GB2542442A - Composite construction of nuclear reactor pressure vessel and barrier shield - Google Patents
Composite construction of nuclear reactor pressure vessel and barrier shield Download PDFInfo
- Publication number
- GB2542442A GB2542442A GB1521982.7A GB201521982A GB2542442A GB 2542442 A GB2542442 A GB 2542442A GB 201521982 A GB201521982 A GB 201521982A GB 2542442 A GB2542442 A GB 2542442A
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- GB
- United Kingdom
- Prior art keywords
- pressure vessel
- barrier shield
- reactor pressure
- reactor
- receiving chamber
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- Legal status (The legal status 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 status listed.)
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
-
- 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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- 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
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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
A composite nuclear reactor pressure vessel and barrier shield comprising: a barrier shield being formed with a water injection pipe connected to a reactor pit lower portion, wherein the reactor pit is enclosed by the barrier shield; this aims to maintain the melt in the reactor pressure vessel. The reactor pressure vessel having thermal insulation is seated in the reactor pit with a passageway between the insulation and the reactor pressure vessel and between the insulation and the barrier shield. The barrier shield defining a receiving chamber at an upper inner wall and having a reflux flow channel, which connects the receiving chamber with the bottom of the reactor pit. The reflux flow channel may define a bottom outlet in the reactor pit with a blocking element for use in normal operation, but which can be opened under severe accident conditions. The passageway between the insulation and the barrier shield may be a normal ventilation channel. The barrier shield may be characterised in that the annular receiving chamber is located at a height indicating position where the coolant lines are connected to the reactor.
Description
SPECIFICATION
Composite Construction of Nuclear Reactor Pressure Vessel and Barrier Shield
FIELD OF THE INVENTION
[0001] The present invention generally relates to nuclear power plants and, more particularly, to a composite construction of nuclear reactor pressure vessel and barrier shield which can deal with server accident conditions.
BACKGROUND OF THE INVENTION
[0002] After Chernobyl, Three Mile Island, Fukushima nuclear power plant accidents, countries around the world pay unprecedented attentions to nuclear safety. More strict requirements have been requested to the probability of severe accident of the next generation nuclear power plant. According to the characteristics of the nuclear power plants in service or in construction in each country, various kinds of projects have been set forth to mitigate severe accidents. On April 18, 2014, China Nuclear Safety Agency published the latest version of Design Safety Requirements of Nuclear Power Plant (HAF102) and IAEA Guide Rule NS-G-1.10, which require to taking accident prevention and accident mitigation in consideration as much as possible during the design of nuclear power plants.
[0003] When severe accidents occur to pressurized water reactor nuclear power plant, if cooling measures in the reactor fail to function, the reactor core will melt gradually, collapse and fall into the bottom of the reactor pressure vessel. In this case, if there is no effective external cooling means available, fusion of the reactor pressure vessel as well as retention and failure of the melt in the reactor may occur. The melt of the reactor enters the reactor pit and further carries out MCCI reaction with the concrete floor (reaction between the melt and the concrete), which will lead to release of hazardous combustible gases and further lead to notable severe accident deterioration.
[0004] To avoid retention and failure of the melt in the reactor, external cooling has been used to cool reactor pressure vessel of conventional pressurized water reactor nuclear power plant. Under severe accident conditions, water is injected into the reactor pit, so that the reactor pressure vessel is immerged in the water in the reactor pit. External wall cooling method can ensure the reactor pressure vessel cannot be fused, so that the melt in the reactor can be stably maintained in the reactor pressure vessel. To avoid the fusion of the reactor pressure vessel due to inadequate critical heat flux density, larger flow of the cooling medium must pass through the external wall of the reactor pressure vessel. There is need to provide suitable channel design for the external cooling medium of the reactor pressure vessel, such that the external cooling medium can generate natural circulation effect strong enough. Generally, a appropriate gap is defined between the external wall of the reactor pressure vessel and the thermal insulation thereof, and an overboard steam drain hole and a lower inlet are respectively defined in upper and lower sections of the thermal insulation. Under severe accident conditions, the overboard steam drain hole and lower inlet are opened according to the passive principle, to provide upwelling channel for external cooling. As to the mixture of the water and the gas from the overboard steam drain hole, there is small amount of vapor (about 1 wt %). The main ingredient of the mixture of water and gas is saturated water. In order to form strong and stable natural circulation effect of external cooling, the saturated water needs to flow back to the bottom of the reactor pit at a small pressure drop. According to experiments and analysis, increasing natural circulation flow of external cooling can facilitate improving the critical heat flux density, so as to ensure the external cooling capacity.
