WO2010134280A1 - 原子炉格納構造 - Google Patents
原子炉格納構造 Download PDFInfo
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- WO2010134280A1 WO2010134280A1 PCT/JP2010/003171 JP2010003171W WO2010134280A1 WO 2010134280 A1 WO2010134280 A1 WO 2010134280A1 JP 2010003171 W JP2010003171 W JP 2010003171W WO 2010134280 A1 WO2010134280 A1 WO 2010134280A1
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- WIPO (PCT)
- Prior art keywords
- reactor containment
- sump
- opening
- pool
- weir
- Prior art date
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Classifications
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- 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
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
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- 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
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- 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 reactor containment structure used for a pressurized water reactor.
- This application claims priority on May 20, 2009 based on Japanese Patent Application No. 2009-12296 for which it applied to Japan, and uses the content here.
- the primary coolant (light water) is pressurized so as not to boil.
- the primary coolant is heated with the thermal energy generated by the nuclear fission reaction, and the primary coolant that has reached a high temperature is sent to the steam generator.
- the secondary coolant (light water) is boiled and the turbine generator is rotated by high-temperature and high-pressure steam to generate electricity.
- This security structure mainly includes a reactor containment vessel and a pump device.
- the reactor containment vessel mainly includes a reactor containment chamber, a pool, and a sump.
- the reactor is stored in the reactor containment chamber.
- the pool is provided inside the reactor containment vessel and adjacent to the lower part of the reactor containment chamber, and stores the emergency coolant.
- the sump is located at the bottom of the pool.
- an opening for allowing the emergency coolant in the reactor containment chamber to flow into the pool is provided in the lower part of the reactor containment chamber.
- the pump device draws in the emergency coolant from the sump and discharges it from the upper part of the reactor containment chamber.
- the emergency coolant is sucked from the sump at the bottom of the pool by the pump device and discharged from the top of the reactor containment chamber.
- the discharged emergency coolant flows into the pool from the opening of the reactor containment chamber, is sucked again by the pump device, and circulates in the safety structure.
- the reactor containment structure disclosed in Patent Document 1 below includes a second sump that functions as a temporary storage tank for emergency cooling water at the opening of the floor of the reactor containment chamber.
- the 2nd screen is provided in the water outflow part from a 2nd sump to a pool.
- the debris is captured by the second screen so as not to flow into the pool, thereby suppressing the debris from adhering to the sump screen.
- the pressurized water reactor as described above has a problem that the second sump cannot be provided in all of the openings. That is, for example, the second sump as described above cannot be provided in the opening of the ascending / descending steps provided between the pool and the reactor containment chamber. It is also conceivable that this opening can be opened and closed. However, if the opening of the elevating staircase can be opened and closed, there is a problem that maintainability is lowered and the circulation efficiency of emergency cooling water is lowered.
- the present invention provides a reactor containment structure that can suppress the attachment of debris to a debris filter and can simplify the configuration of an opening.
- a reactor containment structure of the present invention comprises the following.
- a reactor containment chamber having a plurality of openings communicating with the lower floor in the lower part of the room where the nuclear reactor is stored, a sump pool in which the emergency coolant is stored, and a lower part of the sump pool.
- a reactor containment vessel with an integrated sump.
- a debris filter provided in the sump.
- a pump body that sucks the emergency coolant from the sump and discharges it from the upper part of the reactor containment chamber.
- the emergency coolant discharged from the upper part of the reactor containment chamber reflows into the sump pool from the opening of the reactor containment chamber, and the emergency containment Coolant circulates.
- the reactor containment structure of the present invention includes a weir for restricting a flow rate of the emergency coolant re-flowing from the opening into the sump pool at an opening closest to the sump among the plurality of openings. It is characterized by that. That is, in order to solve the above problems, the reactor containment structure of the present invention includes the following. Reactor containment vessel. A reactor containment chamber provided inside the reactor containment vessel and housing the reactor. A pool that is provided inside the reactor containment vessel and adjacent to the lower part of the reactor containment chamber and stores an emergency coolant. A plurality of openings through which the emergency coolant flows from the reactor containment chamber into the pool. A sump provided below the pool. A debris filter provided in the sump for filtering debris contained in the emergency coolant.
- a pump device that sucks the emergency coolant from the sump and discharges it into the reactor containment chamber.
- a weir that is provided at least in the opening closest to the sump among the plurality of openings and restricts the flow rate of the emergency coolant flowing into the pool from the reactor containment chamber.
- the flow rate of the emergency coolant flowing into the pool through the opening having the weir among the plurality of openings is limited. Therefore, the flow rate of the emergency coolant flowing into the pool from the opening having no weir increases.
