CN113782230B - Nuclear reactor safety rod and nuclear reactor - Google Patents
Nuclear reactor safety rod and nuclear reactor Download PDFInfo
- Publication number
- CN113782230B CN113782230B CN202110997253.0A CN202110997253A CN113782230B CN 113782230 B CN113782230 B CN 113782230B CN 202110997253 A CN202110997253 A CN 202110997253A CN 113782230 B CN113782230 B CN 113782230B
- Authority
- CN
- China
- Prior art keywords
- section
- core
- reactor
- nuclear reactor
- safety rod
- 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
- 239000000446 fuel Substances 0.000 claims abstract description 31
- 239000002574 poison Substances 0.000 claims description 38
- 231100000614 poison Toxicity 0.000 claims description 38
- 238000005253 cladding Methods 0.000 claims description 9
- 239000000463 material Substances 0.000 claims description 7
- 230000009257 reactivity Effects 0.000 abstract description 12
- 238000000034 method Methods 0.000 description 9
- 238000010304 firing Methods 0.000 description 7
- 230000008569 process Effects 0.000 description 6
- 238000010586 diagram Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 5
- 239000011248 coating agent Substances 0.000 description 4
- 238000000576 coating method Methods 0.000 description 4
- 230000009471 action Effects 0.000 description 3
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- RKTYLMNFRDHKIL-UHFFFAOYSA-N copper;5,10,15,20-tetraphenylporphyrin-22,24-diide Chemical compound [Cu+2].C1=CC(C(=C2C=CC([N-]2)=C(C=2C=CC=CC=2)C=2C=CC(N=2)=C(C=2C=CC=CC=2)C2=CC=C3[N-]2)C=2C=CC=CC=2)=NC1=C3C1=CC=CC=C1 RKTYLMNFRDHKIL-UHFFFAOYSA-N 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000002035 prolonged effect Effects 0.000 description 2
- 239000004576 sand Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910001092 metal group alloy Inorganic materials 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000035484 reaction time Effects 0.000 description 1
- 239000003870 refractory metal Substances 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000001502 supplementing effect Effects 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The embodiment of the application discloses a nuclear reactor safety rod and a nuclear reactor, relates to the technical field of nuclear energy, ensures the safety of the reactor under the working condition of an emission drop accident, and solves the problem of insufficient reactivity of the nuclear reactor after the safety rod is pulled out of a reactor core. The nuclear reactor safety rod comprises a control reaction section and a following combustible section, wherein the control reaction section is used for being placed in a reactor core of a nuclear reactor to enable the reactor core to maintain a subcritical state; the following combustible section is consistent with the radial outer contour and the extending direction of the control reaction section, one end of the following combustible section is fixed with one end of the control reaction section, and the following combustible section has the same fuel as the reactor core; when the control reaction section is withdrawn from the core, the following combustible section is located in the core. The safety rod of the nuclear reactor is used for providing fuel for the safety rod part positioned in the reactor core after being extracted.
Description
Technical Field
The application relates to the technical field of nuclear energy, in particular to a nuclear reactor safety rod and a nuclear reactor.
Background
The reactor core of a nuclear reactor, also called the reactor active zone, is composed of fuel assemblies arranged in a grid of a certain grid, control rods are arranged in many space nuclear reactor core designs, and safety rods are one of the control rods and are used for guaranteeing the safety of the reactor under the condition of an emission drop accident, so that the reactor can maintain a subcritical state even under the condition of entering water, wet sand and the like.
At present, the safety rod in the related art generally adopts two operation modes, one is to draw the core back to enter the shielding body to become a part of shielding materials, and the other is to draw the safety rod forward to leave the reactor system and enter the outer space.
Although the safety of the reactor under the condition of the firing drop accident can be ensured by the action of the safety rod in the related art, the problem of insufficient reactivity of the nuclear reactor after the safety rod is pulled out of the reactor core cannot be solved.
Disclosure of Invention
The embodiment of the application provides a nuclear reactor safety rod-level nuclear reactor, which ensures the safety of the reactor under the working condition of an emission drop accident and solves the problem of insufficient reactivity of the nuclear reactor after a safety rod is extracted from a reactor core.
