CN117174347B - High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof - Google Patents
High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof Download PDFInfo
- Publication number
- CN117174347B CN117174347B CN202310923766.6A CN202310923766A CN117174347B CN 117174347 B CN117174347 B CN 117174347B CN 202310923766 A CN202310923766 A CN 202310923766A CN 117174347 B CN117174347 B CN 117174347B
- Authority
- CN
- China
- Prior art keywords
- temperature gas
- gas cooled
- groove
- cooled reactor
- flow
- Prior art date
- 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.)
- Active
Links
- 238000012360 testing method Methods 0.000 title claims abstract description 29
- 239000002826 coolant Substances 0.000 title abstract description 29
- 238000000034 method Methods 0.000 title abstract description 13
- 238000007789 sealing Methods 0.000 claims abstract description 73
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 50
- 229910002804 graphite Inorganic materials 0.000 claims abstract description 49
- 239000010439 graphite Substances 0.000 claims abstract description 49
- 230000005540 biological transmission Effects 0.000 claims abstract description 12
- 239000011241 protective layer Substances 0.000 claims abstract description 10
- 238000003825 pressing Methods 0.000 claims description 20
- 230000006835 compression Effects 0.000 claims description 3
- 238000007906 compression Methods 0.000 claims description 3
- 230000000903 blocking effect Effects 0.000 claims description 2
- 239000007789 gas Substances 0.000 abstract description 42
- 239000001307 helium Substances 0.000 abstract description 24
- 229910052734 helium Inorganic materials 0.000 abstract description 24
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 abstract description 24
- 238000013461 design Methods 0.000 abstract description 15
- 238000009826 distribution Methods 0.000 abstract description 13
- 239000000446 fuel Substances 0.000 abstract description 7
- 238000004088 simulation Methods 0.000 abstract description 6
- 230000009286 beneficial effect Effects 0.000 abstract description 2
- 239000010410 layer Substances 0.000 description 12
- 230000000694 effects Effects 0.000 description 6
- 230000007423 decrease Effects 0.000 description 5
- 238000012986 modification Methods 0.000 description 4
- 230000004048 modification Effects 0.000 description 4
- 230000000149 penetrating effect Effects 0.000 description 4
- 238000011056 performance test Methods 0.000 description 4
- 230000008901 benefit Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 238000004364 calculation method Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000013011 mating Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 230000003139 buffering effect Effects 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 239000003086 colorant Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000012552 review Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a high-temperature gas cooled reactor coolant bypass control method and a tightness test device thereof, wherein the method comprises a reactor unit, a plurality of groups of graphite blocks, a protective layer and a plurality of groups of graphite blocks; a plugging unit comprising a longitudinal seal and a transverse seal rack; the adjusting unit comprises a plurality of rotating rods, a transmission piece arranged on one side of the rotating rods and a limiting cover. The invention has the beneficial effects that the sealing performance is tested through the simulation experiment device, the longitudinal side flow and the transverse leakage flow of the helium coolant are blocked, the influence of the structural side flow on the flow distribution of the helium coolant in the pebble bed is effectively reduced, the effective coolant flow flowing through the pebble bed is ensured, and then the temperature distribution and the highest fuel temperature of the pebble bed are optimized, so that the design demonstration of the high-temperature gas cooled reactor structure is effectively supported, and the safety and the reliability of the pebble bed type high-temperature gas cooled reactor are further improved.
Description
Technical Field
The invention relates to the technical field of bypass control, in particular to a high-temperature gas cooled reactor coolant bypass control method and a tightness test device thereof.
Background
The pebble-bed high-temperature gas cooled reactor is an advanced reactor with inherent safety, high power generation efficiency and wide potential heat application. The reactor internal components comprise a large number of graphite blocks, carbon blocks and other ceramic components, namely reactor structural materials, and also form a flow passage of helium coolant. Depending on the flow characteristics and reasons for generation of the coolant in each section of the reactor, the helium coolant in the reactor can be divided into three sections:
1. the main flow of helium gas is an effective flow part which flows through the reactor core sphere and carries fuel out of the reactor core by heating;
2. functional side streams, including side streams flowing through control rod openings and side streams flowing through discharge tubes;
3. due to structural bypass flow, a certain narrow gap exists between graphite blocks due to assembly, thermal expansion and other reasons, so that helium flows in a main design flow channel, and a small part of the helium flows in the graphite gap to become a bypass flow of a main flow of helium.