- the opening without the weir is farther from the sump than the opening with the weir. Therefore, most of the emergency coolant discharged into the reactor containment chamber flows into the pool from a position farther away from the sump than before through an opening having no weir.
- route for which the emergency coolant which flowed into the pool moves to a sump is extended rather than before. Therefore, the debris contained in the emergency coolant that has flowed into the pool is more likely to settle than before in the middle of the sump.
- the debris contained in the emergency coolant is difficult to reach the debris filter. That is, by providing the weir, the flow rate of the emergency coolant in the opening through which the emergency coolant flows into a position where the debris easily reaches the debris filter body is limited. At the same time, the flow rate of the emergency cooling liquid at the opening through which the emergency cooling liquid flows into a position where the debris hardly reaches the debris filter is increased. Thereby, it becomes difficult for debris to reach the debris filter body than before, and debris reaching the debris filter body can be reduced. In addition, the weir captures debris at the opening closest to the sump. Therefore, it becomes difficult for debris to flow into the pool from the opening closest to the sump.
- the debris flowing into the pool is reduced, and it becomes difficult for the debris to reach the debris filter. Therefore, according to the containment structure of the present invention, the debris reaching the debris filter body can be suppressed, and the debris adhesion to the debris filter body can be suppressed. Further, the configuration can be simplified as compared with the case where a sump structure is provided in the opening or a sealing mechanism is provided. Therefore, debris can be prevented from adhering to the debris filter and the configuration of the opening can be simplified.
- the weir of one opening part near the said sump among arbitrary two openings may be higher than the weir of the other opening part away from the said sump. That is, among the plurality of openings having the weir, the height of the weir in the opening close to the sump may be higher than the height of the weir in the opening far from the sump. According to this configuration, the inflow amount distribution of the emergency coolant to the pool can be finely adjusted.
- the weir may gradually increase in thickness from the upper end toward the lower end. That is, the thickness of the weir may be gradually increased so that the lower portion is thicker than the upper portion.
- the weir may be configured integrally with the reactor containment vessel. That is, the weir may be provided integrally with the reactor containment vessel. According to these configurations, the strength of the weir can be increased. This prevents damage to the weir even when large debris collides or when a large fluid force acts from the emergency coolant. Therefore, even in such a case, adhesion of debris to the debris filter can be continuously suppressed.
- the nuclear reactor containment structure according to the present invention can suppress the adhesion of debris to the debris filter and can simplify the configuration of the opening.
- FIG. 2 is a cross-sectional view of a main part of the reactor containment structure 1 according to the first embodiment of the present invention, taken along the line II in FIG.
- FIG. 2 is a cross-sectional view of a main part of the reactor containment structure 1 according to the first embodiment of the present invention, taken along the line II-II in FIG.
- FIG. 1 is a schematic configuration diagram of a reactor containment structure 1 according to a first embodiment of the present invention.
- 2 is a cross-sectional view taken along the line II in FIG. 3 is a cross-sectional view taken along line II-II in FIG.
- the reactor containment structure 1 includes a reactor containment vessel 10 that houses a nuclear reactor 5, and a circulation pump (pump body, pump device) 20.
- the nuclear reactor containment vessel 10 includes a nuclear reactor containment chamber 11 for storing the nuclear reactor 5 and a pool (sump pool) 12 in which emergency cooling water (emergency cooling liquid) W is stored.
- the reactor containment chamber 11 is provided inside the reactor containment vessel 10.
- the reactor containment chamber 11 stores a steam generator and a pressurizer (not shown) together with the reactor 5.
- rectangular openings 11 b and 11 c communicating with the lower floor are provided in the floor 11 a of the reactor containment chamber 11.
- the weir 30 provided in the opening 11b will be described later.
- the pool 12 is provided inside the nuclear reactor containment vessel 10 adjacent to the lower part of the nuclear reactor containment chamber 11, and stores the emergency cooling water W. That is, the pool 12 is provided on the lower floor of the reactor containment vessel 10, specifically, on the basement floor of the reactor containment vessel 10.
- a circulation sump (sump, suction part) 13 is provided below the bottom 12 a of the pool 12.
- the circulation sump 13 is provided one step lower than the bottom 12 a of the pool 12.
- the circulation sump 13 is provided with a sump screen (debris filter body) 14 for filtering debris such as damaged matters contained in the emergency cooling water W.
- the sump screen 14 is provided so as to cover the opening of the circulation sump 13.
- the sump screen 14 is formed in a box shape with one surface open.
- the sump screen 14 is installed so that the opened side is overlaid on the opening of the circulation sump 13. That is, the sub-screen 14 covers the opening of the circulation sump 13 with the bottom facing upward and the opening facing downward. Further, as shown in FIG. 1, the sump screen 14 is entirely submerged in order to effectively use the entire area for capturing the damaged object.
