CN114628050A - Reactor core structure and spatial nuclear reactor - Google Patents

Reactor core structure and spatial nuclear reactor Download PDF

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Publication number
CN114628050A
CN114628050A CN202210069356.5A CN202210069356A CN114628050A CN 114628050 A CN114628050 A CN 114628050A CN 202210069356 A CN202210069356 A CN 202210069356A CN 114628050 A CN114628050 A CN 114628050A
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China
Prior art keywords
core
control
reactor
control drum
fuel
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Pending
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CN202210069356.5A
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Chinese (zh)
Inventor
庄乃亮
宋永念
汤晓斌
赵行斌
杨晨皓
赵艺淇
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Nanjing University of Aeronautics and Astronautics
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Nanjing University of Aeronautics and Astronautics
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Application filed by Nanjing University of Aeronautics and Astronautics filed Critical Nanjing University of Aeronautics and Astronautics
Priority to CN202210069356.5A priority Critical patent/CN114628050A/en
Publication of CN114628050A publication Critical patent/CN114628050A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • 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
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The application discloses reactor core structure includes: a core active region in which a first fuel region is disposed; the heat exchange structure is arranged in the core active area and used for leading out heat; a reflective layer covering the outside of the core active region; the first control drum is rotatably arranged in the reflecting layer, a first absorber is arranged on the side surface of the first control drum, and a gap is formed between the first control drum and the core active area; the second control drum is rotatably arranged in the reflecting layer, and a second absorber and a second fuel area are arranged on the side surface of the second control drum at intervals; wherein, the core active area is provided with an accommodation groove, and the second control drum part is embedded in the accommodation groove and can rotate relative to the accommodation groove. By adopting the reactor core and the method, the axial size of the reactor core and the whole reactor can be reduced, the capability of rapidly stopping the reactor when the reactor encounters an emergency accident can be improved, and the safety of the reactor is further improved.

Description

Reactor core structure and spatial nuclear reactor
Technical Field
The application relates to the technical field of nuclear reactors, in particular to a reactor core structure and a nuclear reactor.
Background
The space nuclear reactor is a reactor for providing energy for a spacecraft, and reactivity control of the space nuclear reactor is generally realized by control rods, control drums and the like so as to ensure the safety of the reactor core. However, the control of reactivity by using control rods can increase the axial size of the reactor core, and the power distribution can be influenced when the control rods are inserted into the reactor core; the control drums are adopted for reactivity control, when shutdown is needed in emergency, a plurality of control drums are needed to rotate in a combined mode, difficulty is high, and the shutdown control capability is weak. Therefore, the above control methods have great disadvantages.
Disclosure of Invention
In order to reduce the axial dimension of a reactor core structure and improve the capability of realizing rapid shutdown when the reactor encounters an emergency accident, the application provides a reactor core structure and a spatial nuclear reactor, and the following technical scheme is adopted:
in a first aspect, the present application provides a core structure comprising:
a core active region in which a first fuel region is disposed;
the heat exchange structure is arranged in the core active area and used for leading out heat;
a reflective layer covering the outside of the core active region;
the first control drum is rotatably arranged in the reflecting layer, a first absorber is arranged on the side surface of the first control drum, and a gap is formed between the first control drum and the core active area; and
the second control drum is rotatably arranged in the reflecting layer, and a second absorber and a second fuel area are arranged on the side surface of the second control drum at intervals;
wherein, be provided with the holding tank on the core active area, the second control drum part imbeds in the holding tank to can rotate relatively the holding tank.
Optionally, the diameter of the second control drum is larger than the diameter of the first control drum.
Optionally, the first control drum and the second control drum are provided with a plurality of drums, and the included angles between the adjacent second control drums are the same.
Optionally, at least one first control drum is arranged between adjacent second control drums;
the first control drums between the adjacent second control drums are uniformly distributed along the circular arcs between the adjacent second control drums.
Optionally, the first absorber and the second absorber are each provided in an arcuate plate-like structure.
Optionally, the first and second absorbents have an angle of wrap of 90 ° to 135 °.