In order to achieve the above object, the technical solution of the embodiment of the present application is as follows:
the embodiment of the application provides a nuclear reactor safety rod, which comprises a control reaction section and a following combustible section, wherein the control reaction section is used for being placed in a reactor core of a nuclear reactor so as to maintain the reactor core in a subcritical state; the radial outline and the extending direction of the following combustible section are consistent with those of the control reaction section, one end of the following combustible section is fixed with one end of the control reaction section, and the following combustible section has the same fuel as the reactor core; the following burnable segment is located within the core after the control reaction segment is withdrawn from the core.
In the first aspect, the control reaction section and the following combustible section are arranged on the reactor safety rod, when the nuclear reactor does not react, the control reaction section of the safety rod is positioned in the reactor core of the nuclear reactor, so that the reactor core maintains a subcritical state, one end of the following combustible section is fixed with one end of the control reaction section, the radial outline and the extending direction are the same as those of the control reaction section, when the nuclear reactor is ready to react, the control reaction section is pumped out of the reactor core, the following combustible section is positioned in the reactor core, and the following combustible section has the same fuel as the reactor core, so that the following combustible section can continuously provide fuel for the reactor core of the nuclear reactor after the control reaction section is pumped out of the reactor core. The safety rod adopted in the related art is probably two cases, one is directly entering the shielding body after the safety rod is pulled out, and the other is directly entering the outer space after the safety rod is pulled out, so that fuel can not be provided for the reactor core after the safety rod is pulled out. Therefore, the safety rod of the reactor provided by the application has the advantages that the control reaction section and the following combustible section are arranged, so that after the control reaction section is pulled out, the following combustible section provides fuel for the reactor core, the safety of the reactor under the condition of an emission drop accident is ensured, and the problem of insufficient reactivity of the nuclear reactor after the safety rod is pulled out of the reactor core is solved.
Further, at least a part of the outer surface of the following combustible section is coated with a combustible poison layer, when the control reaction section is pumped out of the reactor core and then the following combustible section enters the reactor core, the peripheral coated combustible poison layer can reduce the power density of the central area of the reactor core, reduce the power non-uniformity factor of the reactor, and the released reactivity can also prolong the period of the reactor when the combustible poison layer is consumed.
Further, a part of the outer surface of the following combustible section is coated with a combustible poison layer, and when the control reaction section is pulled out of the reactor core and the following combustible section is positioned in the reactor core, the combustible poison layer corresponds to the central area of the reactor core. The burnable poison layer is arranged in the central area of the corresponding reactor core, so that the burnable poison layer is beneficial to the larger area where the released reactivity can radiate the reactor core when consumed.
Further, the burnable poison layer completely covers the outer surface of the corresponding position of the following burnable segment, so that after the burnable poison layer is consumed, the following burnable segment can also provide the same fuel as the reactor core for the nuclear reactor, and the reaction time of the nuclear reactor is prolonged.
Further, the control center area following the combustible section is provided with a concave part, the combustible poison layer is correspondingly coated at the concave part, the outer surface of the combustible poison layer is flush with the outer surface of the non-center area following the combustible section, the reaction section is conveniently controlled to be rapidly pulled out of the reactor core, and the combustible section can smoothly enter the reactor core.
Further, the nuclear reaction safety rod includes an envelope made of a high temperature resistant material, the control reaction section and the following combustible section being located within the envelope.
Further, the control reaction section and the following combustible section are both cylindrical structures.
In a second aspect, an embodiment of the present application provides a nuclear reactor structure, including a core, a through hole provided in a central position of the core, and a safety rod of the nuclear reactor provided in the embodiment of the first aspect, wherein the safety rod of the nuclear reactor is inserted into the through hole of the core.
The nuclear reactor structure provided by the embodiment of the application has the same technical effect as that of ensuring the safety of the reactor under the working condition of an emission drop accident due to the inclusion of the safety rod of any embodiment of the first aspect, and solves the problem of insufficient reactivity of the nuclear reactor after the safety rod is pulled out of the reactor core.
Further, the nuclear reactor comprises a shielding body, the shielding body is located at one end of the through hole of the reactor core, the shielding body is provided with an avoidance hole corresponding to the through hole, the extending direction of the avoidance hole is consistent with that of the through hole, when the control reaction section of the nuclear reactor safety rod is pulled out from the through hole, the control reaction section of the nuclear reactor safety rod extends into the avoidance hole, and the following combustible section of the nuclear reactor safety rod is located in the through hole. And the avoidance hole consistent with the extending direction of the reactor core through hole is formed in the shielding body, so that the reaction section can be controlled to enter the avoidance hole, and the reaction section becomes a part of the shielding body and provides a shielding function.