[0005] In conventional nuclear power design, a support ring is used to provide natural circulation channel for external cooling. However, due to the seismic requirements of the nuclear power plant, the upper surface of the support ring is higher than the overflow elevation of the reactor pit. Therefore, the support ring cannot provide the reflux flow channel for the external cooling. Therefore, there is a need to adjust the structure and design of the reactor pit, to provide a reflux flow channel for external cooling. In addition, in spite of compact structure of the reactor pit, the reactor pit has multiple functions. There is a need to integrate functional designs under normal operation and severe accident conditions as well as provide a reflux flow channel for external cooling.
[0006] What is needed, therefore, is to provide a composite construction of a nuclear reactor pressure vessel and a barrier shield, which can form stable natural circulation of the cooling medium under severe accident conditions, so as to cool the reactor pressure vessel more effectively and ensure the integrity of the reactor pressure vessel.
SUMMARY OF I III INVENTION
[0007] One object of the present invention is to provide a composite construction of nuclear reactor pressure vessel and barrier shield, which can form stable natural circulation of the cooling medium under severe accident conditions, so as to cool the reactor pressure vessel more effectively and ensure the integrity of the reactor pressure vessel.
[0008] According to one embodiment of the present invention, a composite construction of nuclear reactor pressure vessel and barrier shield including: a barrier shield being formed with a water injection pipe in communication with a reactor pit at a lower portion thereof; a reactor pit enclosed by the barrier shield; and a reactor pressure vessel having a thermal insulation formed thereon seated in the reactor pit, with a passageway being defined between the thermal insulation and the reactor pressure vessel and another passageway being defined between the thermal insulation and the barrier shield. The barrier shield defines a receiving chamber at an upper inner wall thereof, and a reflux flow channel is defined in the barrier shield for connecting the receiving chamber with a bottom of the reactor pit.
[0009] According to one aspect of the present invention, the reflux flow channel defines a bottom outlet in communication with the bottom space of the reactor pit, the bottom outlet is formed with a blocking element, the blocking element blocks the bottom outlet of the reflux flow channel in normal operation to avoid division of normal airflow in the reflux flow channel, the blocking element is automatically opened according to passive principle under severe accident conditions to keep the reflux flow channel unobstructed and ensure the external cooling medium in the receiving chamber can flow back to the bottom of the reactor pit smoothly.
[0010] According to one aspect of the present invention, the passageway between the thermal insulation and the reactor pressure vessel is an upwelling channel for the external cooling medium under severe accident conditions, the upwelling channel and the reflux flow channel form a natural circulation circuit due to the density difference of the cooling medium under severe accident conditions to cool the outer side of the reactor pressure vessel continuously.
[0011] According to one aspect of the present invention, the receiving chamber of the barrier shield is connected to the pit exterior space out of the reactor pit via the main coolant line gateways, the vapor liquid mixed medium in the upwelling channel divided into vapor and saturated water in the receiving chamber under severe accident conditions, wherein the vapor is discharged out of the reactor pit via the main coolant line gateways in the barrier shield to take the heat out of the reactor pit, and the separated saturated water flows back to the bottom of the reactor pit via the reflux flow channel.
[0012] According to one aspect of the present invention, the thermal insulation defines water injection holes at a bottom thereof, overboard steam drain holes are defined between the top of the thermal insulation and the reactor pressure vessel, the water injection holes and the overboard steam drain hole are closed in normal conditions and are automatically opened according to passive principle under severe accident conditions, so as to define an upwelling channel for the external cooling medium between the reactor pressure vessel and the thermal insulation.
[0013] According to one aspect of the present invention, the water injection holes are located below the lower seal head of the reactor pressure vessel.
[0014] According to one aspect of the present invention, the top inlet of the reflux flow channel is located at a lowest point of the receiving chamber of the barrier shield.
[0015] According to one aspect of the present invention, the receiving chamber of the barrier shield is located at a height indicating position where the main pipelines are connected to the reactor and the receiving chamber has an annular shape.
[0016] According to one aspect of the present invention, the reactor pressure vessel is equipped with a number of main coolant lines at an upper portion thereof with each main coolant line extending out of the barrier shield via a corresponding main coolant line gateway, and the main coolant line gateway has a diameter larger than a cross section of the main pipeline to communicate the receiving chamber with the pit exterior space out of the reactor pit.