The presence of the structural bypass flow alters the flow distribution of the helium coolant within the reactor to a degree that results in a reduction in the effective helium coolant flow through the sphere, which in turn affects the temperature distribution within the sphere and the maximum temperature of the fuel, thus requiring significant attention and effective control in the design of high temperature gas cooled reactors. The invention provides a simulation test device and a sealing performance simulation test device, which are used for realizing optimization of flow distribution of helium coolant in a reactor, effectively controlling the highest temperature of fuel, effectively supporting design and demonstration of a high-temperature gas cooled reactor structure, and further improving the safety and reliability of a pebble-bed high-temperature gas cooled reactor.
Disclosure of Invention
This section is intended to outline some aspects of embodiments of the application and to briefly introduce some preferred embodiments. Some simplifications or omissions may be made in this section as well as in the description of the application and in the title of the application, which may not be used to limit the scope of the application.
The present invention has been made in view of the above-mentioned or existing problems occurring in the prior art.
Therefore, the invention aims at providing a bypass control device and a sealing performance simulation test device for structural bypass flowing through vertical narrow slits among graphite blocks of a reflecting layer at the inner side of a reactor, so as to optimize the flow distribution of helium coolant in the reactor, effectively control the highest temperature of fuel and finally optimize the flow distribution of the helium coolant in a pebble bed.
In order to solve the technical problems, the invention provides the following technical scheme: a high temperature gas cooled reactor coolant bypass control method comprising the steps of:
s1, identifying a structural bypass flow part in a reactor; s2, constructing a sealing key sealing bypass channel of a dovetail groove structure; s3, processing a simulator to carry out a bypass flow sealing performance test, and verifying a bypass flow control effect.
As a preferable scheme of the high-temperature gas cooled reactor coolant bypass control method, the invention comprises the following steps: the identification of structural bypass flows in the reactor is specifically as follows: according to the structural characteristics of the reactor, the narrow slit bypass flow which possibly affects the temperature distribution of the ball bed is analyzed, and the size of the bypass flow and the influence on the heat exchange of the flow in the ball bed are quantitatively analyzed through thermodynamic hydraulic calculation, so that the main narrow slit bypass flow is confirmed.
As a preferable scheme of the high-temperature gas cooled reactor coolant bypass control method, the invention comprises the following steps: the sealing key of the dovetail groove structure is specifically designed at the ball bed side of the identified narrow slit and comprises a transverse sealing key for sealing the narrow slit on the upper surface among graphite blocks and a vertical sealing key for sealing the vertical narrow slit penetrating through the whole side reflecting layer among the graphite blocks, so that the longitudinal bypass flow and the transverse leakage flow of helium coolant are blocked.
The invention further aims to provide a high-temperature gas cooled reactor bypass flow tightness testing device which comprises a reactor unit, a plurality of groups of graphite blocks, a plurality of connecting rods and a plurality of connecting rods, wherein the connecting rods are arranged in the connecting rods;
the plugging unit comprises a longitudinal sealing piece and a transverse sealing rack arranged on one side of the longitudinal sealing piece;
The adjusting unit comprises a plurality of rotating rods, a transmission piece arranged on one side of the rotating rods and a limit cover arranged on one side of the transmission piece.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the protective layer comprises a mounting groove arranged at the bottom of the protective layer; the mounting groove comprises a compression spring arranged in the mounting groove and a plurality of fixed guide balls arranged on the inner wall of the mounting groove.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the graphite block comprises a bypass channel and a trapezoid protruding block arranged on one side of the graphite block.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the cross section shape of the longitudinal sealing element is consistent with the gap formed between two adjacent graphite blocks which are on the same plane;
The longitudinal sealing piece comprises a first inserting groove longitudinally arranged in the longitudinal sealing piece and a second inserting groove transversely arranged in the longitudinal sealing piece;
The diameter of the upper half section of the first inserting groove is gradually reduced from top to bottom, and the first inserting groove further comprises a spiral groove arranged on the inner wall of the first inserting groove and an annular groove communicated with the lower part of the spiral groove.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the rotating rod comprises a pressing knob, a pressing spring arranged on one side of the pressing knob, a first inserted link arranged on one side of the pressing spring, a second inserted link arranged on one side of the first inserted link, a gear arranged on the outer wall of the second inserted link and a clamping head arranged on one side of the second inserted link;
The first inserted link rod diameter gradually decreases from top to bottom, and the first inserted link further comprises a spherical protrusion arranged on the outer wall of the first inserted link rod.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the transmission piece comprises a disc-shaped gear, a connecting rod arranged on one side of the disc-shaped gear and a rotating rod arranged on one side of the connecting rod.
As a preferable scheme of the high-temperature gas cooled reactor bypass flow tightness testing device, the invention comprises the following steps: the limit cover comprises a plurality of limit protrusions arranged on one side of the limit cover.