Further, the core includes a fuel assembly and a reflective layer disposed about the periphery of the fuel assembly.
Drawings
FIG. 1 is a state diagram of a safety rod of the 1 st mode of operation in the related art in the core;
FIG. 2 is a state diagram of the 1 st mode of operation safety rod in the related art being withdrawn from the core into the shield;
FIG. 3 is a state diagram of a 2 nd mode of operation safety rod of the related art in the core;
FIG. 4 is a state diagram of the 2 nd mode of operation safety rod extraction from the core in the related art;
FIG. 5 is a schematic view of a nuclear reactor safety rod according to the present application;
FIG. 6 is a cross-sectional view of a nuclear reactor safety rod of the present application;
FIG. 7 is one of the cross-sectional views of a nuclear reactor safety rod of the present application;
FIG. 8 is a cross-sectional view of a nuclear reactor safety rod of the present application;
FIG. 9 is a state diagram of a nuclear reactor safety rod of the present application in the core;
FIG. 10 is a schematic view of a nuclear reactor safety rod withdrawn from the core in accordance with the present application;
reference numerals illustrate:
1-a safety bar; 11-controlling the reaction section; 12-following the combustible section; 121-a recess; 1211-burnable poison layer; 13-cladding; 2-core; 21-a fuel assembly; 211-a central region; 212-a through hole; a 22-reflective layer; 3-shielding; 31-avoiding holes.
Detailed Description
It should be noted that, in the case of no conflict, the embodiments of the present application and the technical features of the embodiments may be combined with each other, and the detailed description in the specific embodiments should be interpreted as an explanation of the gist of the present application and should not be construed as unduly limiting the present application.
In order to make the objects, technical solutions and advantages of the embodiments of the present application more apparent, the specific technical solutions of the present application will be described in further detail below with reference to the accompanying drawings in the embodiments of the present application. The following examples are illustrative of the application and are not intended to limit the scope of the application.
In embodiments of the present application, the terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include one or more such feature. In the description of the embodiments of the present application, unless otherwise indicated, the meaning of "a plurality" is two or more.
Furthermore, in the embodiments of the present application, the terms "upper," "lower," "left," and "right," etc., are defined with respect to the orientation in which the components in the drawings are schematically disposed, and it should be understood that these directional terms are relative terms, which are used for descriptive and clarity with respect to each other, and which may vary accordingly with respect to the orientation in which the components in the drawings are disposed.
In embodiments of the present application, unless explicitly specified and limited otherwise, the term "connected" is to be construed broadly, and for example, "connected" may be either a fixed connection, a removable connection, or an integral unit; can be directly connected or indirectly connected through an intermediate medium.
In embodiments of the present application, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising one … …" does not exclude the presence of other like elements in a process, method, article, or apparatus that comprises the element.
In embodiments of the application, words such as "exemplary" or "such as" are used to mean serving as an example, instance, or illustration. Any embodiment or design described herein as "exemplary" or "e.g." in an embodiment of the present application is not to be taken as preferred or advantageous over other embodiments or designs. Rather, the use of words such as "exemplary" or "such as" is intended to present related concepts in a concrete fashion.
A nuclear reactor, also known as an atomic energy reactor, is a device that can sustain a controllable self-sustaining chain-type nuclear fission reaction to perform nuclear energy utilization. A nuclear reactor is called the heart of a nuclear power plant by properly arranging the nuclear fuel such that a process of self-sustaining chained nuclear fission can occur therein without supplementing a neutron source.
The reactor core of a nuclear reactor, also called a reactor active region, is composed of fuel assemblies arranged in a reactor grid having a certain grid, and includes a structure body, control rods, a shielding body, and the like in addition to the reactor core, wherein the structure body includes fuel cladding, the reactor grid for arranging the reactor core, a reactor vessel, and the like, and the shielding body is used for attenuating various rays generated by the reactor core, so that neutrons generated by the reactor core during the reactor reaction can be decelerated and absorbed by the shielding body. The control rods then act to compensate and adjust neutron reactivity and emergency shutdown in the reactor. The control rod can be divided into a compensation rod, an adjusting rod and a safety rod according to the action, and the safety rod is mainly used for guaranteeing the safety of the reactor under the working condition of an emission drop accident, so that the reactor can still maintain a subcritical state even under the conditions of entering water, wet sand and the like.
