CN112037943B - Hydraulic suspension split type passive shutdown assembly for fast neutron reactor - Google Patents
Hydraulic suspension split type passive shutdown assembly for fast neutron reactor Download PDFInfo
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- CN112037943B CN112037943B CN202010737630.2A CN202010737630A CN112037943B CN 112037943 B CN112037943 B CN 112037943B CN 202010737630 A CN202010737630 A CN 202010737630A CN 112037943 B CN112037943 B CN 112037943B
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- core rod
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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
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
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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
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- General Engineering & Computer Science (AREA)
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Abstract
The invention relates to a hydraulic suspension split type passive shutdown assembly for a fast neutron reactor, which comprises a movable core rod and an assembly sleeve matched with the movable core rod, wherein one end of the movable core rod is inserted into the assembly sleeve, an absorber rod bundle is arranged inside the movable core rod, a coolant inlet hole is arranged at the end part of the movable core rod extending into the assembly sleeve, and a coolant outlet hole group is arranged at the middle position of the peripheral surface of the movable core rod and the position far away from the end part of the coolant inlet hole; the assembly sleeve comprises a guide pipe, an outer sleeve and a pin, a pin inlet is formed in the pin, the pin inlet is communicated with the guide pipe, one end of the guide pipe is opened, the movable core rod is inserted into the guide pipe from the opening, and a gap annular cavity is formed between the inner wall of the guide pipe and the outer wall of the movable core rod. The passive safety device is designed according to a passive concept, does not need any trigger signal or external force drive, greatly reduces the failure probability, and can practically improve the safety of the nuclear power plant.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a hydraulic suspension split type passive shutdown assembly for a fast neutron reactor.
Background
In the case of a power source failure/protection system failure, there is a possibility that the nuclear power plant may not be protected in time. Taking a traditional control rod assembly in a sodium-cooled fast reactor as an example, the control rod assembly consists of an assembly sleeve and a core rod which can move up and down in the assembly sleeve, and the core rod moves up and down through the matching of a driving mechanism; during the operation of the reactor, the core rod is held by the gripper of the driving mechanism, and the core rod needs to be inserted into the reactor core under the action of the driving mechanism to realize shutdown.
In the sodium-cooled fast reactor, the most typical core cooling system failure or damage accident is a current loss accident, and the hydraulic suspension split type passive reactor-stopping assembly (hereinafter, referred to as a split type passive reactor-stopping assembly) is a control rod assembly for relieving the current loss accident consequence of the fast reactor, so that the safety of the reactor can be improved, and the capability of the fast reactor for dealing with the current loss accident is improved. The main working principle is as follows: before the reactor is used for increasing power, the core rod is lifted to a high working position by using the driving mechanism, then the flow of the coolant is increased, when the hydraulic thrust of the coolant is greater than the weight of the core rod, the gripper of the driving mechanism releases the core rod, and the core rod is suspended at the high working position under the action of the hydraulic thrust of the coolant; when a flow loss accident occurs, the reduction of the coolant flow enables the hydraulic thrust of the coolant to be smaller than the weight of the core rod, and the core rod falls freely under the action of the gravity and is inserted into a reactor core to realize shutdown. However, no specific practical research and application experience of the split type passive shutdown assembly exists at present.
Disclosure of Invention
The invention aims to solve the defects in the prior art and provides a hydraulic suspension split type passive reactor shutdown assembly for a fast neutron reactor.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a hydraulic suspension split type passive shutdown assembly for a fast neutron reactor comprises a movable core rod and an assembly sleeve matched with the movable core rod, wherein one end of the movable core rod is inserted into the assembly sleeve, an absorber rod bundle is arranged inside the movable core rod, a coolant inlet hole is formed in the end part of the movable core rod extending into the assembly sleeve, and a coolant outlet hole group is arranged in the middle of the periphery of the movable core rod and far away from the end part of the coolant inlet hole;
the assembly sleeve comprises a guide pipe, an outer sleeve and a pin, a pin inlet is formed in the pin, the pin inlet is communicated with the guide pipe, one end of the guide pipe is open, the movable core rod is inserted into the guide pipe from the opening, and a gap annular cavity is formed between the inner wall of the guide pipe and the outer wall of the movable core rod.