Optionally, the enrichment of the fuel in the second fuel zone is greater than the enrichment of the fuel in the first fuel zone.
Optionally, the heat exchange structure is a plurality of heat pipes inserted in the core active area.
Optionally, the heat exchange structure is a cooling channel disposed between the core active region and the reflective layer.
In a first aspect, the present application provides a spatial nuclear reactor including a core structure as claimed in any one of the first aspects.
As described above, when the core structure according to the present invention is applied to a spatial nuclear reactor, the first absorber and the second absorber are both in a state closest to the core active region before the reactor is started, that is, the first absorber faces the core active region, and the second absorber is embedded in the holding tank.
When the reactor is started, the second control drum is firstly rotated to enable the second absorber to be far away from the core active area, the second fuel area is rotated to the accommodating groove and is meshed with the first fuel area, at the moment, the second fuel area and the first fuel area react together, the second absorber has the weakest absorption capacity on neutrons, and the reactor is close to a critical state, namely, the generation rate and the consumption rate of the neutrons in the reactor core are approximately equal. And then the first control drum is rotated to adjust the distance between the first absorber and the core active area, so that the reactor reaches a critical state and is increased to a rated power, and the reactor enters an operating state. In the operation process of the reactor, the second control drum is kept in a static state, fuel consumption compensation is carried out according to the actual operation condition, the full power of the reactor is stably operated by adjusting the state of the first control drum, and heat is led out and the reactor core is cooled by the heat exchange structure in the operation process.
When an emergency happens, the second control drum is rapidly rotated, so that the second absorber is embedded into the accommodating tank, neutrons in the core active area are rapidly absorbed, and the aim of rapidly reducing reactivity is fulfilled. And finally, adjusting the first control drum to enable the first absorber to face the core active area, so as to realize reactor shutdown.
In this application, through the linkage cooperation of first control drum and second control drum, under the reactor running state, rotate first control drum, adjust the reactivity of reactor operation in-process. When an emergency accident happens, the second control drum is rapidly rotated, the second fuel area is separated from the first fuel area, and meanwhile, the second absorber is close to the core active area to rapidly absorb the center, so that the purpose of rapidly stopping the reactor is achieved. By adopting the mode, the axial sizes of the reactor core and the reactor are reduced, the disturbance to the power distribution in the reactor core is reduced, the reactor can be quickly stopped under the condition of emergency accidents, and the safety of the reactor is improved.
Drawings
In order to more clearly illustrate the technical solutions of the present application, the drawings needed to be used in the description of the embodiments are briefly introduced below, it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for a person skilled in the art to obtain other drawings based on these drawings without exceeding the protection scope of the present application.
FIG. 1 is a schematic view of a core structure according to an embodiment of the present application;
FIG. 2 is a cross-sectional view taken along line A-A of FIG. 1;
FIG. 3 is a three-dimensional schematic representation of the positional relationship of the second control drum to the core active area;
FIG. 4 is a state diagram of the core structure before or after reactor startup or shutdown;
FIG. 5 is a state diagram of the core structure during reactor operation;
FIG. 6 is another schematic of a heat exchange configuration.
In the drawings, reference numerals refer to the following:
1. a core active area; 11. a first fuel zone; 12. accommodating grooves;
2. a heat exchange structure;
3. a reflective layer;
4. a first control drum; 41. a first absorbent;
5. a second control drum; 51. a second absorbent body; 52. a second fuel zone.
Detailed Description
The technical solutions of the present application will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present application, and it is obvious that the described embodiments are some, not all, of the embodiments of the present application. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present application.
In order to facilitate understanding of the technical solutions of the present application and to more clearly embody the inventive concepts of the present application, a reactivity control scheme of an existing spatial nuclear reactor will first be briefly described.
Reactivity control is performed in the form of control rods. The reactivity is controlled by adjusting the depth of insertion of the control rods into the core. In this way, the axial dimensions of the core and the entire vessel are increased due to the large axial movement distance of the control rods along the core, and the insertion of the control rods into the core also affects the power distribution in the core, which is detrimental to the power output in the core.