The beneficial effects of the invention are as follows: the sealing piece with the dovetail groove structure is designed at the position of the main narrow slit bypass flow, and the sealing piece can block the longitudinal bypass flow and the transverse leakage flow of the helium coolant. Meanwhile, a bypass flow sealing performance test device is designed to verify the bypass flow control effect. Through the bypass control measure, the influence of structural bypass on the flow distribution of helium coolant in the pebble bed is effectively reduced, the effective coolant flow flowing through the pebble bed is ensured, and then the temperature distribution and the highest fuel temperature of the pebble bed are optimized, so that the design and demonstration of the high-temperature gas cooled reactor structure are effectively supported, and the safety and reliability of the pebble bed type high-temperature gas cooled reactor are further improved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the description of the embodiments will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present invention, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art. Wherein:
FIG. 1 is a schematic diagram of the overall structure of a high temperature gas cooled reactor bypass flow tightness test device;
FIG. 2 is a schematic diagram of another overall structure of a high temperature gas cooled reactor bypass flow tightness test device;
FIG. 3 is an overall cross-sectional view of a high temperature gas cooled reactor bypass flow tightness test device;
FIG. 4 is an enlarged view of a portion of the high temperature gas cooled reactor bypass flow tightness test device at A in FIG. 3;
FIG. 5 is a schematic structural view of a rotating rod in the high temperature gas cooled reactor bypass flow tightness test device;
FIG. 6 is a schematic diagram of the structure of graphite blocks in the high temperature gas cooled reactor bypass flow tightness test device;
FIG. 7 is a schematic structural view of a longitudinal seal in a high temperature gas cooled reactor bypass flow tightness test device.
Detailed Description
In order that the above-recited objects, features and advantages of the present invention will become more readily apparent, a more particular description of the invention will be rendered by reference to specific embodiments thereof which are illustrated in the appended drawings.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, but the present invention may be practiced in other ways other than those described herein, and persons skilled in the art will readily appreciate that the present invention is not limited to the specific embodiments disclosed below.
Further, reference herein to "one embodiment" or "an embodiment" means that a particular feature, structure, or characteristic can be included in at least one implementation of the invention. The appearances of the phrase "in one embodiment" in various places in the specification are not necessarily all referring to the same embodiment, nor are separate or alternative embodiments mutually exclusive of other embodiments.
Example 1
The first embodiment of the invention provides a high-temperature gas cooled reactor bypass flow tightness testing device, which comprises the following steps: s1, identifying a structural bypass flow part in a reactor; s2, constructing a sealing key sealing bypass channel of a dovetail groove structure; s3, processing a simulator to carry out a bypass flow sealing performance test, and verifying a bypass flow control effect.
The method is characterized in that structural bypass flows in the reactor are identified, namely, narrow slit bypass flows which possibly influence the temperature distribution of the ball bed are analyzed according to the structural design characteristics of the reactor, the size of the bypass flows and the influence on the heat exchange of the flow in the ball bed are quantitatively analyzed through thermodynamic hydraulic calculation, and therefore the main narrow slit bypass flows are confirmed.
The design dovetail groove structure sealing key is specifically that a dovetail groove structure sealing key is designed at the sphere bed side of the identified narrow slit, and comprises a transverse sealing key for sealing the narrow slit on the upper surface among graphite blocks and a vertical sealing key for sealing the vertical narrow slit penetrating through the whole side reflecting layer among the graphite blocks, so that the longitudinal bypass flow and the transverse leakage flow of helium coolant are blocked.
It should be noted that, the adjacent sealing keys are overlapped with each other by adopting a mortise and tenon structure, and the sealing keys are further fixed. Radial movement is avoided through the fixation of mortise and tenon structure to horizontal sealing key, and vertical sealing key is fixed by the mortise and tenon structure between dovetail structure and upper and lower key, avoids taking off and falls into the ball bed.
Preferably, a reactor simulator with a ratio of 1:10 is processed, a channel penetrating to a narrow slit is processed in a graphite block anti-rotation key, a sealing cover is added to seal a cavity between an outer layer cylinder body and a side reflection layer graphite block, then a fan is used for extracting side flow leaking into the narrow slit, and the measured side flow is compared with the upper limit value of the leakage rate considered by the reactor design, so that the side flow control effect is verified. As the medium flowing in the reactor adopts normal temperature and normal pressure air, the design leakage rate is converted from the corresponding value of high temperature and high pressure helium gas to the value of normal temperature and normal pressure air.