[0017] According to one aspect of the present invention, a support ring is provided at a bottom of the annular receiving chamber for supporting the nozzle of the main coolant lines so that the reactor pressure vessel hangs in the reactor pit, and the top inlet of the reflux flow channel is positioned in the bottom wall of the receiving chamber outside of the support ring.
[0018] According to one aspect of the present invention, the passageway between the thermal insulation and the barrier shield is a normal ventilation channel which acts as an airflow channel for the ventilation of the reactor pit under normal operation.
[0019] Compared with the prior art, the composite construction of a nuclear reactor pressure vessel and a barrier shield of the present invention defines a reflux flow channel in the side wall of the barrier shield, which can ensure the saturated water in the vapor flow back to the reactor pit smoothly, so that a stable natural circulation can be formed in the upwelling channel A and the flux flow channel due to the density difference of the external cooling medium. Under severe accident conditions, the reactor pressure vessel can be cooled quickly and continuously. Therefore, the melt can be maintained in the reactor pressure vessel efficiently.
[0020] Other advantages and novel features will be drawn from the following detailed description of preferred embodiment with the attached drawings, in which:
BRIEF DESCRIPTION OF THE DRAWINGS
[0021] Fig. 1 depicts a schematic diagram of a composite construction of nuclear reactor pressure vessel and barrier shield according to one embodiment of the present invention.
DETAILED DESCRIPTION OF THE INVENTION
[0022] Example embodiments of the present invention will now be described more fully hereinafter with reference to the accompanying drawings, in which some, but not all embodiments of the invention are shown. Indeed, the invention may be embodied in many different forms and should not be construed as limited to the embodiments set forth herein; rather, these embodiments are provided so that this disclosure will satisfy applicable legal requirements. Like reference numerals refer to like elements throughout.
[0023] Referring to Fig. 1, the composite construction of nuclear reactor pressure vessel and barrier shield in accordance with one embodiment of the present invention includes a barrier shield 10, a reactor pit 20 enclosed by the barrier shield 10, and a reactor pressure vessel 30 positioned in the reactor pit 20. Upper portion of the reactor pressure vessel 30 is equipped with a number of main coolant lines 32 extending out through the barrier shield 10.
[0024] The barrier shield 10 includes a side wall 12 and a bottom wall 14. The side wall 12 defines an annular receiving chamber 120 and a number of main coolant line gateways 122 for connecting the receiving chamber 120 with the pit exterior space. The receiving chamber 120 is seated at the height indicating position where the main pipelines are connected to the reactor. The number and position of the main coolant line gateways 122 correspond to the number and position of the main coolant lines 32. The receiving chamber 120 is provided with a support ring 16 at a bottom wall thereof for supporting the main coolant lines 32, so that the reactor pressure vessel 30 hangs in the reactor pit 20. The main coolant line gateways 122 each have a size larger than the cross section of a corresponding main coolant line 32. There is no sealing means between a main coolant line gateway 122 and a corresponding main coolant line 32. Therefore, the main coolant line gateways 122 are configured as the channels for connecting the reactor pit 20 and the receiving chamber 120 to the exterior space. The bottom of each main coolant line gateway 122 is higher than the bottom of the receiving chamber 120. The main coolant line gateway 122 and the receiving chamber 120 jointly define a vent hole of the barrier shield 10. Lower portion of the side wall 12 is hermetically formed with a water injection pipe 18 extending through the side wall 12. The outlet of the water injection pipe 18 is close to the bottom of the reactor pit 20, so that the water injection pipe 18 can be used to inject water into the reactor pit 20 under severe accident conditions. The water injection pipes 18 are connected to the water source, such as water tank of the reactor pit and the refueling water tank in the containment. Water can be injected into the reactor pit 20 via passive principle, active principle or combination thereof.
[0025] In order to ensure external cooling efficiency of the reactor pressure vessel 30, the reactor pressure vessel 30 is formed with a thermal insulation 34 at an outside thereof. The thermal insulation 34 is supported on the inner wall of the barrier shield 10 via a supporting element (not shown). Inner wall of the thermal insulation 30 is set apart from the reactor pressure vessel 30. Therefore, a gap extending through up and down is defined between the inner wall of the thermal insulation 34 and the outer wall of the reactor pressure vessel 30. The thermal insulation 34 defines a number of water injection holes 340 laterally arranged below the lower seal head of the reactor pressure vessel 30. A vent hole is provided between the top of the thermal insulation 34 and the reactor pressure vessel 30. The overboard steam drain hole of the thermal insulation 34 and the lower water injection holes 340 are closed in normal conditions while are opened automatically under severe accident conditions, so that an upwelling channel A is provided between the reactor pressure vessel 30 and the thermal insulation 34. The upwelling channel A allows the rising of the cooling medium outside of the reactor under severe accident conditions. The outer wall of the thermal insulation 34 does not contact the inner wall of the barrier shield 10. Therefore, another gap extending through up and down which is in communication with the ventilation structure of the reactor pit (not shown) is provided between the barrier shield 10 and the thermal insulation 34. In this case, the gap, referred as normal airflow channel B, acts as the airflow channel of the reactor pit 20 during normal operation of the reactor core.