The embodiment of the application provides a nuclear reactor safety rod 1, as shown in fig. 5 and 9, which comprises a control reaction section 11 and a following combustible section 12, wherein the control reaction section 11 is used for being placed in a reactor core 2 of a nuclear reactor so as to maintain the reactor core 2 in a subcritical state; while the following combustible section 12 is consistent with the radial outer contour and the extending direction of the control reaction section 11, one end of the following combustible section 12 is fixed with one end of the control reaction section 11, and the following combustible section 12 has the same fuel as the reactor core 2; the following combustible segment 12 is located in the core 2 after the control reaction segment 11 is withdrawn from the core 2.
In the related art, the safety rod 1 is located in the core 2 at the time of firing of the spatial nuclear reactor, and the safety rod 1 is withdrawn from the core 2 when the firing is successfully prepared for start-up, and the reactor starts to operate under the action of the control mechanism. At this stage, the safety rod 1 is operated in two modes, one is shown in fig. 1 and 2, and when the safety rod 1 is positioned in the reactor core 2 during the firing, and when the reactor is ready to be started after the firing is successful, the safety rod 1 is pulled out of the reactor core 2 and enters the shielding body 3 to become a part of shielding material, thereby providing a partial shielding function. Another mode of operation is shown in fig. 3 and 4, in which the safety rod 1 is located in the core 2 during firing, and the safety rod 1 is withdrawn forward from the core 2 and out of the reactor system into outer space when the reactor is ready to start after the firing is successful. As shown in fig. 9 and 10, the technical solution provided by the present application is that a control reaction section 11 and a following combustible section 12 are disposed on a reactor safety rod 1, when no reaction occurs in the nuclear reactor, the control reaction section 11 of the safety rod 1 is located in the core 2 of the nuclear reactor, so that the core 2 maintains a subcritical state, one end of the following combustible section 12 is fixed to one end of the control reaction section 11, and has a radial outer contour and an extending direction, when the nuclear reactor is ready to react, the control reaction section 11 is withdrawn from the core 2, and the following combustible section 12 falls in the core 2, and because the following combustible section 12 has the same fuel as the core 2, the following combustible section 12 can also continue to provide fuel for the core 2 of the nuclear reactor after the control reaction section 11 is withdrawn from the core 2. After the control reaction section 11 is pulled out, the control reaction section 12 falls into the reactor core 2 to provide fuel for the reactor core 2, so that the safety of the reactor under the condition of the accident of falling during the launching is ensured, and the problem that the nuclear reactor has insufficient reactivity after the safety rod 1 is pulled out of the reactor core 2 is solved.
In some embodiments, as shown in fig. 7 and 10, in the nuclear reactor, the burnable poison has advantages of compensating for the reactivity of the nuclear reactor, prolonging the life of the core 2, reducing the number of movable control rods and reducing the power density of the central region 211 of the core 2, and reducing the power distribution of the reactor, and thus, it is preferable that at least a part of the outer surface cladding burnable poison layer 1211 is provided at the following burnable segment 12 in the technical scheme of the nuclear reactor safety rod 1 of the present application, and the peripherally cladding burnable poison layer 1211 not only can reduce the power density of the central region 211 of the core 2, reduce the power non-uniformity factor of the reactor, but also can prolong the period of the reactor when the burnable poison layer 1211 is consumed when the following burnable segment 12 falls into the core 2 after the reaction segment 11 is controlled to be withdrawn from the core 2.