In summary, the sealing key with the dovetail groove structure is designed at the side flow position of the main narrow slit, and the sealing key can block the longitudinal side flow and the transverse leakage flow of the helium coolant. Meanwhile, a bypass flow sealing performance test device is designed to verify the bypass flow control effect. Through the bypass control measure, the influence of structural bypass on the flow distribution of helium coolant in the pebble bed is effectively reduced, the effective coolant flow flowing through the pebble bed is ensured, and then the temperature distribution and the highest fuel temperature of the pebble bed are optimized, so that the design and demonstration of the high-temperature gas cooled reactor structure are effectively supported, and the safety and reliability of the pebble bed type high-temperature gas cooled reactor are further improved.
Example 2
Referring to fig. 1 to 3 and 6 to 7, a second embodiment of the present invention provides a high temperature gas cooled reactor bypass leak tightness test device, which includes a reactor unit 100 including a protection layer 101, and a plurality of groups of graphite blocks 102 disposed in the protection layer 101;
the plugging unit 200 comprises a longitudinal sealing member 201 and a transverse sealing rack 202 arranged on one side of the longitudinal sealing member 201;
The adjusting unit 300 comprises a plurality of rotating rods 301, a transmission member 302 arranged on one side of the rotating rods 301, and a limiting cover 303 arranged on one side of the transmission member 302.
The graphite block 102 includes a bypass channel 102a and a trapezoidal bump 102b disposed on one side of the graphite block 102;
the longitudinal seal 201 has a cross-sectional shape that corresponds to the gap formed between two co-planar and adjacent graphite blocks 102;
The longitudinal seal 201 includes a first mating groove 201a disposed longitudinally therein and a second mating groove 201b disposed transversely to the interior of the longitudinal seal 201.
It should be noted that, the protective layer 101 is made of a high-strength high-density metal material, specifically steel or lead, and protects the reactor to prevent the graphite blocks 102 from directly contacting with the external environment, reduces oxidation and corrosion to the graphite blocks 102, and in addition, plays a role in sealing radioactive substances to prevent leakage, supporting and improving stability, the graphite blocks 102 have a fan-shaped cross section, the graphite blocks are divided into two layers, each layer is connected with 12 graphite blocks 102 in a surrounding manner, and the graphite blocks 102 are arranged in the protective layer 101 in a circular ring shape after surrounding.
Preferably, the plugging unit 200 is comprised of a longitudinal seal 201 and a transverse seal rack 202 to seal the gap between each adjacent two graphite blocks 102, i.e., to control the structural bypass of helium gas coolant in the graphite gaps.
Preferably, the graphite block 102 is longitudinally provided with a through bypass channel 102a along the center position thereof, the bypass channel 102a is a bypass channel for circulating helium gas coolant, the device is mainly used for simulating and testing the sealing performance of the part, one side of the graphite block 102 is fixedly connected with a trapezoid convex block 102b, the trapezoid convex block 102b and the trapezoid convex block are fixed into an integral structure, thus a through sealing area is formed between two adjacent graphite blocks 102 and is divided into a longitudinal through area and a transverse through area, a longitudinal sealing piece 201 is inserted into the longitudinal through area, the section of the longitudinal sealing piece 201 is attached to the inner wall of the area, after the longitudinal sealing piece 201 is inserted, the sealing of a longitudinal gap can be realized, the longitudinal sealing piece 201 also comprises a first inserting groove 201a longitudinally penetrating through the center position of the upper surface of the longitudinal sealing piece, and a through transverse second inserting groove 201b positioned in the middle of the longitudinal sealing piece, and the second inserting groove 201b is in a curved surface 1/24 circular ring shape and faces the transverse gap between the upper graphite block 102 and the lower graphite block.
Preferably, the transverse sealing rack 202 is an arc-shaped 1/24 annular rack, and is movably arranged in the second inserting groove 201b, the transverse sealing rack 202 is used for sealing the gap between the upper graphite block 102 and the lower graphite block 102, after the longitudinal sealing piece 201 is inserted and aligned, the rotating rod 301 inserted into the transverse sealing rack is rotated, and as the gear 301e fixedly connected with the outer wall of the rotating rod 301 is meshed with the transverse sealing rack 202, the rotating rod 301 drives the transverse sealing rack 202 to rotate along the second inserting groove 201b to transfer the transverse sealing rack 202 into the transverse gap which is not sealed by the longitudinal sealing piece 201, so that the complete sealing of the transverse gap is realized.
Example 3
Referring to fig. 1 to 7, a third embodiment of the present invention includes the above embodiments, and is different from the above embodiments: the first plugging groove 201a further comprises a spiral groove 201a-1 arranged on the inner wall of the first plugging groove 201a, and an annular groove 201a-2 communicated with the lower part of the spiral groove 201a-1, wherein the diameter of the upper half section of the first plugging groove 201a gradually decreases from top to bottom;
The protective layer 101 includes a mounting groove 101a provided at the bottom thereof; the installation groove 101a includes a compression spring 101a-1 provided therein, and a plurality of fixed guide balls 101a-2 provided on an inner wall of the installation groove 101 a.