- a debris filter body in which plate members having through holes are stacked in multiple stages may be used.
- the circulation pump 20 is connected to one end of the suction side pipe 20a.
- the other end of the suction side pipe 20 a is connected to the circulation sump 13 and opens to the circulation sump 13.
- the circulation pump 20 is connected to the discharge side pipe 20b.
- the discharge side pipe 20 b is connected to a spray nozzle 20 c disposed in the upper part 11 f of the reactor containment chamber 11.
- the reactor containment structure 1 operates the circulation pump 20 when a primary coolant loss accident such as a breakage of the piping portion 5a of the reactor 5 occurs.
- the circulation pump 20 sucks the emergency cooling water W stored in the pool 12 from the circulation sump 13.
- the circulation pump 20 discharges the sucked emergency cooling water W from a spray nozzle 20 c provided in the upper part 11 f of the reactor containment chamber 11.
- the circulation pump 20 discharges the emergency cooling water W from the spray nozzle 20 c and supplies it to the nuclear reactor 5 to cool the nuclear reactor 5.
- the emergency cooling water W that has cooled the nuclear reactor 5 and has flowed down to the floor portion 11a flows into the pool 12 through the openings 11b and 11c.
- the reactor containment structure 1 circulates the emergency cooling water W in the pool 12.
- FIG. 4 is an enlarged cross-sectional view of a main part of the reactor containment structure 1.
- the reactor containment structure 1 includes a weir 30 as shown in FIG.
- the weir 30 is provided so as to protrude upward from the floor portion 11a.
- the weir 30 restricts the flow rate of the emergency cooling water W flowing into the pool 12 from the opening 11b.
- the weir 30 is provided at the edge of the opening 11b closest to the circulation sump 13 among the plurality of openings 11b and 11c.
- the weir 30 is not provided in the opening 11c that is further away from the circulation sump 13 than the opening 11b.
- the weir 30 is formed in a rectangular shape along the edge of the opening 11 b.
- the weir 30 is provided around the opening 11b and surrounds the opening 11b.
- the vertical cross-sectional shape of the weir 30 is a rectangle.
- the weir 30 has substantially the same horizontal thickness in the vertical direction from the upper end 30a to the lower end 30b.
- the circulation pump 20 shown in FIG. 1 operates and sucks the emergency cooling water W from the circulation sump 13.
- the circulation pump 20 discharges the sucked emergency cooling water W from the spray nozzle 20 c provided in the upper part 11 f of the reactor containment chamber 11 and supplies it to the reactor 5.
- the emergency cooling water W supplied to the nuclear reactor 5 flows down to the floor 12a after cooling the nuclear reactor 5.
- the emergency cooling water W that has flowed down to the floor 12a flows into the pool 12 from the opening 11c (arrow A).
- the debris D scattered on the floor portion 12 a is flowed by the emergency cooling water W and flows into the pool 12 together with the emergency cooling water W.
- the emergency cooling water W is blocked by the weir 30. Thereby, inflow of the emergency cooling water W from the opening 11b to the pool 12 is temporarily inhibited.
- the emergency cooling water W is stored on the floor 11a. It will be done. Thereby, the water level of the emergency cooling water W from the floor part 11a rises. Eventually, the level of the emergency cooling water W from the floor portion 11a becomes higher than the height from the lower end 30b to the upper end 30a of the weir 30. Then, as shown in FIG. 6, the emergency cooling water W flows over the weir 30. The emergency cooling water W over the weir 30 flows into the pool 12 from the opening 11b (arrow B). At this time, the dam 30 continues to dam the debris D (FIG.
- the reactor containment structure 1 has the weir that restricts the flow rate of the emergency cooling water W flowing into the pool 12 into the opening 11b closest to the circulation sump 13 out of the two openings 11b and 11c. 30. Therefore, the flow rate of the emergency cooling water W flowing into the pool 12 from the opening 11c where the weir 30 is not provided increases.
- the opening 11c where the weir 30 is not provided is further away from the circulation sump 13 than the opening 11b where the weir 30 is provided. Therefore, the debris D that has flowed into the opening 11 c where the weir 30 is not provided flows into a position away from the circulation sump 13 of the pool 12.
- the debris D that has flowed into the pool 12 from the opening portion 11 c where the weir 30 is not provided is likely to sink to the floor portion 12 b of the pool 12 on the way to the circulation sump 13 from the flow-in position. Therefore, the debris D that has flowed into the pool 12 from the opening 11 c where the weir 30 is not provided does not easily reach the screen 14.