[0026] In order to form natural circulation of the cooling water in the reactor pit 20, in accordance with one embodiment of the present invention, the side wall 12 of the barrier shield 10 defines a reflux flow channel 124 which can act as external cooling under server accident conditions. Top inlet of the reflux flow channel 124 is defined in the bottom wall of the receiving chamber 120 outside of the support ring 16. The reflux flow channel 124 almost extends along the whole height of the side wall 12. The bottom outlet of the reflux flow channel 124 is defined in the inner wall of the side wall 12 close to the bottom of the reactor pit 20. To ensure smooth flux, the top inlet of the reflux flow channel 124 is at the lowest point of the receiving chamber 120. A blocking element 126 is provided at the bottom outlet of the reflux flow channel 124, such as a check valve or any one blocking element which has the same function as that of the check valve. In normal conditions, the blocking element 126 is closed. The flow from the reactor pit 20 is not divided into streams at the reflux flow channel 124, and the reflux flow channel 124 does not affect the normal operation of the reactor pit 20. Under severe accident conditions, the blocking element 126 is opened automatically according to passive principle. The reflux flow channel 124 is unblocked, so as to provide a return path for the saturated water and form a natural circulation flow path for external cooling together with the upwelling channel A.
[0027] Under severe accident conditions of a nuclear power plant, the composite construction of a nuclear reactor pressure vessel and a barrier shield according to the present invention functions as following: [0028] 1) When the outlet temperature of the reactor pressure vessel 30 is higher than 650°C, cooling water is injected into the reactor pit 20 via the water injection pipe 18. At first, a large flow of water is injected into the reactor pit 20 to fill the reactor pit 20 quickly and submerge the outer wall of the bottom of the reactor pressure vessel 30. Then, a small flow of water is injected into the reactor pit 20, to supplement the water loss due to evaporation for cooling the reactor pressure vessel 30.
[0029] 2) The lower water injection holes 340 in the thermal insulation 34, the overboard steam drain hole and the blocking element 126 at the lower outlet of the reflux flow channel 124 are opened automatically. The cooling water enters the reactor pit 20 is divided into two streams. One stream of the cooling water passes through the water injection holes 340 to cool the reactor pressure vessel 30 via the upwelling channel A. The other stream of water enters and stays in the normal airflow channel B to cool the whole reactor pit 20.
[0030] 3) The cooling water passing through the upwelling channel A flows to the lower seal head of the reactor pressure vessel 30 and is heated to boiling, to generate vapor liquid mixed medium. The vapor liquid mixed medium goes up to the top of the upwelling channel A and flows out via the gaps between the reactor pressure vessel 30 and the thermal insulation 34/the support ring 16, and further enters the receiving chamber 120.
[0031] 4) The vapor liquid mixed medium is separated into vapor and saturated water in the annular receiving chamber 120. The vapor is discharged out of the reactor pit 20 via the main coolant lines 122 of the barrier shield 10 and takes away the heat in the reactor pit 20. The separated saturated water flows back to the bottom of the reactor pit 20 via the reflux flow channel 124.
[0032] 5) In this case, the upwelling channel A and the reflux flow channel 124 forms a natural circulation circuit for external cooling. The external cooling medium in the upwelling channel A is vapor liquid mixed medium which has a small density. The external cooling medium in the reflux flow channel 124 is saturated water which has a large density. Density difference between the upwelling channel A and the reflux flow channel 124 provides a driving force for the natural circulation, such that the cooling fluid passing through the outer wall of the reactor pressure vessel 30 has a high flow rate, to cool the reactor pressure vessel 30 continuously and efficiently.
[0033] According to the embodiment of the present invention as previously described, the composite construction of nuclear reactor pressure vessel and barrier shield defines a reflux flow channel 124 in the side wall 12 of the barrier shield 10, which can form a stable natural circulation in the upwelling channel A and the flux flow channel 124 due to the density difference of the external cooling medium. Under severe accident conditions, the reactor pressure vessel 30 can be cooled quickly and continuously. The melt can be maintained in the reactor pressure vessel 30 efficiently and the integrity of the reactor pressure vessel 30 is maintained.