The rotary lever 301 includes a pressing knob 301a, a pressing spring 301b provided on the pressing knob 301a side, a first plunger 301c provided on the pressing spring 301b side, a second plunger 301d provided on the first plunger 301c side, a gear 301e provided on the outer wall of the second plunger 301d, and a chuck 301f provided on the second plunger 301d side.
The first plunger 301c gradually decreases in the diameter from top to bottom, and the first plunger 301c further includes a spherical protrusion 301c-1 provided on the outer wall thereof.
The transmission member 302 includes a disk gear 302a, a connecting rod 302b provided on one side of the disk gear 302a, and a rotating rod 302c provided on one side of the connecting rod 302 b.
The stopper cover 303 includes a plurality of stopper protrusions 303a provided at one side thereof.
It should be noted that, the pressing knob 301a is disc-shaped, the circumference of the pressing knob 301a is provided with a longitudinal tooth shape, the pressing knob 301a is fixedly connected with the first inserting rod 301c through a short rod, the short rod is externally surrounded with a pressing spring 301b for buffering the pressing knob 301a, the first inserting rod 301c is fixedly connected with the second inserting rod 301d into a whole, the outer wall of the second inserting rod 301d is fixedly connected with a gear 301e, and the clamping head 301f is fixedly connected with the other side of the second inserting rod 301 d.
Preferably, the diameter of the first insert rod 301c gradually decreases from top to bottom until the diameter of the first insert rod is consistent with that of the second insert rod 301d, the diameter of the upper insert rod is about 1.5 times that of the lower insert rod, and a fixed spherical protrusion 301c-1 is formed on the surface side of the first insert rod 301c, which is close to the position of the gear 301 e. The clamping head 301f is fixedly connected to the end position of the second inserting rod 301d, the clamping head 301f is in an irregular convex sphere shape, a spiral annular groove is formed in the outer wall of the sphere of the clamping head 301f, the groove is meshed with a fixed guide ball 101a-2 fixedly connected to the inner wall of the mounting groove 101a, the clamping head 301f can be inserted into the mounting groove 101a through the rotating rod 301, the clamping head can continue to rotate without being influenced after the clamping head rotates into the mounting groove 101a, once the clamping head rotates reversely, the rotating rod 301 is driven to scratch the mounting groove 101a, and the structure is quite suitable for a scene that the transverse sealing rack 202 still needs to be rotated after the insertion of the rotating rod 301 is completed.
Preferably, the longitudinal first inserting groove 201a is divided into an upper half section and a lower half section along the transverse gap between the upper and lower graphite blocks 102, wherein the diameter of the upper half section gradually decreases from the upper to the lower apertures, and the diameter of the upper section is about 1.5 times of the diameter of the lower section and slightly larger than the diameter of the first inserting rod 301 c. The inner wall of the upper half section of the first inserting groove 201a is also provided with a spiral groove 201a-1, the spiral groove 201a-1 is also provided with a smooth round angle from top to bottom, the lower part of the spiral groove 201a-1 is also provided with an annular groove 201a-2, the annular groove 201a-2 is communicated with the spiral groove 201a-1 through a section of longitudinal groove, when the rotating rod 301 is inserted into the first inserting groove 201a, a spherical bulge 301c-1 fixedly connected to the outer wall of the rotating rod 301 is gradually meshed with the spiral groove 201a-1, the direction of the spherical bulge is regulated to be fixed in the direction of the spiral groove 201a-1, the bulge slides into the annular groove 201a-2 after reaching the end point of the spiral groove 201a-1, and is limited in the annular groove 201a-2, and as the bulge is inserted into the position of the gear 301e and the transverse sealing rack 202 is always at the bottom position of the spiral groove 201a-1, the problem that the rotating rod 301 is blocked due to the collision between two parts of teeth can be well avoided.
Preferably, the transmission piece 302, the limiting cover 303 and the rotating rods 301 are integrated, the transmission piece 302 is connected with the rotating rods 301 through a central rotating shaft, the disc-mounted gear 302a is meshed with the outer tooth shapes of the pressing knobs 301a on the rotating rods 301, when the rotating rods 302c are rotated, the surrounding 12 rotating rods 301 can be simultaneously driven to rotate, so that the rotating rods 301 are synchronously inserted and sealed transversely, the working efficiency is greatly improved, the limiting cover 303 is a circular steel cover, 12 limiting protrusions 303a are fixed on the outer edge of the limiting cover in a uniform array, when the limiting cover 303 is tightly covered, the limiting protrusions 303a are meshed with the upper portions of the trapezoidal protrusions 102b of the upper graphite blocks 102 in a recessed mode, position fixing can be achieved, and when the limiting cover 303 is pressed, the limiting cover 303 can press the rotating rods 301 to be inserted downwards into the mounting grooves 101 a.