- the debris D when the debris D flows into the pool 12 from the opening 11b close to the circulation sump 13, the debris D often reaches the screen 14 before settling on the floor 12a of the pool 12. Therefore, the debris D that has flowed into the pool 12 from the opening 11 b close to the circulation sump 13 tends to adhere to the screen 14.
- the weir 30 restricts the flow rate of the emergency cooling water W that flows into the opening 11 b that allows the passed debris D to easily reach the screen 14. At the same time, the weir 30 increases the flow rate of the emergency cooling water W that flows into the opening 11 c where it is difficult for the passed debris D to reach the screen 14. Therefore, most of the debris D flowing into the pool 12 can be settled, and the debris D reaching the screen 14 can be reduced.
- the weir 30 captures the debris D at the opening 11b closest to the circulation sump 13. Therefore, it becomes difficult for the debris D to flow in from the opening 11b, and it becomes difficult for the debris D to reach the screen 14. Therefore, according to the reactor containment structure 1, the debris D that reaches the screen 14 can be reduced, and adhesion of the debris D to the screen 14 can be suppressed.
- the configuration can be simplified without providing a sump structure or a sealing mechanism in the openings 11b and 11c. Therefore, according to the reactor containment structure 1, it is possible to suppress the adhesion of the debris D to the screen 14 and to simplify the configuration of the openings 11b and 11c.
- FIG. 7 is an enlarged cross-sectional view of a dam 31 that is a modification of the dam 30 described above.
- the weir 31 is different from the weir 30 described above in that the thickness in the horizontal direction gradually increases from the upper end 31 a toward the lower end 31 b. Since the weir 31 of the modified example becomes thicker in the horizontal direction as it approaches the lower end 31b, the stress generated with respect to the load in the horizontal direction along the floor portion 11a becomes smaller as it approaches the lower end 31b. A large debris D may collide with the weir 31, or a large fluid force may act on the weir 31 from the emergency coolant W. According to the present modification, even in such a case, damage to the weir 31 can be prevented and adhesion of debris D to the sump screen 14 can be continuously suppressed.
- FIG. 8 is an enlarged cross-sectional view of the main part of the reactor containment structure 2 according to the second embodiment of the present invention.
- the same components as those in FIGS. 1 to 7 are denoted by the same reference numerals, and description thereof is omitted.
- the reactor containment structure 2 includes a weir 30 provided in the opening 11b closest to the circulation sump 13, and a weir 32 provided in the opening 11c that is further away from the circulation sump 13 than the opening 11b. .
- the weir 32 is formed in a rectangular shape along the edge of the opening 11c.
- the weir 32 is provided around the opening 11c and surrounds the opening 11c.
- the vertical cross-sectional shape of the weir 32 is rectangular as shown in FIG.
- the weir 32 has substantially the same horizontal thickness from the upper end 32a to the lower end 32b.
- the height from the lower end 32b of the weir 32 provided at the opening 11c spaced from the circulation sump 13 to the upper end 32a is the height from the lower end 30b of the weir 30 provided at the opening 11b close to the circulation sump 13 to the upper end 30a. Lower than that. Further, when the circulation of the emergency cooling water W becomes stable and steady, the water level from the floor portion 11a to the water surface of the emergency cooling water W becomes substantially constant.
- the weirs 30 and 32 are set so that the distances h1 and h2 from the upper ends 30a and 32a to the water surface of the emergency cooling water W in the steady state have predetermined values.
- the emergency cooling water W flows over the weirs 30 and 31 into the openings 11 b and 11 c and into the pool 12.
- the weirs 30 and 32 keep damming the debris D (FIG. 6) located below the upper ends 30a and 32a of the weirs 30 and 32, respectively. Therefore, the debris D is prevented from flowing into the pool 12 from the openings 11b and 11c, and the adhesion of the debris D to the screen 14 is suppressed.
- the flow rate of the emergency coolant W flowing into the opening 11c is larger than the flow rate of the emergency coolant W flowing into the opening 11b.
- the flow rate of the emergency cooling water W flowing into the openings 11b and 11c is proportional to the 1.5th power of the distances h1 and h2. That is, the flow rate of the emergency cooling water W flowing into the opening portion 11c is proportional to the 1.5th power of the difference between the distance h1 and the distance h2, rather than the flow rate of the emergency cooling water W flowing into the opening portion 11b.
- the flow rate of the emergency cooling water W that flows into the opening portion 11b in which the debris D contained in the emergency cooling water W easily reaches the screen 14 is reduced as compared with the conventional case. Therefore, the amount of debris D that flows into the pool 12 through the opening 11b is reduced.
- the flow rate of the emergency cooling water W that flows into the opening 11c in which the debris D contained in the emergency cooling water W is difficult to reach the screen 14 is increased as compared with the conventional case. Therefore, the debris D flowing into the pool 12 from the opening 11c increases. Most of the debris D that has flowed into the pool 12 from the opening 11 c sinks on the way to the circulation sump 13.