Reactivity control was performed in the form of a control drum. The reactor core is characterized in that a reflecting layer is arranged on the outer side of the reactor core, a control drum is rotatably arranged in the reflecting layer, the reactivity is adjusted by changing the position of a neutron absorber on the control drum, the disturbance of the mode on the power distribution in the reactor core is small, but the neutron absorber on the control drum is not inserted into the reactor core, so the reactivity adjusting capacity of the control drum is weak, a plurality of control drums are required to rotate in a combined mode during shutdown, and the difficulty of controlling the reactivity by using the control drum is large under the condition of encountering an emergency accident.
In order to overcome the defects of the two control schemes, a mode of combining the control rods and the control drums is proposed, the reactor core power is regulated through the control drums in the reactor operation process, and when the reactor needs to be shut down in case of emergency, the reactivity is regulated through the control rods so as to enhance the safety of the reactor, but the axial sizes of the reactor core and the reactor vessel are still increased by adopting the mode. Therefore, the above methods have certain disadvantages.
Referring to fig. 1 and 2, a core structure disclosed in an embodiment of the present application includes a core active area 1, a heat exchange structure 2, a reflective layer 3, a first control drum 4, and a second control drum 5.
The core active region 1 includes cladding and a first fuel region 11 disposed within the cladding. The cladding acts as a carrier for the first fuel region 11 to mount, which may be a shell. The first fuel region 11 may be filled with liquid fuel or solid fuel. When the fission reaction occurs, the first fuel region 11 generates fission heat.
The heat exchange structure 2 is arranged in the core active region 1 and used for guiding out heat generated by fission reaction and cooling the core.
The reflecting layer 3 covers the outer side of the cladding of the core active region 1 and is used for reducing the leakage of neutrons in the core. Optionally, BeO is used as the material of the reflective layer 3 in this embodiment.
The first control drum 4 is rotatably disposed in the reflective layer 3, and in the embodiment of the present invention, the first control drum 4 is a columnar body, the axis of the first control drum 4 is parallel to the axis of the core active region 1, and a gap is formed between the first control drum 4 and the outer surface of the core active region 1. The first absorber 41 is provided on a side surface of the first control drum 4, and the first control drum 4 is rotated to change a distance between the first absorber 41 and the core active region 1.
Referring to fig. 1 and 3, the second control drum 5 is rotatably disposed in the reflective layer 3, and in the embodiment of the present invention, the second control drum 5 is a cylindrical body, and the axis of the second control drum 5 is parallel to the axis of the core active region 1. It should be noted that the side surface of the cladding of the core active region 1 is provided with the accommodation groove 12 that is fitted with the second control drum 5, the second control drum 5 is partially fitted into the accommodation groove 12, and the portion of the second control drum 5 fitted into the accommodation groove 12 is fitted to the inner wall of the accommodation groove 12 so as to be rotatable relative to the accommodation groove 12.
The second control drum 5 is provided with a second absorber 51 and a second fuel zone 52 at intervals on the side surface thereof. Alternatively, the second absorber 51 and the second fuel zone 52 are disposed symmetrically with respect to the axis of the second control drum 5. The second control drum 5 is rotated to change the relative positions between the second absorber 51 and the second fuel region 52 and the core active region 1 so that the second absorber 51 or the second fuel region 52 is located in the accommodation groove 12.
Optionally, the main materials of the first control drum 4 and the second control drum 5 in the embodiment of the present application are BeO. The first absorber 41 and the second absorber 51 are both B4And C, coating.
Liquid fuels, which may be LiF and UF in composition, may be used in both the first fuel zone 11 and the second fuel zone 524A mixture of (a). Alternatively, in other possible embodiments, the first fuel zone 11 and the second fuel zone 52 may also use solid fuel, and the solid fuel may have a composition of UO2UN, etc.
When the core structure in the present application is applied to a spatial nuclear reactor, the first control drum 4 and the second control drum 5 are in the states shown in fig. 4 before the reactor is started, and both the first absorber 41 and the second absorber 51 are in the states closest to the core active region 1, that is, the first absorber 41 faces the core active region 1, and the second absorber 51 is embedded in the holding tank 12, at this time, the first control drum 4 and the second control drum 5 have the maximum ability to absorb neutrons, and the core remains in the subcritical state. It should be understood that the subcritical state described in the present application is a state in which the rate of production of neutrons in the core active region 1 is smaller than the rate of disappearance of neutrons.