Illustratively, as shown in fig. 9 and 10, the following burnable segment 12 has the same material as the fuel, and the burnable poison may reduce the power density of the central region 211 of the core 2, reduce the power non-uniformity factor of the reactor, and if the outer surface of the following burnable segment 12 is entirely covered with the burnable poison layer 1211, the following burnable segment 12 may be prevented from providing the fuel to the core 2. If the outer surface of the installation part of the following combustible segment 12 is coated with the burnable poison layer 1211, so that the combination of the two effects is optimized, the following combustible segment 12 can supply fuel to the reactor core 2, the loading capacity of the fuel is reduced, the weight and the volume of the reactor are reduced, and the burnable poison layer 1211 can reduce the power non-uniformity factor of the reactor, therefore, the technical scheme provided by the application is that a part of the outer surface of the following combustible segment 12 is coated with the burnable poison layer 1211, when the reaction segment 11 is controlled to be withdrawn from the reactor core 2 and the following combustible segment 12 is positioned in the reactor core 2, the burnable poison layer 1211 corresponds to the central area 211 of the reactor core 2, and the burnable poison layer 1211 is arranged in the central area 211 corresponding to the reactor core 2. The area of the core 2 where the reactivity released when the burnable poison layer 1211 is consumed can radiate is larger and wider, and at the same time, the two ends of the following burnable segment 12 are not covered by the burnable poison layer 1211, and when the burnable poison layer 1211 is consumed, the two ends of the following burnable segment 12 can also provide fuel for the core 2, so that the effect and function are maximized.
In other embodiments, as shown in fig. 7 and 10, it is possible that the burnout layer 1211 coats a part of the following burnout section 12 and also coats the whole section of the following burnout section 12, if the outer surface of the corresponding position of the following burnout section 12 is incompletely coated, there is a phenomenon that a part of coating and a part of coating are not completely coated, so that the outer surface of the corresponding position of the burnout layer 1211 cannot form continuous coating, which is unfavorable for uniform consumption of the burnout layer 1211, if the burnout layer 1211 is completely coated on the outer surface of the corresponding position of the following burnout section 12, the outer surface of the burnout layer 1211 forms complete coating, when the reaction section 11 is withdrawn from the core 2, the outer surface of the following burnout section 12 enters the core 2, the burnout layer 1211 is uniformly contacted with the core 2, which is favorable for uniform consumption of the burnout layer 1211, and after uniform consumption, the following burnout section 12 is completely exposed, which is the same as the core 2, and the time of the nuclear reactor reaction is prolonged.
It should be noted that, as shown in fig. 7 and 10, if the burnable poison layer 1211 wraps the entire section following the burnable section 12, it is ensured that the outer contour of the burnable section 12 and the reaction control section are consistent. In order to maximize the effect, a part of the outer surface of the following burnable segment 12 is coated with the burnable poison layer 1211, and when the control reaction segment 11 is withdrawn from the core 2 and the following burnable segment 12 is located in the core 2, the burnable poison layer 1211 corresponds to the central region 211 of the core 2, and the burnable poison layer 1211 is disposed in the central region 211 corresponding to the core 2. If wrapped around the outer periphery of the control center region 211 of the following burnable segment 12, the outer contour of the center region 211 of the wrapped burnable poison layer 1211 is larger than the non-center region 211 of the following burnable segment 12, and bosses are provided on two sections of the center region 211 of the following burnable segment 12 to provide resistance to the following burnable segment 12 entering the core 2 when the control reaction segment 11 is withdrawn from the core 2. In order to solve this problem, the present application proposes a technical solution, in which the control area of the following combustible segment 12 is provided with the concave portion 121, the corresponding concave portion 121 is covered with the burnable poison layer 1211, the outer surface of the burnable poison layer 1211 is flush with the outer surface of the non-central area 211 of the following combustible segment 12, the whole section of the following combustible segment 12 is consistent with the outer contour reflecting the control area, and after the control reaction segment 11 is withdrawn from the reactor core 2, the following combustible segment 12 can smoothly and rapidly enter the reactor core 2 without overcoming the resistance caused by the boss formed by covering the burnable poison layer 1211 on the control central area 211 of the following combustible segment 12.
Specifically, as shown in fig. 8, an envelope 13 should be disposed at the periphery of the nuclear reaction safety rod 1, and the control reaction section 11 and the following combustible section 12 should be located in the envelope 13, so that it is convenient to prevent reaction with the outside during the manufacturing and use process, and impurities adverse to the nuclear reaction are generated. It should be noted that, the material of the cladding 13 may be selected according to the operating temperature of the reactor, so as to avoid the excessive reaction temperature of the nuclear reactor from melting the cladding 13, and the cladding 13 is generally made of high-temperature resistant stainless steel or refractory metal alloy.
For example, as shown in fig. 6 and 7, when the nuclear reactor is ready for reaction, the control reaction section 11 needs to be withdrawn from the reactor core 2, so that the following combustible section 12 enters the reactor core 2, during the withdrawal process, the friction between the reactor core 2 and the reactor core 2 needs to be overcome, and a part of the friction depends on the shapes of the control reaction section 11 and the following combustible section 12, if the shapes of the control reaction section 11 and the following combustible section 12 are set to be tetragonal, the outer surfaces of the tetragonal have corners, during the withdrawal of the reactor core 2, the friction between the control reaction section 11 and the following combustible section 12 needs to be additionally overcome, and if the shapes of the control reaction section 11 and the following combustible section 12 are set to be spherical, the outer surfaces of the spherical are smoother, no corners, and the friction between the spherical outer surfaces and the reactor core 2 does not need to be additionally overcome, but the contact surfaces of the spherical outer surfaces and the reactor core 2 are smaller, so that the effect of the following combustible section 12 in the reactor core 2 cannot be exerted. If the control reaction section 11 and the following combustible section 12 are designed to be cylindrical structures, the angles similar to the tetragonal structures are not provided, the friction force of the angles does not need to be overcome additionally, and the contact surface between the outer surface of the sphere and the reactor core 2 is not smaller like the contact surface, preferably, the technical scheme provided by the application is that the control reaction section 11 and the following combustible section 12 are both arranged to be cylindrical structures.
Further, as shown in fig. 9 and 10, the present application further provides a reactor structure, which includes a core 2 and a safety rod 1 of a nuclear reactor, and a through hole 212 is provided in a central position of the core 2, and the safety rod 1 of the nuclear reactor is inserted into the through hole 212 of the core 2, so that the safety rod 1 has the safety of ensuring that the reactor is dropped under the working condition when the reactor is launched, and the problem of insufficient reactivity of the nuclear reactor after the safety rod 1 is pulled out of the core 2 is solved. Generally, the safety rod 1 is prepared before the reactor core 2 is prepared, the safety rod 1 is directly placed in the reactor core 2 when the reactor core 2 is prepared, the reactor preparation time is long, and the friction force required to be overcome when the safety rod 1 is extracted is large. If the through hole 212 is provided in the central region 211 of the core 2, the core 2 and the safety rod 1 are manufactured at the same time, and finally the safety rod 1 is inserted into the through hole 212 of the core 2. The manufacturing time of the nuclear reactor is saved.
It should be noted that, as shown in fig. 10, the nuclear reactor further includes a shielding body 3 in addition to the core 2 and the safety rod 1, the shielding body 3 is disposed at one end of the through hole 212 of the core 2, and a relief hole 31 is disposed at a position of the shielding body 3 corresponding to the through hole 212, the extending direction of the relief hole 31 is consistent with that of the through hole 212, when the control reaction section 11 of the nuclear reactor is withdrawn from the through hole 212, the control reaction section 11 of the safety rod 1 of the nuclear reactor extends into the relief hole 31, and the following combustible section 12 of the safety rod 1 of the nuclear reactor is located in the through hole 212. The shielding body 3 is provided with the avoidance holes 31 which are consistent with the extending direction of the through holes 212 of the reactor core 2, thereby being beneficial to controlling the reaction section 11 to enter the avoidance holes 31 and become a part of the shielding body 3 to provide a shielding function.
Further, as shown in fig. 10, the fuel assemblies 21 in the core 2 may leak neutron substances during the nuclear reactor reaction, resulting in energy waste of the nuclear reactor reaction, and failing to meet the required nuclear energy requirement. Therefore, the reflection layer 22 is arranged on the periphery of the fuel assembly 21 in the reactor core 2, and the material which surrounds the outside of the reactor core 2 and is used for reflecting neutrons leaked from the fuel assembly 21 can reduce the leakage of neutrons in the fuel assembly 21, reduce fuel, improve the average output power of the reactor and prolong the running life of the nuclear reactor.
The above description is not intended to limit the scope of the application, but is intended to cover any modifications, equivalents, and improvements within the spirit and principles of the application.
Claims (6)
1. A nuclear reactor safety rod, comprising:
a control reaction section for placement within a core of a nuclear reactor to maintain the core in a subcritical state;
a following combustible section having a radial outer contour and an extension direction consistent with those of the control reaction section, one end of the following combustible section being fixed to one end of the control reaction section, the following combustible section having the same fuel as the core;
when the control reaction section is withdrawn from the reactor core, the following combustible section is positioned in the reactor core;
a part of the outer surface of the following combustible section is coated with a combustible poison layer, and when the control reaction section is pulled out from the reactor core and the following combustible section is positioned in the reactor core, the combustible poison layer corresponds to the central area of the reactor core;
the control center area of the following combustible section is provided with a concave part, the combustible poison layer is correspondingly coated at the concave part, and the outer surface of the combustible poison layer is flush with the outer surface of the non-center area of the following combustible section.
2. The nuclear reactor safety rod of claim 1, comprising an cladding made of a high temperature resistant material, the control reaction section and the following combustible section being located within the cladding.
3. The nuclear reactor safety rod according to any one of claims 1-2, wherein the control reaction section and the following combustible section are both cylindrical structures.
4. A nuclear reactor structure, comprising:
the reactor core is provided with a through hole at the center;
the nuclear reactor safety rod according to any one of claims 1 to 3, wherein the nuclear reactor safety rod is inserted into the through hole.
5. The nuclear reactor structure of claim 4, comprising a shield positioned at one end of the through hole of the core, the shield having a relief hole corresponding to the through hole, the relief hole extending in a direction that is coincident with the direction of extension of the through hole, the control reaction section of the safety rod extending into the relief hole after the control reaction section of the safety rod is withdrawn from the through hole, the follower combustible section of the safety rod being positioned within the through hole.
6. The nuclear reactor structure of claim 5, wherein the core comprises a fuel assembly and a reflective layer disposed on a periphery of the fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110997253.0A CN113782230B (en) | 2021-08-27 | 2021-08-27 | Nuclear reactor safety rod and nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110997253.0A CN113782230B (en) | 2021-08-27 | 2021-08-27 | Nuclear reactor safety rod and nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113782230A CN113782230A (en) | 2021-12-10 |
| CN113782230B true CN113782230B (en) | 2023-11-10 |
Family
ID=78839717
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110997253.0A Active CN113782230B (en) | 2021-08-27 | 2021-08-27 | Nuclear reactor safety rod and nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113782230B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114530265B (en) * | 2022-01-11 | 2024-03-22 | 中国原子能科学研究院 | Safety rod for nuclear reactor and nuclear reactor |
| CN114530266B (en) * | 2022-01-24 | 2024-05-14 | 中国原子能科学研究院 | Safety rod and space nuclear reactor |
Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04264292A (en) * | 1991-02-18 | 1992-09-21 | Hitachi Ltd | Control rod with fuel follower, method and apparatus for driving control rod, nuclear power plant and method of controlling operation of reactor |
| CN101572127A (en) * | 2008-04-28 | 2009-11-04 | 中科华核电技术研究院有限公司 | Nuclear fuel rod, nuclear fuel component and nuclear reactor core |
| KR101482018B1 (en) * | 2013-11-15 | 2015-01-14 | 한국원자력연구원 | Space Power Reactor |
| JP2016070743A (en) * | 2014-09-29 | 2016-05-09 | 株式会社東芝 | Fast neutron reactor core, fast neutron reactor and fast neutron reactor core design method |
| CN109119174A (en) * | 2018-09-06 | 2019-01-01 | 中国原子能科学研究院 | A kind of heat-pipe cooling type nuclear reactor power-supply system based on uranium hydrogen zirconium fuel and static heat to electricity conversion |
| CN208315210U (en) * | 2018-06-14 | 2019-01-01 | 中国工程物理研究院核物理与化学研究所 | A kind of rotation control rod |
| CN110603602A (en) * | 2017-05-09 | 2019-12-20 | 西屋电气有限责任公司 | Annular nuclear fuel pellet with discrete burnable absorber pins |
| CN110634579A (en) * | 2019-10-25 | 2019-12-31 | 华南理工大学 | Fuel and strong neutron absorbing material integrated compact reactor core structure |
| CN112133458A (en) * | 2020-08-24 | 2020-12-25 | 中国原子能科学研究院 | Passive autonomous control safety rod mechanism for space nuclear reactor |
| CN112216410A (en) * | 2020-08-24 | 2021-01-12 | 中国原子能科学研究院 | Multifunctional safety rod for space nuclear reactor |
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
-
2021
- 2021-08-27 CN CN202110997253.0A patent/CN113782230B/en active Active
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH04264292A (en) * | 1991-02-18 | 1992-09-21 | Hitachi Ltd | Control rod with fuel follower, method and apparatus for driving control rod, nuclear power plant and method of controlling operation of reactor |
| CN101572127A (en) * | 2008-04-28 | 2009-11-04 | 中科华核电技术研究院有限公司 | Nuclear fuel rod, nuclear fuel component and nuclear reactor core |
| KR101482018B1 (en) * | 2013-11-15 | 2015-01-14 | 한국원자력연구원 | Space Power Reactor |
| JP2016070743A (en) * | 2014-09-29 | 2016-05-09 | 株式会社東芝 | Fast neutron reactor core, fast neutron reactor and fast neutron reactor core design method |
| CN110603602A (en) * | 2017-05-09 | 2019-12-20 | 西屋电气有限责任公司 | Annular nuclear fuel pellet with discrete burnable absorber pins |
| CN208315210U (en) * | 2018-06-14 | 2019-01-01 | 中国工程物理研究院核物理与化学研究所 | A kind of rotation control rod |
| CN109119174A (en) * | 2018-09-06 | 2019-01-01 | 中国原子能科学研究院 | A kind of heat-pipe cooling type nuclear reactor power-supply system based on uranium hydrogen zirconium fuel and static heat to electricity conversion |
| CN110634579A (en) * | 2019-10-25 | 2019-12-31 | 华南理工大学 | Fuel and strong neutron absorbing material integrated compact reactor core structure |
| CN112133458A (en) * | 2020-08-24 | 2020-12-25 | 中国原子能科学研究院 | Passive autonomous control safety rod mechanism for space nuclear reactor |
| CN112216410A (en) * | 2020-08-24 | 2021-01-12 | 中国原子能科学研究院 | Multifunctional safety rod for space nuclear reactor |
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113782230A (en) | 2021-12-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN113782230B (en) | Nuclear reactor safety rod and nuclear reactor | |
| JP4313204B2 (en) | Compact pressurized water reactor | |
| US20220367070A1 (en) | Standing wave nuclear fission reactor and methods | |
| JP2823053B2 (en) | Fuel rods for reactor fuel assemblies | |
| JPS61111488A (en) | Fuel load for core of nuclear reactor and operating method thereof | |
| CN112669999B (en) | Liquid-solid dual fuel space nuclear reactor power supply | |
| CN112133458A (en) | Passive autonomous control safety rod mechanism for space nuclear reactor | |
| CN101128885B (en) | Fuel bundle for pressurized-water reactor and method of designing fuel bundle | |
| RU2173484C1 (en) | Fast reactor using heavy liquid-metal coolant | |
| JP4351872B2 (en) | Fast reactor with no-exchange-reflector control system | |
| JP2007504442A (en) | Reactor operation method | |
| JP4101424B2 (en) | Reflector-controlled fast breeder reactor | |
| JP7394047B2 (en) | Core structure and reactor | |
| KR101617299B1 (en) | Fast nuclear reactor | |
| JP3950392B2 (en) | Reactor | |
| EP4141890A1 (en) | Fuel element for a water-cooled water-moderated nuclear reactor | |
| CN114530266B (en) | Safety rod and space nuclear reactor | |
| JP7495871B2 (en) | Fast reactor and method for operating control rods in fast reactor | |
| RU2680252C1 (en) | Heat-dividing element of a nuclear energy reactor on fast neutrons | |
| CN113270207B (en) | Short-life-period air-cooled micro-reactor performance optimization structure | |
| US20200343006A1 (en) | Fuel Element, Fuel Assembly, and Core | |
| RU2236712C2 (en) | Control fuel assembly of pressurized water reactors | |
| EP0329985B1 (en) | Nuclear reactor operating method with extended life cycle | |
| JP2731599B2 (en) | Boiling water reactor and its fuel loading method | |
| CN116665929A (en) | Fast reactor component with reactivity compensation function |
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 |