- the debris D hardly reaches the sump screen 14 and hardly adheres to the sump screen 14. Therefore, an increase in the load of the circulation pump 20 is suppressed, and a decrease in the circulation efficiency of the emergency cooling water W is suppressed. Thereby, the emergency cooling water W is circulated efficiently, and the safety of the nuclear reactor 5 is maintained well.
- the height of the weir 30 of the opening 11 b close to the circulation sump 13 out of the two openings 11 b and 11 c is the opening 11 c away from the circulation sump 13.
- the height of the weir 32 is higher. Therefore, as in the first embodiment, the flow rate of the emergency cooling water W flowing into the opening 11c away from the circulation sump 13 increases, and the emergency cooling liquid W flowing into the opening 11b near the circulation sump 13 increases. The flow rate decreases. Therefore, according to the reactor containment structure 2 of this embodiment, the same effect as the reactor containment structure 1 in the first embodiment described above can be obtained.
- the heights of the weirs 30 and 32 are different. Therefore, the flow rate of the emergency coolant W flowing into the openings 11b and 11c is adjusted by the weirs 30 and 32. Therefore, the distribution of the inflow amount of the emergency cooling water W to the pool 12 can be adjusted.
- the reactor containment chamber 11 having two openings 11b and 11c has been described, but three or more openings may be provided. At this time, there may be an opening without a weir. Moreover, if the height of the weir of one opening part close
- the weir 30 surrounds the opening 11b.
- the opening may be surrounded by the wall and the dam when the opening is formed in the vicinity of another structure such as a wall. That is, it is not always necessary to surround the opening with only the weir.
- the present invention includes a nuclear reactor containment vessel, a nuclear reactor containment chamber that is provided inside the nuclear reactor containment vessel and stores the nuclear reactor, and is adjacent to the interior of the nuclear reactor containment vessel below the nuclear reactor containment chamber.
- a debris filter that is provided in the sump and filters debris contained in the emergency coolant; a pump device that sucks the emergency coolant from the sump and discharges it into the reactor containment chamber;
- a weir that is provided at least in the opening closest to the sump and restricts the flow rate of the emergency coolant flowing into the pool from the opening.
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Abstract
Description