The method comprises the following steps of 1, simulating a high-temperature gas cooled reactor to stack graphite blocks 102 into a protection layer 101 in a circular ring shape in two layers;
2. placing the transverse sealing rack 202 into the second insertion groove 201b of the longitudinal seal 201;
3. the longitudinal sealing piece 201 is inserted along the longitudinal through area between the graphite blocks 102, so that the sealing of the longitudinal gap between two adjacent graphite blocks 102 is realized;
4. The rotating rods 301 in the adjusting unit 300 are respectively inserted into the first inserting grooves on the longitudinal sealing piece 201 in a one-to-one correspondence manner, and at the moment, the limiting protrusions 303a on the limiting cover 303 are just meshed with the partial depressions on the trapezoid protruding blocks 102b of the upper-layer graphite block 102;
5. The limiting cover 303 is pressed with uniform force from the upper part of the device, during the pressing process, the spherical protrusion 301c-1 on the rotating rod 301 is gradually meshed with the spiral groove 201a, the direction is adjusted, the spherical protrusion 301c-1 slides into the annular groove 201a-2 and is limited in the annular groove 201a-2 after reaching the end point of the spiral groove 201a-1, meanwhile, the gear 301e is gradually meshed with the transverse sealing rack 202, and meanwhile, the clamping head 301f at the end of the rotating rod 301 is also gradually meshed with the fixed guide ball 101a-2 and is inserted into the mounting groove 101 a;
6. Rotating the rotating rod 302c to enable the disc gear 302a to synchronously drive a pressing knob on the rotating rod 301 and drive the rack to be attached to the wall of the graphite block 102 to extend out through the engagement of the gear 301e and the transverse sealing rack 202, so that the gap between the upper graphite block 102 and the lower graphite block 102 is sealed;
7. flowing medium normal temperature and pressure air or high temperature and high pressure helium gas is injected into one side of the bypass flow passage 102a, the other side of the bypass flow passage 102a is led out and recycled through an outlet, the rest unrecovered leakage gas is pumped out at the other side of the bypass flow passage 102a through a fan, and the measured bypass flow rate is compared with the leakage upper limit value considered by the reactor design, so that the bypass flow control effect is verified.
In summary, the present invention forms a barrier to the longitudinal bypass flow and the lateral leakage flow of helium coolant by the blocking unit 200. The simulation test device can simulate the high-temperature gas cooled reactor for operation test, saves cost, reduces potential safety hazard, and can effectively support the design and demonstration of the high-temperature gas cooled reactor structure through data generated by simulation, thereby further improving the safety and reliability of the pebble-bed high-temperature gas cooled reactor.
It is important to note that the construction and arrangement of the application as shown in the various exemplary embodiments is illustrative only. Although only a few embodiments have been described in detail in this disclosure, those skilled in the art who review this disclosure will readily appreciate that many modifications are possible (e.g., variations in sizes, dimensions, structures, shapes and proportions of the various elements, values of parameters (e.g., temperature, pressure, etc.), mounting arrangements, use of materials, colors, orientations, etc.) without materially departing from the novel teachings and advantages of the subject matter described in this application. For example, elements shown as integrally formed may be constructed of multiple parts or elements, the position of elements may be reversed or otherwise varied, and the nature or number of discrete elements or positions may be altered or varied. Accordingly, all such modifications are intended to be included within the scope of present application. The order or sequence of any process or method steps may be varied or re-sequenced according to alternative embodiments. In the claims, any means-plus-function clause is intended to cover the structures described herein as performing the recited function and not only structural equivalents but also equivalent structures. Other substitutions, modifications, changes and omissions may be made in the design, operating conditions and arrangement of the exemplary embodiments without departing from the scope of the present applications. Therefore, the application is not limited to the specific embodiments, but extends to various modifications that nevertheless fall within the scope of the appended claims.
Furthermore, in order to provide a concise description of the exemplary embodiments, all features of an actual implementation may not be described (i.e., those not associated with the best mode presently contemplated for carrying out the invention, or those not associated with practicing the invention).
It should be appreciated that in the development of any such actual implementation, as in any engineering or design project, numerous implementation-specific decisions may be made. Such a development effort might be complex and time consuming, but would nevertheless be a routine undertaking of design, fabrication, and manufacture for those of ordinary skill having the benefit of this disclosure.