Further, the gap annular cavity extends to the end opening of the guide pipe.
Further, the coolant outlet hole group comprises a plurality of coolant outlet holes which are annularly arranged, and the coolant outlet holes are communicated with the inner cavity of the movable core rod.
Further, the end of the moving mandrel carries an operating head.
Further, the movable core rod and the assembly sleeve are longitudinally arranged, and the central lines of the movable core rod and the assembly sleeve are overlapped.
Further, the caliber of a coolant outlet hole at the top of the movable core rod is larger than that of a coolant outlet hole at the middle of the movable core rod, and the caliber of the coolant outlet hole at the middle of the movable core rod is larger than that of a coolant inlet hole at the bottom of the movable core rod.
Furthermore, the number of the coolant outlet holes of the coolant outlet hole group is generally 6-12, the coolant outlet hole in the middle of the moving core rod is a connecting hole, and the coolant outlet hole in the top of the moving core rod is an outlet hole.
Furthermore, the coolant enters the guide pipe of the assembly sleeve from the pin inlet and flows from bottom to top, the coolant forms a shunt when passing through the coolant inlet hole at the lowest end of the moving core rod, one part of the coolant enters the cooling absorber rod bundle in the moving core rod and flows out from the coolant outlet hole at the middle position and the coolant outlet hole at the highest end of the moving core rod, and the other part of the coolant flows in a gap annular cavity between the moving core rod and the guide pipe and finally flows out.
Furthermore, the diameter of a coolant inlet hole at the lowermost end of the movable core rod is small, the coolant flows through the coolant inlet hole to form large resistance, the flow entering the interior of the movable core rod is small, and most of the coolant flows out from a gap annular cavity on the outer side of the movable core rod; the coolant generates great on-way resistance when flowing through the slit annular cavity, the moving core rod generates great pressure difference under the condition of small liquid flow, and the moving core rod is subjected to upward hydraulic lifting force, so that the moving core rod is suspended at an upper station under a certain flow.
Further, when the liquid lifting force just enables the moving core rod to be in a suspension state, the corresponding flow rate is critical flow rate, when the flow rate of the coolant of the reactor core is reduced due to a flow loss accident, the hydraulic lifting force is reduced, when the flow rate is reduced to be below the critical flow rate, the hydraulic lifting force is smaller than the gravity of the moving core rod, the moving core rod starts to fall down and finally is kept at a lower station, the coolant forms a secondary flow distribution before the coolant passes through a coolant inlet hole at the lowest end of the moving core rod, when the moving core rod is located at the lower station, a coolant outlet hole in the middle position of the moving core rod falls below the annular gap cavity, the coolant outside the moving core rod forms a secondary flow distribution before the coolant is led out of the annular gap cavity, the flow rate of the coolant entering the annular gap cavity at the lower station is reduced, the pressure drop of the moving core rod at the lower station is reduced, and the moving core rod can be hydraulically self-tightened at the lower station.
The beneficial effects of the invention are as follows: when the device is used, a coolant enters the guide pipe of the assembly sleeve from the pin inlet and flows from bottom to top, the coolant forms a shunt when passing through the coolant inlet hole at the lowest end of the movable core rod, one part of the coolant enters the coolant bundle in the movable core rod and flows out from the coolant outlet hole at the middle position and the coolant outlet hole at the highest end of the movable core rod, the other part of the coolant flows in the gap annular cavity between the movable core rod and the guide pipe and finally flows out, and the critical flow of the movable core rod suspended at the upper station can be reduced under the condition of meeting the heat exchange requirement of the absorber rod through the matching of the gap annular cavity with proper size and each small hole, so that the influence of the split type passive reactor stopping assembly on the whole reactor core is reduced;
the passive safety device is designed according to a passive concept, does not need any trigger signal or external force drive, greatly reduces the failure probability, and can practically improve the safety of the nuclear power plant.