[0034] While the present invention has been illustrated by the above description of the preferred embodiment thereof, while the preferred embodiment has been described in considerable detail, it is not intended to restrict or in any way limit the scope of the appended claims to such details. Additional advantages and modifications within the spirit and scope of the present invention will readily appear to those ordinary skilled in the art. Consequently, the present invention is not limited to the specific details and the illustrative examples as shown and described.
Claims (12)
1. A composite construction of nuclear reactor pressure vessel and barrier shield, comprising: a barrier shield being formed with a water injection pipe in communication with a reactor pit at a lower portion thereof; a reactor pit enclosed by the barrier shield; and a reactor pressure vessel having a thermal insulation formed thereon seated in the reactor pit, with a passageway being defined between the thermal insulation and the reactor pressure vessel and another passageway being defined between the thermal insulation and the barrier shield, characterized in that the barrier shield defines a receiving chamber at an upper inner wall thereof, and a reflux flow channel is defined in the barrier shield for connecting the receiving chamber with a bottom of the reactor pit.
2. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 1, characterized in that the reflux flow channel defines a bottom outlet in communication with the bottom space of the reactor pit, the bottom outlet is formed with a blocking element, the blocking element can block the bottom outlet of the reflux flow channel in normal operation to avoid division of normal airflow in the reflux flow channel, the blocking element is automatically opened according to passive principle under severe accident conditions to keep the reflux flow channel unobstructed and ensure the external cooling medium in the receiving chamber can flow back to the bottom of the reactor pit smoothly.
3. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 1 or 2, characterized in that the passageway between the thermal insulation and the reactor pressure vessel is an upwelling channel for the external cooling medium under severe accident conditions, the upwelling channel and the reflux flow channel form a natural circulation circuit due to density difference of the cooling medium under severe accident conditions to cool the outer side of the reactor pressure vessel continuously.
4. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 3, characterized in that the receiving chamber of the barrier shield is connected to the exterior space out of the reactor pit via the main coolant line gateways, the vapor liquid mixed medium in the upwelling channel divided into vapor and saturated water in the receiving chamber under severe accident conditions, wherein the vapor is discharged out of the reactor pit via the main coolant line gateways in the barrier shield to take the heat out of the reactor pit, and the separated saturated water flows back to the bottom of the reactor pit via the reflux flow channel.
5. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 3, characterized in that the thermal insulation defines water injection holes at a bottom thereof, overboard steam drain holes are defined between the top of the thermal insulation and the reactor pressure vessel, the water injection holes and the overboard steam drain hole are closed in normal conditions and are automatically opened according to passive principle under severe accident conditions, to define an upwelling channel for the external cooling medium between the reactor pressure vessel and the thermal insulation.
6. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 5, characterized in that the water injection holes are located below the lower seal head of the reactor pressure vessel.
7. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 1, characterized in that a top inlet of the reflux flow channel is located at a lowest point of the receiving chamber of the barrier shield.
8. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 1, characterized in that the receiving chamber of the barrier shield is located at a height indicating position where the coolant lines are connected to the reactor and the receiving chamber has an annular shape.
9. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 8, characterized in that the reactor pressure vessel is connected with a plurality of main coolant lines at an upper portion thereof with each main coolant line extending out of the barrier shield via a corresponding main coolant line gateway, the main coolant line gateway has a diameter larger than a cross section of the main pipeline to communicate the receiving chamber with the exterior space out of the reactor pit.
10. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 9, characterized in that a support ring is provided at a bottom of the annular receiving chamber for supporting nozzle of the main coolant lines so that the reactor pressure vessel hangs in the reactor pit, and a top inlet of the reflux flow channel is positioned in the bottom wall of the receiving chamber outside of the support ring.
11. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 9, characterized in that a bottom wall of the main coolant line gateway is higher than a bottom wall of the annular receiving chamber, a top inlet of the reflux flow channel is positioned at the lowest point of the annular receiving chamber.