It should be noted that the above embodiments are only for illustrating the technical solution of the present invention and not for limiting the same, and although the present invention has been described in detail with reference to the preferred embodiments, it should be understood by those skilled in the art that the technical solution of the present invention may be modified or substituted without departing from the spirit and scope of the technical solution of the present invention, which is intended to be covered in the scope of the claims of the present invention.
Claims (3)
1. A high temperature gas cooled reactor side stream tightness testing device is characterized in that: comprising the steps of (a) a step of,
A reactor unit (100) comprising a protective layer (101), a plurality of groups of graphite blocks (102) arranged within the protective layer (101);
A blocking unit (200) comprising a longitudinal seal (201) and a transverse seal rack (202) arranged on one side of the longitudinal seal (201);
The adjusting unit (300) comprises a plurality of rotating rods (301), a transmission piece (302) arranged on one side of the rotating rods (301), and a limit cover (303) arranged on one side of the transmission piece (302);
The cross-sectional shape of the longitudinal sealing element (201) is consistent with the gap formed between two adjacent graphite blocks (102) which are coplanar;
the longitudinal sealing element (201) comprises a first inserting groove (201 a) longitudinally arranged in the longitudinal sealing element, and a second inserting groove (201 b) transversely arranged in the longitudinal sealing element (201);
The diameter of the upper half section of the first inserting groove (201 a) is gradually reduced from top to bottom, the first inserting groove (201 a) further comprises a spiral groove (201 a-1) arranged on the inner wall of the first inserting groove, and an annular groove (201 a-2) communicated with the lower part of the spiral groove (201 a-1);
The rotating rod (301) comprises a pressing knob (301 a), a pressing spring (301 b) arranged on one side of the pressing knob (301 a), a first inserting rod (301 c) arranged on one side of the pressing spring (301 b), a second inserting rod (301 d) arranged on one side of the first inserting rod (301 c), a gear (301 e) arranged on the outer wall of the second inserting rod (301 d), and a clamping head (301 f) arranged on one side of the second inserting rod (301 d);
the first inserted link (301 c) gradually reduces from top to bottom, and the first inserted link (301 c) further comprises a spherical protrusion (301 c-1) arranged on the outer wall of the first inserted link;
the transmission member (302) comprises a disc-shaped gear (302 a), a connecting rod (302 b) arranged on one side of the disc-shaped gear (302 a), and a rotating rod (302 c) arranged on one side of the connecting rod (302 b);
The limit cover (303) includes a plurality of limit protrusions (303 a) provided at one side thereof.
2. The high temperature gas cooled reactor bypass flow tightness test device of claim 1, wherein: the protective layer (101) comprises a mounting groove (101 a) arranged at the bottom of the protective layer; the mounting groove (101 a) comprises a compression spring (101 a-1) arranged in the mounting groove, and a plurality of fixed guide balls (101 a-2) arranged on the inner wall of the mounting groove (101 a).
3. The high temperature gas cooled reactor bypass flow tightness test device of claim 2, wherein: the graphite block (102) comprises a bypass channel (102 a) and a trapezoid lug (102 b) arranged on one side of the graphite block (102).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310923766.6A CN117174347B (en) | 2023-07-26 | 2023-07-26 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310923766.6A CN117174347B (en) | 2023-07-26 | 2023-07-26 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN117174347A CN117174347A (en) | 2023-12-05 |
| CN117174347B true CN117174347B (en) | 2024-06-04 |
Family
ID=88943835
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310923766.6A Active CN117174347B (en) | 2023-07-26 | 2023-07-26 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117174347B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN117079842B (en) * | 2023-07-27 | 2024-06-04 | 华能核能技术研究院有限公司 | High-temperature gas cooled reactor side gap flow blocking device |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3998057A (en) * | 1974-02-01 | 1976-12-21 | Hochtemperatur-Reactorbau Gmbh | Nuclear powerplant with closed gas-cooling circuit |
| EP1465207A2 (en) * | 2003-03-27 | 2004-10-06 | President of Tokyo Institute of Technology | Reactor core cooling structure |
| JP2005049227A (en) * | 2003-07-29 | 2005-02-24 | Fuji Electric Systems Co Ltd | Pebble bed type high-temperature gas-cooled reactor |