本願は、2009年5月20日に、日本に出願された特願2009-122496号に基づき優先権を主張し、その内容をここに援用する。
原子炉格納容器は、主に、原子炉格納室と、プールと、サンプとを備えている。原子炉格納室には、原子炉が格納される。プールは、原子炉格納容器の内部に、原子炉格納室の下方に隣接して設けられ、非常用冷却液が貯留される。サンプは、プールの下部に設けられている。また、原子炉格納室の下部には、原子炉格納室内の非常用冷却液をプールに流入させる開口部が設けられている。
ポンプ装置は、サンプから非常用冷却液を吸い込んで、原子炉格納室の上部から吐出する。
上記の保安構造において、非常用冷却液は、ポンプ装置によってプールの下部のサンプから吸い込まれ、原子炉格納室の上部から吐出される。吐出された非常用冷却液は、原子炉格納室の開口部からプールに流入し、再びポンプ装置によって吸い込まれ、保安構造内で循環する。
原子炉が格納された室内下部において下階に連通する複数の開口部を有する原子炉格納室と前記下階に設けられ、非常用冷却液が貯留されたサンププールと前記サンププールの下部に設けられたサンプとを備える原子炉格納容器。
前記サンプに設けられたデブリ濾過体。
前記サンプから前記非常用冷却液を吸い込んで前記原子炉格納室の上部から吐出するポンプ体。
以上の構成を備える原子炉格納構造においては、前記原子炉格納室の上部から吐出された前記非常用冷却液が、前記原子炉格納室の開口部から前記サンププールに再流入し、前記非常用冷却液が循環する。
本発明の原子炉格納構造は、前記複数の開口部のうち、前記サンプに最も近い開口部に、該開口部から前記サンププールに再流入する前記非常用冷却液の流量を制限する堰を備えることを特徴とする。
すなわち、上記の課題を解決するために、本発明の原子炉格納構造は、次を備える。
原子炉格納容器。
前記原子炉格納容器の内部に設けられ、原子炉を格納する原子炉格納室。
前記原子炉格納容器の内部に、前記原子炉格納室の下方に隣接して設けられ、非常用冷却液が貯留されるプール。
前記非常用冷却液を前記原子炉格納室から前記プールへ流入させる複数の開口部。
前記プールの下方に設けられたサンプ。
前記サンプに設けられ、前記非常用冷却液に含まれるデブリを濾過するデブリ濾過体。
前記非常用冷却液を前記サンプから吸い込んで前記原子炉格納室の内部に吐出するポンプ装置。
前記複数の開口部のうち、少なくとも前記サンプに最も近い開口部に設けられ、前記原子炉格納室から前記プールに流入する前記非常用冷却液の流量を制限する堰。
すなわち、堰を設けることで、デブリがデブリ濾過体に到達し易い位置に非常用冷却液を流入させる開口部の非常用冷却液の流量を制限する。同時に、デブリがデブリ濾過体に到達し難い位置に非常用冷却液を流入させる開口部の非常用冷却液の流量を増加させる。これにより、従来よりもデブリがデブリ濾過体に到達し難くなり、デブリ濾過体に到達するデブリを減少させることができる。
また、サンプに最も近い開口部においては、堰がデブリを捕捉する。そのため、サンプに最も近い開口部からプールへデブリが流入し難くなる。よって、プールに流入するデブリが減少し、デブリがデブリ濾過体に到達し難くなる。
従って、本発明の原子炉格納構造によれば、デブリ濾過体に到達するデブリを抑制して、デブリ濾過体へのデブリの付着を抑制できる。また、開口部にサンプ構造を設けたり、封止機構を設けたりするよりも、構成を簡略化できる。よって、デブリ濾過体にデブリが付着することを抑止すると共に、開口部の構成を簡略化できる。
すなわち、前記堰は、前記複数の開口部のうち、二以上の開口部に設けられていてもよい。
この構成によれば、サンプの位置関係を考慮して、開口部の流量を調整することができる。換言すれば、プールへの非常用冷却材の流入量分布を調整することができる。
また、各々の堰がデブリを捕捉するので、プールに流入するデブリを従来よりも減少させることができる。
すなわち、前記堰を有する複数の前記開口部のうち、前記サンプに近い前記開口部の前記堰の高さが、前記サンプから遠い前記開口部の前記堰の高さよりも高くてもよい。
この構成によれば、プールへの非常用冷却材の流入量分布を微調整をすることができる。
すなわち、前記堰の厚みは、上方よりも下方が厚くなるように、漸次厚くなってもよい。
また、前記堰は、前記原子炉格納容器と一体に構成されてもよい。
すなわち、前記堰は、前記原子炉格納容器と一体的に設けられてもよい。
これら構成によれば、堰の強度を大きくすることができる。これにより、大型のデブリが衝突した場合や、非常用冷却液から大きな流体力が作用した場合であっても、堰の破損を防止できる。従って、このような場合でも、デブリ濾過体へのデブリの付着を継続して抑制できる。
図1は、本発明の第一実施形態に係る原子炉格納構造1の概略構成図である。図2は、図1におけるI-I線断面図である。図3は、図1におけるII-II線断面図である。
図1に示すように、原子炉格納構造1は、原子炉5を格納する原子炉格納容器10と、循環ポンプ(ポンプ体、ポンプ装置)20とを備えている。
原子炉格納室11は、原子炉格納容器10の内部に設けられている。原子炉格納室11には、原子炉5と共に、不図示の蒸気発生器や加圧器等が格納されている。原子炉格納室11の床部11aには、図1及び図2に示すように、下階へと連通する矩形状の開口部11b,11cが設けられている。
開口部11bに設けられた堰30については後述する。
図1及び図3に示すように、プール12の底部12aの下方には、循環サンプ(サンプ、吸込部)13が設けられている。循環サンプ13は、プール12の底部12aよりも一段低く設けられている。循環サンプ13には、非常用冷却水Wに含まれる破損物などのデブリを濾過するサンプスクリーン(デブリ濾過体)14が設けられている。サンプスクリーン14は、循環サンプ13の開口部を覆うように設けられている。
なお、サンプスクリーン14に代えて、貫通孔を有するプレート部材を多段に積み重ねたデブリ濾過体を用いてもよい。
原子炉5を冷却し、床部11aに流れ落ちた非常用冷却水Wは、開口部11b,11cからプール12に流入する。以上のように、原子炉格納構造1は、プール12の非常用冷却水Wを循環させる。
原子炉格納構造1は、図4に示すように、堰30を備えている。堰30は、床部11aから上方に突出するように設けられている。堰30は、開口部11bからプール12に流入する非常用冷却水Wの流量を制限する。
一次冷却材の喪失事故が発生すると、高圧の一次冷却材の噴出によって、図5に示すような断熱材片や金属片を含むデブリDが原子炉格納室11に飛散する。
このとき、図1に示す循環ポンプ20が作動して、循環サンプ13から非常用冷却水Wを吸い込む。循環ポンプ20は、吸い込んだ非常用冷却水Wを原子炉格納室11の上部11fに設けられたスプレイノズル20cから吐出して、原子炉5に供給する。原子炉5に供給された非常用冷却水Wは、原子炉5を冷却した後に床部12aに流れ落ちる。
一方、循環サンプ13に最も近い開口部11bにおいては、堰30によって非常用冷却水Wが堰き止められる。これにより、開口部11bからプール12への非常用冷却水Wの流入が一時的に阻害される。
開口部11cからプール12に流入する非常用冷却水Wと共にプール12に流入したデブリDは、図6に示すように、着水の衝撃により、プール12内で舞い上がるように流れる。その後、プール12内のデブリDは、非常用冷却水Wが循環サンプ13まで流れていく過程で沈降し、プール12の床部12aに堆積する。すなわち、デブリDは、プール12における非常用冷却水Wの流路の下流に進むに従って、漸次床部12aに堆積していく。これにより、スクリーン14に到達するデブリDが減少する。
この際、堰30は、堰30の上端30aより下方に位置するデブリD(図6)を堰き止め続ける。そのため、循環サンプ13に最も近い開口部11bからプール12へのデブリDの流入が抑制される。これにより、デブリDのスクリーン14への付着が抑制される。
堰30が設けられていない開口部11cは、堰30が設けられた開口部11bよりも循環サンプ13から離間している。そのため、堰30が設けられていない開口部11cに流入したデブリDは、プール12の循環サンプ13から離間した位置に流入する。そのため、堰30が設けられていない開口部11cからプール12へ流入したデブリDは、流入した位置から循環サンプ13に向かう途中でプール12の床部12bに沈降し易い。従って、堰30が設けられていない開口部11cからプール12へ流入したデブリDは、スクリーン14に到達し難い。反対に、循環サンプ13に近い開口部11bからプール12へデブリDが流入すると、デブリDがプール12の床部12aに沈降して堆積する前に、スクリーン14に到達してしまうことが多い。従って、循環サンプ13に近い開口部11bからプール12へ流入したデブリDは、スクリーン14に付着し易い。
本実施形態では、通過させたデブリDをスクリーン14に到達させ易い開口部11bに流入する非常用冷却水Wの流量を、堰30によって制限している。同時に、通過させたデブリDをスクリーン14に到達させ難い開口部11cに流入する非常用冷却水Wの流量を、堰30によって増加させている。従って、プール12に流入するデブリDの多くを沈降させ、スクリーン14に到達するデブリDを減少させることができる。
従って、原子炉格納構造1によれば、スクリーン14に到達するデブリDを減少させて、スクリーン14へのデブリDの付着を抑制することができる。
よって、原子炉格納構造1によれば、スクリーン14へのデブリDの付着を抑止すると共に、開口部11b,11cの構成を簡略化できる。
図7に示すように、堰31は、上端31aから下端31bに向かうに従って、水平方向の厚みが漸次厚くなっている点が、上述した堰30と相違する。
変形例の堰31は、下端31bに近づくにつれて水平方向の厚みが厚くなっているので、下端31bに近づくにつれて床部11aに沿った水平方向の荷重に対して発生する応力が小さくなる。堰31には、大型のデブリDが衝突する場合や、非常用冷却液Wから堰31に大きな流体力が作用する場合がある。本変形例によれば、このような場合であっても、堰31の破損を防止し、サンプスクリーン14へのデブリDの付着を継続して抑制することができる。
堰32は、図2に示す堰30と同様に、開口部11cの縁部に沿って矩形状に形成されている。堰32は、開口部11cの周囲に設けられ、開口部11cを囲繞している。この堰32の縦断面形状は、図4に示すように、矩形である。堰32は、上端32aから下端32bまでの水平方向の厚みが略同一である。
また、非常用冷却水Wの循環が安定して定常状態になると、床部11aから非常用冷却水Wの水面までの水位は略一定になる。堰30,32は、上端30a,32aから、この定常状態における非常用冷却水Wの水面までの距離h1,h2が、所定の値になるように設定されている。
この際、堰30,32は、堰30,32の上端30a,32aより下方に位置するデブリD(図6)をそれぞれ堰き止め続ける。そのため、デブリDが開口部11b,11cからプール12へ流入するのを抑制し、デブリDのスクリーン14への付着が抑制される。
一方、非常用冷却水Wに含まれるデブリDをスクリーン14に到達させ難い開口部11cに流入する非常用冷却水Wの流量は、従来よりも増加する。そのため、開口部11cからプール12へ流入するデブリDが多くなる。開口部11cからプール12へ流入したデブリDの多くは、循環サンプ13に向かう途中で沈降する。
例えば、上述した実施形態では、堰30が開口部11bを囲繞するようにした。しかし、堰は、例えば壁部などの他の構造体の近傍に開口部が形成されている場合には、開口部を壁部と堰とによりに囲繞してもよい。すなわち、必ずしも堰のみで開口部を囲繞する必要はない。
5…原子炉
10…原子炉格納容器
11…原子炉格納室
11a…床部
11b~11d…開口部
11f…上部
12…プール
13…循環サンプ(吸込部)
14…サンプスクリーン(デブリ濾過体)
20…循環ポンプ(ポンプ体、ポンプ装置)
W…非常用冷却水(非常用冷却液)
Claims (5)
- 原子炉格納容器と、
前記原子炉格納容器の内部に設けられ、原子炉を格納する原子炉格納室と、
前記原子炉格納容器の内部に、前記原子炉格納室の下方に隣接して設けられ、非常用冷却液が貯留されるプールと、
前記非常用冷却液を前記原子炉格納室から前記プールへ流入させる複数の開口部と、
前記プールの下方に設けられたサンプと、
前記サンプに設けられ、前記非常用冷却液に含まれるデブリを濾過するデブリ濾過体と、
前記非常用冷却液を前記サンプから吸い込んで前記原子炉格納室の内部に吐出するポンプ装置と、
前記複数の開口部のうち、少なくとも前記サンプに最も近い開口部に設けられ、該開口部から前記プールに流入する前記非常用冷却液の流量を制限する堰と、
を備える原子炉格納構造。 - 前記堰は、前記複数の開口部のうち、二以上の開口部に設けられている請求項1に記載の原子炉格納構造。
- 前記堰を有する前記開口部のうち、前記サンプに近い前記開口部の前記堰の高さが、前記サンプから離れた前記開口部の堰の高さよりも高い請求項2に記載の原子炉格納構造。
- 前記堰の厚みは、上方よりも下方が厚くなるように、漸次厚くなっている請求項1から3のいずれか一項に記載の原子炉格納構造。
- 前記堰は、前記原子炉格納容器と一体的に設けられている請求項1から4のいずれか一項に記載の原子炉格納構造。
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KR1020117027411A KR20120012472A (ko) | 2009-05-20 | 2010-05-10 | 원자로 격납 구조체 |
CA2761517A CA2761517A1 (en) | 2009-05-20 | 2010-05-10 | Reactor containment structure |
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US20130028365A1 (en) * | 2011-07-29 | 2013-01-31 | Westinghouse Electric Company Llc | Power generation from decay heat for spent nuclear fuel pool cooling and monitoring |
JP6037633B2 (ja) * | 2012-03-23 | 2016-12-07 | 三菱重工業株式会社 | サンプスクリーン及びサンプスクリーンの施工方法 |
JP6655292B2 (ja) * | 2015-02-04 | 2020-02-26 | 三菱重工業株式会社 | 原子炉格納構造 |
JP6680954B2 (ja) * | 2016-10-10 | 2020-04-15 | イリノイ トゥール ワークス インコーポレイティド | サンプル作製ソー |
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JPS5467883A (en) * | 1977-11-11 | 1979-05-31 | Hitachi Ltd | Reactor |
JPS62137586A (ja) * | 1985-12-11 | 1987-06-20 | 株式会社東芝 | 原子炉格納容器 |
JPH02122300A (ja) * | 1988-11-01 | 1990-05-09 | Toshiba Corp | 原子炉格納容器 |
JPH07260977A (ja) * | 1994-03-18 | 1995-10-13 | Mitsubishi Heavy Ind Ltd | 燃料取替用水ピットにおける再循環サンプ構造 |
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- 2009-05-20 JP JP2009122496A patent/JP2010271148A/ja not_active Withdrawn
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2010
- 2010-05-10 CA CA2761517A patent/CA2761517A1/en not_active Abandoned
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- 2010-05-10 KR KR1020117027411A patent/KR20120012472A/ko active IP Right Grant
- 2010-05-10 EP EP10777520A patent/EP2434495A1/en not_active Withdrawn
- 2010-05-10 US US13/319,155 patent/US20120051486A1/en not_active Abandoned
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JPS5435588A (en) * | 1977-08-24 | 1979-03-15 | Toshiba Corp | Reacore container |
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WO2012145020A1 (en) * | 2011-04-21 | 2012-10-26 | Performance Contracting, Inc. | Multimodal debris trap |
US9741458B2 (en) | 2011-04-21 | 2017-08-22 | Performance Contracting, Inc. | Multimodal debris trap |
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US20120051486A1 (en) | 2012-03-01 |
CA2761517A1 (en) | 2010-11-25 |
KR20120012472A (ko) | 2012-02-10 |
EP2434495A1 (en) | 2012-03-28 |
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