Drawings
FIG. 1 is a schematic view of a moving core rod according to the present invention;
FIG. 2 is a schematic view of the construction of the cartridge of the assembly of the present invention;
FIG. 3 is a schematic view of the moving core rod in the upper station during normal reactor operation;
FIG. 4 is a schematic view of the moving core rod in the lower station during normal reactor operation.
Detailed Description
As shown in fig. 1 and fig. 2, a hydraulic suspension split type passive shutdown assembly for a fast neutron reactor comprises a movable core rod 1 and an assembly sleeve 2 matched with the movable core rod, wherein one end of the movable core rod 1 is inserted into the assembly sleeve 2, an absorber rod bundle 11 is arranged in the movable core rod 1, an operating head 12 is arranged at the end part of the movable core rod 1, a coolant inlet hole 13 is arranged at the end part of the movable core rod 1 extending into the assembly sleeve 2, coolant outlet hole groups are arranged at the middle position of the peripheral surface of the movable core rod 1 and the position far away from the end part of the coolant inlet hole 13, each coolant outlet hole group comprises a plurality of annularly arranged coolant outlet holes, the coolant outlet holes are communicated with an inner cavity of the movable core rod 1, the number of the coolant outlet holes of the coolant outlet hole groups is generally 6-12, wherein the coolant outlet hole 14 at the middle part of the movable core rod 1 is a connecting hole, and the coolant outlet hole 15 at the top part of the movable core rod 1 is an outlet hole.
The preferred design of the pores is: the caliber of a coolant outlet hole 15 at the top of the moving core rod 1 is larger than the caliber of a coolant outlet hole 14 at the middle of the moving core rod, and the caliber of the coolant outlet hole 14 at the middle of the moving core rod is larger than the caliber of a coolant inlet hole 13 at the bottom of the moving core rod.
Further, the assembly sleeve 2 comprises a guide tube 21, an outer sleeve 22 and a pin 23, a pin inlet is arranged on the pin 23, the pin inlet is communicated with the guide tube 21, one end of the guide tube 21 is open, the movable core rod 1 is inserted into the guide tube 21 from the opening, a gap annular cavity 3 is formed between the inner wall of the guide tube 21 and the outer wall of the movable core rod 1, and the gap annular cavity 3 extends to the end opening of the guide tube 21.
Further, the movable core rod 1 and the assembly sleeve 2 are longitudinally arranged, and in order to ensure that the movable core rod 1 is suspended stably, the center lines of the movable core rod 1 and the assembly sleeve 2 are superposed.
As shown in fig. 3 and 4, when the apparatus is used, the coolant enters the pin 23 of the module sleeve from the pin inlet and flows from the bottom to the top, the coolant forms a flow split when passing through the coolant inlet hole 13 at the lowermost end of the moving mandrel 1, a part of the coolant enters the cooling absorber bundle 11 in the moving mandrel 1 and flows out from the coolant outlet hole 14 at the middle position and the coolant outlet hole 15 at the uppermost end of the moving mandrel 1, and the other part of the coolant flows through the gap 3 between the moving mandrel 1 and the guide tube 21 and finally flows out from the annular cavity.
Because the diameter of the coolant inlet hole 13 at the lowest end of the moving core rod 1 is small, the coolant flows through the coolant inlet hole to form great resistance, the flow entering the moving core rod 1 is small, and most of the coolant flows out of the gap annular cavity 3 at the outer side of the moving core rod 1; the coolant generates great on-way resistance when flowing through the slit annular cavity 3, the moving core rod 1 generates great pressure difference under the condition of small liquid flow, and the moving core rod 1 is subjected to upward hydraulic lifting force, so that the moving core rod is suspended at an upper working station under a certain flow.
When the hydraulic lifting force just enables the moving core rod 1 to be in a suspension state, the corresponding flow rate is critical flow rate, when the flow rate of the reactor core coolant is reduced due to a flow loss accident, the hydraulic lifting force of the coolant is reduced, when the flow rate is reduced to be below the critical flow rate, the hydraulic lifting force of the coolant is smaller than the gravity of the moving core rod 1, the moving core rod 1 starts to fall down and is finally kept at a lower station, the coolant forms a split flow when passing through a coolant inlet hole 13 at the lowest end of the moving core rod 1, the coolant outlet hole 14 at the middle position of the moving core rod 1 falls below the slit annular cavity 3 when the moving core rod 1 is located at the lower station, the coolant outside of the moving core rod 1 forms a second split flow before being led out of the slit annular cavity 3, the flow rate of the coolant entering the slit annular cavity 3 at the lower station is reduced, the pressure drop of the moving core rod 1 at the lower station is reduced, the moving core rod can be hydraulically self-tight when the moving core is located at the lower station, and the core is inserted into the reactor core to achieve reactor core shutdown.
The following examples of specific use of the device are as follows:
the total length of the passive component is 3960mm, the single-side clearance of the annular slit between the moving core rod 1 and the guide pipe 21 is 2mm, the lowest end of the moving core rod is provided with a coolant inlet hole 13 with the diameter of 10.5mm, the middle position of the moving core rod is provided with 12 connecting holes with the diameter of 12mm, and the highest end of the moving core rod is provided with 12 outlet holes with the diameter of 15 mm. The moving core rod has the mass of 25kg, the diameter of 90mm, the static buoyancy of 35N and the rated flow of the split type passive shutdown component of 5kg/s.
According to the calculation result, under the condition of rated flow, the upward resultant force of the moving core rod on the upper station is 823.77N, and the multiple of the gravity of the moving core rod is 3.36 times. The critical flow rate required for the moving mandrel to reach equilibrium at the upper station is Q =2.49kg/s, which is about 49.8% of the rated flow rate, i.e. the moving mandrel starts to fall when the flow rate drops to the critical flow rate of 2.49 kg/s. When a reactor has a flow loss accident, when the flow is reduced to be below 49.8 percent of the rated flow, namely the flow in the split type passive reactor shutdown component is reduced to be below 2.49kg/s, the movable core rod begins to fall under the action of gravity and is inserted into the reactor core, the reactor shutdown is realized, and the consequence of the flow loss accident is relieved.
After the core rod falls to the lower station, under the rated flow, the upward resultant force borne by the moving core rod is about 90.1N, which is far less than the gravity of the moving core rod, and the gravity is about 2.72 times of the upward resultant force, so that the hydraulic self-tightening of the core rod is ensured.
In conclusion, when the device is used, a coolant enters the guide pipe 21 of the assembly sleeve from a pin inlet and flows from bottom to top, the coolant forms a shunt when passing through the coolant inlet hole 13 at the lowest end of the moving core rod 1, one part of the coolant enters the cooling absorber rod bundle 11 in the moving core rod 1 and flows out from the coolant outlet hole 14 at the middle position and the coolant outlet hole 15 at the highest end of the moving core rod 1, the other part of the coolant flows in the gap annular cavity 3 between the moving core rod 1 and the guide pipe 21 and finally flows out, and by matching the gap annular cavity 3 with proper size and each small hole, the critical flow rate of the moving core rod 1 suspended at an upper station can be reduced under the condition of meeting the heat exchange requirement of the absorber rod bundle 11, and the influence of the split type passive reactor stopping assembly on the whole reactor core is reduced;
the passive safety device is designed according to the passive concept, does not need any trigger signal or external force drive, greatly reduces the failure probability, and can practically improve the safety of the nuclear power plant.
The foregoing shows and describes the general principles, essential features, and advantages of the invention. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the invention, but various changes and modifications may be made without departing from the spirit and scope of the invention, which is defined by the appended claims. The scope of the invention is defined by the appended claims and equivalents thereof.
Claims (4)
1. A hydraulic suspension split type passive shutdown assembly for a fast neutron reactor comprises a movable core rod and an assembly sleeve matched with the movable core rod, wherein one end of the movable core rod is inserted into the assembly sleeve;
the assembly sleeve comprises a guide pipe, an outer sleeve and a pin, the pin is provided with a pin inlet, the pin inlet is communicated with the guide pipe, one end of the guide pipe is opened, the movable core rod is inserted into the guide pipe from the opening, and a gap annular cavity is formed between the inner wall of the guide pipe and the outer wall of the movable core rod;
the gap annular cavity extends to an opening at the end part of the guide pipe;
the cooling agent outlet hole group comprises a plurality of cooling agent outlet holes which are annularly arranged, and the cooling agent outlet holes are communicated with the inner cavity of the movable core rod;
the end of the moving core rod is provided with an operating head;
the movable core rod and the assembly sleeve are longitudinally arranged, and the central lines of the movable core rod and the assembly sleeve are superposed;
the caliber of a coolant outlet hole at the top of the moving core rod is larger than that of a coolant outlet hole at the middle of the moving core rod, and the caliber of the coolant outlet hole at the middle of the moving core rod is larger than that of a coolant inlet hole at the bottom of the moving core rod;
the number of the coolant outlet holes of the coolant outlet hole group is 6-12, the coolant outlet hole in the middle of the moving core rod is a connecting hole, and the coolant outlet hole in the top of the moving core rod is an outlet hole.
2. The hydraulic suspension split type passive shutdown assembly for the fast neutron reactor according to claim 1, wherein the coolant enters the guide pipe of the assembly sleeve from the pin inlet, flows from bottom to top, forms a split flow when passing through the coolant inlet hole at the lowest end of the moving core rod, one part of the coolant enters the absorber rod bundle in the moving core rod and flows out from the coolant outlet hole at the middle position and the coolant outlet hole at the highest end of the moving core rod, and the other part of the coolant flows in the gap annular cavity between the moving core rod and the guide pipe and finally flows out.
3. The hydraulic suspension split type passive shutdown assembly for the fast neutron reactor according to claim 2, wherein the diameter of the coolant inlet hole at the lowest end of the moving core rod is small, the coolant flows through the coolant inlet hole to form great resistance, the flow rate entering the inside of the moving core rod is small, and most of the coolant flows out from the annular gap cavity on the outer side of the moving core rod; the coolant generates great on-way resistance when flowing through the slit annular cavity, the moving core rod generates great pressure difference under the condition of small liquid flow, and the moving core rod is subjected to upward hydraulic lifting force, so that the moving core rod is suspended at an upper station under a certain flow.
4. The hydraulic suspension split type passive shutdown assembly for the fast neutron reactor according to claim 2, wherein when the liquid lifting force just enables the moving core rod to be in a suspension state, the corresponding flow rate is critical flow rate, when a flow loss accident causes the flow rate of the reactor core coolant to be reduced, the hydraulic lifting force is reduced, when the flow rate is reduced below the critical flow rate, the hydraulic lifting force is smaller than the gravity of the moving core rod, the moving core rod starts to fall down and finally is kept at a lower station, the coolant forms a split flow when passing through a coolant inlet hole at the lowest end of the moving core rod, when the moving core rod is located at the lower station, a coolant outlet hole at the middle position of the moving core rod falls below the slit annular chamber, the coolant outside the moving core rod forms a second split flow before being led out of the slit annular chamber, the flow rate of the coolant entering the slit annular chamber at the lower station is reduced, and therefore, the pressure drop of the moving core rod at the lower station is reduced, and the moving core rod can be hydraulically self-tightened when located at the lower station.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010737630.2A CN112037943B (en) | 2020-07-28 | 2020-07-28 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
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| CN202010737630.2A CN112037943B (en) | 2020-07-28 | 2020-07-28 | Hydraulic suspension split type passive shutdown assembly for fast neutron reactor |
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| CN112037943B true CN112037943B (en) | 2023-03-14 |
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