| KR20110075487A (en) * | 2009-12-28 | 2011-07-06 | 한국원자력연구원 | Core for high temperature gas cooled reactor |
| CN102603300A (en) * | 2012-03-26 | 2012-07-25 | 方大炭素新材料科技股份有限公司 | Brick fuel used for high-temperature gas cooled reactor and preparation method thereof |
| CN113299409A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Small-size villaumite of spiral cross fuel element cools off high temperature reactor core |
| CN114220566A (en) * | 2021-10-29 | 2022-03-22 | 华能核能技术研究院有限公司 | Method for plugging narrow gap in reactor pressure vessel of nuclear power station |
-
2023
- 2023-07-26 CN CN202310923766.6A patent/CN117174347B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3998057A (en) * | 1974-02-01 | 1976-12-21 | Hochtemperatur-Reactorbau Gmbh | Nuclear powerplant with closed gas-cooling circuit |
| EP1465207A2 (en) * | 2003-03-27 | 2004-10-06 | President of Tokyo Institute of Technology | Reactor core cooling structure |
| JP2005049227A (en) * | 2003-07-29 | 2005-02-24 | Fuji Electric Systems Co Ltd | Pebble bed type high-temperature gas-cooled reactor |
| KR20110075487A (en) * | 2009-12-28 | 2011-07-06 | 한국원자력연구원 | Core for high temperature gas cooled reactor |
| CN102603300A (en) * | 2012-03-26 | 2012-07-25 | 方大炭素新材料科技股份有限公司 | Brick fuel used for high-temperature gas cooled reactor and preparation method thereof |
| CN113299409A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Small-size villaumite of spiral cross fuel element cools off high temperature reactor core |
| CN114220566A (en) * | 2021-10-29 | 2022-03-22 | 华能核能技术研究院有限公司 | Method for plugging narrow gap in reactor pressure vessel of nuclear power station |
Non-Patent Citations (3)
| Title |
|---|
| Various bypass flow paths and bypass flow ratios in HTR-PM;Sun Jun er al.;Energy Procedia;20131231;第258-266页 * |
| 石墨堆芯结构在地震激励下动态响应的数值模拟;赖士刚 等;原子能科学技术;20161130;第50卷(第11期);第2041-2047页 * |
| 高温气冷堆反射层竖向窄缝中的旁流研究;陈志鹏 等;工程热物理学报;20180331;第39卷(第3期);第592-597页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN117174347A (en) | 2023-12-05 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN117174347B (en) | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof | |
| Martin et al. | Radiation-assisted internal heat transfer enhancement with fiber arrays | |
| Baek et al. | KAERI integral effect test program and the ATLAS design | |
| Imaizumi et al. | Development of CFD method to evaluate 3-D flow characteristics for PWR fuel assembly | |
| CN111781059A (en) | Creep irradiation device suitable for stress static loading | |
| Sumner et al. | Benchmark Specification for FFTF LOFWOS Test# 13 | |
| CN117079842B (en) | High-temperature gas cooled reactor side gap flow blocking device | |
| Li et al. | Research on scaling analysis and design parameters of integral test facilities for PWR | |
| CN116734067A (en) | Connecting device for thermal control instrument | |
| Dawson et al. | The effect of testing environment on small punch creep | |
| Kawaji et al. | Experimental Investigation of Forced Convection and Natural Circulation Cooling of a VHTR Core under Normal Operation and Accident Scenarios | |
| Repetto et al. | Thermal hydraulics behavior of a rod bundle with partially blocked area during the reflooding phase of the loss of cooling accident | |
| CN219242796U (en) | Valve internal part structure for high-temperature high-pressure difference environment | |
| Krovvidi et al. | Manufacturing experiences of large stroke welded disc bellows for nuclear applications | |
| Lee et al. | Preliminary Multi-Physics Analysis of a 2x2 Rod Array Using CUPID/GIFT Coupled Code | |
| Tuunanen et al. | PACTEL experiments for the investigation of passive safety injection systems of advanced light water reactors | |
| JP2000046979A (en) | Control rod for reactor | |
| Viljoen et al. | The re-evaluation of the AVR melt-wire experiment using modern methods with specific focus on bounding the bypass flow effects | |
| JP2009133853A (en) | Fuel rod design using internal spacer element and method of using the same | |
| Onder et al. | Assessment of ASSERT subchannel code for the canadian SCWR bundle at supercritical conditions | |
| Gerschenfeld et al. | Multiscale effects in sodium fast reactors: feedback from the open phase of the FFTF LOFWOS-13 test | |
| CN117906060A (en) | Device and method for improving outlet temperature of primary loop coolant of high-temperature gas cooled reactor | |
| Bueter et al. | Testing of the AP600 automatic depressurization system | |
| Liao et al. | A Thermal Hydraulic Phenomenon Based Review on the Validation Matrix of Several Reactor Safety Analysis Systems Codes | |
| 森平正之 et al. | Comparison of the fuel performance for advanced FBR cycle systems (FUJI project)(7) Result of 1st irradiation tests and PIE (Initial sintering test) |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |