reactor vessel, which makes it possible to provide the possibility of keeping the melt in the vessel of a nuclear reactor at different severity of the accident, both in passive and active modes.
- the technical result of the present invention is to improve the safety of nuclear power plants by ensuring the possibility of keeping the melt in the body of a nuclear reactor in an accident of various severity, both in passive and active modes.
- the technical result is achieved by the fact that in the known system of in-vessel retention of the melt, containing the reactor located in the shaft, the pump for circulation of the coolant outside the reactor vessel and the storage tank, the storage tank is located in the shaft under the bottom of the reactor vessel, above the bottom of the reactor vessel there are additional sump tanks with the possibility of collecting coolant in the event of an accident with a loss of coolant, while the storage tank is connected to the upper part of the sump tanks with coolant supply channels.
- the storage tank with a pipeline with a steam condensation system located above the reactor vessel, and the reactor shaft - with a steam condensation system with steam removal channels. It is rational to introduce a special storage tank into the pipeline connecting the steam condensation system and the storage tank.
- the advantage of the present invention is to improve the safety of nuclear power plants by ensuring the possibility of keeping the melt in the reactor vessel in an accident of various severity, both in passive and active modes.
- the location of the storage tank in the shaft under the bottom of the reactor vessel, connected by channels for the coolant supply with the upper part of the sump tanks located above the bottom of the reactor vessel with the possibility of collecting coolant in the event of an accident with a loss of coolant makes it possible to retain the melt in the reactor vessel in case of various accidents.
- gravity in both passive and active modes due to the possibility of accumulation of coolant in the tanks-pits in a situation when the pumps of the ECCS system do not function, with its subsequent supply to the storage tank for cooling the reactor.
- Installing a deflector in the reactor shaft affects the technical result by ensuring the equalization of heat fluxes during reactor cooling.
- the ribbing of the deflector increases its area, which makes it possible to increase the heat flux during cooling of the reactor vessel.
- the introduction of a filter into the storage tank makes it possible to purify the coolant, which increases the cooling capabilities of the reactor vessel.
- Connecting the storage tank with pipelines to external sources of coolant allows for more efficient cooling of the reactor vessel in the active mode, i.e. while maintaining the efficiency of the pumps of the ECCS system.
- Providing the connection of the storage tank with a pipeline with the steam condensation system located above the reactor vessel, and the reactor shaft with the steam condensation system with the steam removal channels allows to provide an additional coolant flow loop with heat transfer through the steam condensation system.
- the introduction of a special storage tank into the pipeline connecting the steam condensation system and the storage tank makes it possible to ensure the deposition of boric acid in it, initially contained in the cooling liquid (water), which makes it possible to avoid its deposition on the surfaces forming the cooling channel of the reactor vessel, which in turn would reduce the heat flux cooling the reactor vessel.
- FIG. 1 shows a general view of the containment of a nuclear power plant with a system for keeping the melt in the reactor loop.
- FIG. 2 is a schematic diagram of a preferred embodiment of a melt retention system in a reactor vessel.
- FIG. 3 shows a view of the lower part of the containment of a nuclear power plant with a system for keeping the melt in the reactor vessel.
- the system for keeping the melt in the reactor vessel preferably comprises a reactor 1 located in the shaft, one or more coolant circulation pumps (not shown in the figures) outside the reactor vessel, on the side of which, at the level of its middle part, there are pit tanks 2 of the emergency cooling system of the active zone (ECCS), below the reactor 1 there is a storage tank 3 connected through a filter 6 by a coolant supply channel 7 to the upper part of the sump tanks 2.
- the storage tank 3 is also connected through pipelines 5 to external water sources shown in the diagram in FIG. 2.
- One of such sources is condensing heat exchangers 9, a special storage tank is installed in the pipeline 4 connecting them to the storage tank 3 8.
- a deflector is installed around the reactor vessel in the reactor shaft with a small gap 5. In the upper part of the reactor, above the deflector, drainage channels are made pair 10, connected to common containment areas.
- the cooling liquid water with some boric acid content
- special tanks such as the hydraulic accumulators of the ECCS system and the hydraulic accumulators of the second stage, revision shafts, as well as in sump tanks 2, while the water level in the sump tanks is at a level below the intake of the coolant intake channel 7 and therefore does not enter the storage tank 3.
- the ingress of water on the reactor vessel at its maximum operating temperature is unacceptable.
- the liquid is taken from the sump tanks 2 by standard means of this system and fed into the internal volume of the reactor 1, so that it does not reach the level of the intake hole of the coolant intake channel 7, despite on the flow of the coolant through the breaks in the pipelines with the coolant, and does not enter the storage tank 3.
- the circulation pumps of the pipelines 4 for supplying water from external sources also do not work, so that the water level in the storage tank 3 cannot reach the reactor vessel 1, which reduces the number of loading cycles of the reactor vessel 1, protecting it from unnecessary loads.
- water is supplied for filling the reactor shaft from the maximum number of different sources available (depending on the accident scenario) - from the main circulation loop, from the ECCS system hydraulic reservoirs and the second stage hydraulic reservoirs, from the revision shafts, from sources outside the containment ...
- the resulting steam-water mixture is discharged through the steam removal channels 10 in the reactor shaft equipment to the steam generator (SG) boxes and further to the space under the containment dome, where steam is condensed due to the operation of the passive heat removal system from the containment shell (SPOT 30) and then water it flows by gravity into the shaft of the reactor 1. At the same time, heat is removed from the containment shell to the atmospheric air for an unlimited time.
- the pipeline 4, connecting the SPOT 30 and the storage tank 3, a special storage tank 8 is introduced, designed for b collection of condensate from heat exchangers SPOT 30 and its further supply to the storage tank 3.
- a special storage tank 8 is introduced, designed for b collection of condensate from heat exchangers SPOT 30 and its further supply to the storage tank 3.
- the elements of the system for containing the melt in the reactor vessel, as well as the systems associated with them, can be equipped with instrumentation necessary for monitoring and managing a severe beyond design basis accident.
- melt retention system in the reactor vessel in the designs of the power unit and the reactor plant does not lead to a deterioration in operational characteristics (installed capacity utilization factor (ICUF), availability factor, time and dose costs during maintenance and repair), and an increase in heat losses from equipment.
- ICUF installed capacity utilization factor
- availability factor availability factor
- time and dose costs during maintenance and repair
- the system for keeping the melt in the reactor vessel does not interfere with the operation of ventilation ducts in the concrete of the mine and the passage of cooling air between the heat insulation of the vessel and the metal structure of the dry shield during normal operation, disruption of normal operation, in emergency modes (design basis accident and beyond design basis accident without core melting).
- the design of the elements of the melt retention system in the reactor vessel excludes the ingress of water onto the reactor vessel in all modes, except for a severe accident, in order to reduce the number of vessel loading cycles.
- the lower part of the deflector 5 also performs the function of thermal insulation of the reactor vessel. To provide personnel access to the bottom of the reactor 1, the lower part of the deflector 5 (with thermal insulation) can be made with the possibility of going down.
- Filter 6 which provides cleaning of the coolant from contamination, is located in the lower part of the reactor shaft around the storage tank 3. It is also possible to use standard ECCS filters to ensure the purity of the water supplied to the melt retention system in the reactor vessel.
- pipelines 4 for supplying water from external sources preferably include:
- the supply channel is located above the nominal water level in the sump tanks 2. In this case, water is supplied to the reactor shaft only after accidents with loss of coolant.
- the system for retention of the melt in the reactor vessel can be used in nuclear power plants of various types and can improve their safety by ensuring the retention of the melt in the reactor vessel during various types of accidents.
Landscapes
- 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 se rapporte au domaine de l'énergie nucléaire et a pour but d'augmenter la sécurité des centrales nucléaires en garantissant la possibilité de retenir un bain de fusion dans le corps d'un réacteur nucléaire lors de divers niveaux de difficultés en cas d'accident tant en mode passif qu'en mode actif. L'invention concerne un système de retenu d'un bain de fusion dans un corps, lequel comprend un réacteur disposé dans un puits, une pompe de circulation d'un liquide de refroidissement à l'extérieur du corps du réacteur et un réservoir d'accumulation; le système est caractérisé en ce que le réservoir de récupération est disposé dans le puits sous le fond du corps du réacteur tandis que, au-dessus du fond du corps du réacteur se trouvent en outre des réservoirs de réception capables de recueillir le liquide de refroidissement en cas d'accident avec une perte du caloporteur; le réservoir d'accumulation est connecté à la partie supérieure des réservoirs de réception par des canaux d'admission en liquide de refroidissement. Ce système de retenue de bain de fusion dans le corps d'un réacteur peut être utilisé dans des centrales nucléaires de divers types, et permet d'augmenter leur sécurité en retenant le bain de fusion dans le corps du réacteur lors de divers types d'accidents.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202080047834.1A CN114730641A (zh) | 2019-12-30 | 2020-04-30 | 反应堆容器中的熔体保留系统 |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| RU2019145006A RU2726226C1 (ru) | 2019-12-30 | 2019-12-30 | Система удержания расплава в корпусе реактора |
| RU2019145006 | 2019-12-30 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO2021137718A1 true WO2021137718A1 (fr) | 2021-07-08 |
Family
ID=71510157
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/RU2020/000208 WO2021137718A1 (fr) | 2019-12-30 | 2020-04-30 | Système pour retenir un bain de fusion dans un réacteur |
Country Status (3)
| Country | Link |
|---|---|
| CN (1) | CN114730641A (fr) |
| RU (1) | RU2726226C1 (fr) |
| WO (1) | WO2021137718A1 (fr) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112191287B (zh) * | 2020-09-30 | 2021-11-02 | 中国核动力研究设计院 | 一种高温熔融物全自动释放机构及其控制方法 |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2187852C1 (ru) * | 2001-05-11 | 2002-08-20 | Российский научный центр "Курчатовский институт" | Ловушка расплава активной зоны ядерного реактора |
| RU2496163C2 (ru) | 2007-10-22 | 2013-10-20 | Коммиссариат А Л'Энержи Атомик Э Оз Энержи Альтернатив | Ядерный реактор с улучшенным охлаждением в аварийной ситуации |
| CN104036833A (zh) | 2014-05-23 | 2014-09-10 | 中国核电工程有限公司 | 具有导热堆坑外墙的核电站事故后堆内熔融物滞留系统 |
| RU2649417C1 (ru) | 2017-01-24 | 2018-04-03 | Общество с ограниченной ответственностью "Научно-технический центр инноваций" | Система и способ отвода тепла от корпуса ядерного реактора |
| CN108550406A (zh) * | 2018-03-16 | 2018-09-18 | 中国核电工程有限公司 | 堆芯熔融物捕集装置 |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2169953C2 (ru) * | 1999-08-12 | 2001-06-27 | Российский научный центр "Курчатовский институт" | Ловушка расплава активной зоны ядерного реактора |
| RU35463U1 (ru) * | 2003-08-18 | 2004-01-10 | Хабенский Владимир Бенцианович | Устройство локализации и охлаждения кориума аварийного ядерного реактора водо-водяного типа |
| RU2700925C1 (ru) * | 2018-09-25 | 2019-09-24 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава активной зоны ядерного реактора |
| RU2696012C1 (ru) * | 2018-11-08 | 2019-07-30 | Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" | Устройство локализации кориума ядерного реактора водо-водяного типа |
| RU2696612C1 (ru) * | 2018-12-26 | 2019-08-05 | Акционерное Общество "Атомэнергопроект" | Устройство локализации расплава |
-
2019
- 2019-12-30 RU RU2019145006A patent/RU2726226C1/ru active
-
2020
- 2020-04-30 WO PCT/RU2020/000208 patent/WO2021137718A1/fr active Application Filing
- 2020-04-30 CN CN202080047834.1A patent/CN114730641A/zh active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2187852C1 (ru) * | 2001-05-11 | 2002-08-20 | Российский научный центр "Курчатовский институт" | Ловушка расплава активной зоны ядерного реактора |
| RU2496163C2 (ru) | 2007-10-22 | 2013-10-20 | Коммиссариат А Л'Энержи Атомик Э Оз Энержи Альтернатив | Ядерный реактор с улучшенным охлаждением в аварийной ситуации |
| CN104036833A (zh) | 2014-05-23 | 2014-09-10 | 中国核电工程有限公司 | 具有导热堆坑外墙的核电站事故后堆内熔融物滞留系统 |
| RU2649417C1 (ru) | 2017-01-24 | 2018-04-03 | Общество с ограниченной ответственностью "Научно-технический центр инноваций" | Система и способ отвода тепла от корпуса ядерного реактора |
| CN108550406A (zh) * | 2018-03-16 | 2018-09-18 | 中国核电工程有限公司 | 堆芯熔融物捕集装置 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN114730641A (zh) | 2022-07-08 |
| RU2726226C1 (ru) | 2020-07-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US10726959B2 (en) | Nuclear power plant | |
| CN103377728B (zh) | 一种水淹式安全壳完全非能动余热导出系统 | |
| US10290379B2 (en) | Passive containment cooling and filtered venting system, and nuclear power plant | |
| US10115488B2 (en) | Passive safety equipment for a nuclear power plant | |
| WO2015149718A1 (fr) | Système de dissipation passive de la chaleur de cuve de confinement, procédé de commande de celui-ci et réacteur à eau sous pression | |
| KR101973996B1 (ko) | 원자로용기 외벽 냉각 및 발전 시스템 | |
| KR20140126187A (ko) | 피동안전설비 및 이를 구비하는 원전 | |
| EP0397509B1 (fr) | Système indirect passif de refroidissement pour les réacteurs nucléaires à refroidissement par les métaux liquides | |
| US20120213322A1 (en) | Emergency core cooling system and reactor facility | |
| JPH0216496A (ja) | 停止冷却系熱交換器付き隔離復水器 | |
| KR101505475B1 (ko) | 피동격납부냉각계통 및 이를 구비하는 원전 | |
| WO2021137718A1 (fr) | Système pour retenir un bain de fusion dans un réacteur | |
| KR101502393B1 (ko) | 피동안전계통 및 이를 구비하는 원전 | |
| CN111599498B (zh) | 一种非能动安全壳空气-水长期冷却系统 | |
| US4698201A (en) | Heat exchanger equipped with emergency cooling means and fast neutron nuclear reactor incorporating such an exchanger | |
| US20230215589A1 (en) | Self-cleaning liquid purification system | |
| JP4031259B2 (ja) | 原子炉格納容器冷却設備 | |
| US4175001A (en) | Gas turbine power plant with closed gas circuit | |
| EP2500908A1 (fr) | Dispositif de refroidissement de c ur de réacteur d'urgence et installation de réacteur nucléaire | |
| EA046615B1 (ru) | Система удержания расплава в корпусе реактора | |
| JP5941795B2 (ja) | 原子炉圧力容器の冷却設備および原子炉圧力容器の冷却設備による冷却方法 | |
| CN1322516C (zh) | 用于核技术设备的燃料元件的中间储存系统及其运行方法 | |
| US5078959A (en) | Reactor block of a fast reactor, with an inner cylindrical vessel for removing the residual power of the core by natural circulation | |
| CN111933315A (zh) | 一种用于池式铅基反应堆的非能动余热排出系统及方法 | |
| CN111883270A (zh) | 热量排出系统、池式反应堆以及池式反应堆热量排出方法 |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| 121 | Ep: the epo has been informed by wipo that ep was designated in this application |
Ref document number: 20909258 Country of ref document: EP Kind code of ref document: A1 |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 140050140003008455 Country of ref document: IR |
|
| NENP | Non-entry into the national phase |
Ref country code: DE |
|
| ENP | Entry into the national phase |
Ref document number: 2020909258 Country of ref document: EP Effective date: 20220801 |
|
| ENP | Entry into the national phase |
Ref document number: 2020909258 Country of ref document: EP Effective date: 20220801 |