12. The composite construction of nuclear reactor pressure vessel and barrier shield of claim 1, characterized in that the passageway between the thermal insulation and the barrier shield is a normal ventilation channel which acts as an airflow channel for the ventilation of the reactor pit under normal operation.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510586928.7A CN105280249B (en) | 2015-09-16 | 2015-09-16 | The combining structure of nuclear power plant reactor pressure vessel and barrier shield |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| GB201521982D0 GB201521982D0 (en) | 2016-01-27 |
| GB2542442A true GB2542442A (en) | 2017-03-22 |
| GB2542442B GB2542442B (en) | 2019-07-10 |
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| Application Number | Title | Priority Date | Filing Date |
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| GB1521982.7A Active GB2542442B (en) | 2015-09-16 | 2015-12-14 | Composite construction of nuclear reactor pressure vessel and barrier shield |
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| Country | Link |
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| CN (1) | CN105280249B (en) |
| GB (1) | GB2542442B (en) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107039094B (en) * | 2017-05-24 | 2019-02-01 | 长江勘测规划设计研究有限责任公司 | Pressure vessel changeable type underground nuclear power station heap chamber |
| CN107845434B (en) * | 2017-10-27 | 2022-03-04 | 中国核电工程有限公司 | Reactor core auxiliary cooling system of passive reactor |
| CN108010591B (en) * | 2017-12-18 | 2024-01-19 | 中广核研究院有限公司 | Multifunctional pressure vessel pit stacking structure and reactor containment structure |
| CN111199806B (en) * | 2019-12-31 | 2022-04-19 | 中国核动力研究设计院 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
| CN111081395B (en) * | 2019-12-31 | 2022-05-20 | 中国核动力研究设计院 | Nuclear reactor heat insulation device capable of realizing heat radiation and heat dissipation |
| GB2606803A (en) * | 2020-01-07 | 2022-11-23 | China Nuclear Power Technology Res Inst Co Ltd | Safety system for handling severe accident of nuclear power plant and control method therefor |
| CN111933316B (en) * | 2020-08-12 | 2023-06-02 | 三门核电有限公司 | Method for efficiently cooling reactor cavity area of pressurized water reactor |
| CN112489824A (en) * | 2020-11-26 | 2021-03-12 | 中广核研究院有限公司 | Reactor cabin shielding device for compactly arranging small reactors |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
| CN114155983B (en) * | 2021-10-29 | 2024-09-06 | 中国核电工程有限公司 | Reactor model, reactor ventilation testing device and reactor ventilation testing method |
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| US5889830A (en) * | 1994-12-23 | 1999-03-30 | Siemens Aktiengesellschaft | Cooling system for cooling a containment chamber constructed for receiving a core melt |
| KR20140060768A (en) * | 2012-11-12 | 2014-05-21 | 한국수력원자력 주식회사 | Support structure for nuclear reactor |
| JP2014185989A (en) * | 2013-03-25 | 2014-10-02 | Hitachi-Ge Nuclear Energy Ltd | Core catcher |
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| US5699394A (en) * | 1995-07-13 | 1997-12-16 | Westinghouse Electric Corporation | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel |
| DE19846057B4 (en) * | 1998-10-07 | 2004-04-29 | Forschungszentrum Jülich GmbH | Device for cooling and protecting a reactor pressure vessel in the event of meltdowns |
| US8401142B2 (en) * | 2007-02-20 | 2013-03-19 | Westinghouse Electric Company Llc | Nuclear reactor vessel fuel thermal insulating barrier |
| FR2922678A1 (en) * | 2007-10-22 | 2009-04-24 | Commissariat Energie Atomique | NUCLEAR REACTOR WITH IMPROVED COOLING IN ACCIDENT CONDITIONS |
| FR2985844B1 (en) * | 2012-01-18 | 2014-03-14 | Dcns | IMMERSE ENERGY PRODUCTION MODULE |
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2015
- 2015-09-16 CN CN201510586928.7A patent/CN105280249B/en active Active
- 2015-12-14 GB GB1521982.7A patent/GB2542442B/en active Active
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5889830A (en) * | 1994-12-23 | 1999-03-30 | Siemens Aktiengesellschaft | Cooling system for cooling a containment chamber constructed for receiving a core melt |
| KR20140060768A (en) * | 2012-11-12 | 2014-05-21 | 한국수력원자력 주식회사 | Support structure for nuclear reactor |
| JP2014185989A (en) * | 2013-03-25 | 2014-10-02 | Hitachi-Ge Nuclear Energy Ltd | Core catcher |
Also Published As
| Publication number | Publication date |
|---|---|
| CN105280249A (en) | 2016-01-27 |
| GB201521982D0 (en) | 2016-01-27 |
| CN105280249B (en) | 2018-04-27 |
| GB2542442B (en) | 2019-07-10 |
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