Referring to fig. 5, when the reactor is started, the second control drum 5 is first rotated to move the second absorber 51 away from the core active region 1, the second fuel region 52 is rotated into the holding tank 12, the second fuel region 52 is engaged with the first fuel region 11, at this time, the second fuel region 52 and the first fuel region 11 react together, the second absorber 51 has the weakest absorption capacity for neutrons, and the reactor is close to a critical state, that is, the production rate and the consumption rate of neutrons in the reactor core are nearly equal. And then the first control drum 4 is rotated to adjust the distance between the first absorber 41 and the core active area 1, so that the reactor reaches a critical state and is lifted to a rated power, and the reactor enters an operating state. In the operation process of the reactor, the second control drum 5 keeps the state shown in fig. 5, the fuel consumption compensation is carried out according to the actual operation condition, the full power stable operation of the reactor is realized by adjusting the state of the first control drum 4, and the heat export and the core cooling are realized through the heat exchange structure 2 in the operation process.
In the event of an emergency, the second control drum 5 is rapidly rotated to insert the second absorber 51 into the housing tank 12, thereby rapidly absorbing neutrons in the core active region 1 and rapidly reducing reactivity. Finally, the first control drum 4 is adjusted so that the first absorber 41 is directed towards the core active zone 1, so as to effect a reactor shutdown, i.e. a return to the condition shown in fig. 4.
In this application, through the linkage cooperation of first control drum 4 and second control drum 5, under the reactor running state, rotate first control drum 4, adjust the reactivity of reactor operation in-process. When an emergency happens, the second control drum 5 is rotated rapidly, the second fuel area 52 is separated from the first fuel area 11, and simultaneously, the second absorber 51 approaches the core active area 1 to absorb the fuel rapidly, so that the purpose of rapid shutdown is achieved. By adopting the mode, the axial sizes of the reactor core and the reactor are reduced, the disturbance to the power distribution in the reactor core is reduced, the reactor can be quickly stopped under the condition of emergency accidents, and the safety of the reactor is improved.
According to an alternative solution of the embodiment of the present application, the diameter of the second control drum 5 is larger than the diameter of the first control drum 4. Since the second control drum 5 is partially embedded in the core active region 1, the diameter of the second control drum 5 is increased, and the center distance between the second control drum 5 and the core active region 1 is increased. On the other hand, when the second absorber 51 rotates toward the core center, the second absorber 51 is closer to the core active region 1, and has a higher neutron absorbing capacity; on the other hand, when the second fuel region 52 is rotated to a side away from the core active region 1, the second fuel region is farther from the core active region 1, so that the probability of occurrence of a fission reaction is lower, the number of neutrons generated by reactor fission is smaller, and therefore, the reactivity adjustment capability of the second control drum 5 is stronger.
Referring to fig. 1, as an alternative solution of the embodiment of the present application, a plurality of first and second steering drums 4 and 5 are provided along the circumferential direction, and the number of the first and second steering drums 4 and 5 and the relative positions thereof are determined according to actual conditions. The included angle between adjacent second control drums 5 is the same, namely when the second control drums 5 are provided in plurality, the second control drums 5 are uniformly distributed along the circumferential direction, so that when the second control drums 5 rotate, the power distribution in the core is more uniform.
Alternatively, the number of the second steering drums 5 is smaller than the number of the first steering drums 4, and at least one first steering drum 4 is provided between the adjacent second steering drums 5. When the number of the first control drums 4 between the adjacent second control drums 5 is two or more, the first control drums 4 between the adjacent second control drums 5 are uniformly distributed along the circular arc between the adjacent second control drums 5. It should be understood that the circular arc between the second steering drums 5 as described herein means a portion of a virtual circle formed by the axial centers of the plurality of second steering drums 5 when they are uniformly distributed in the circumferential direction. It should be noted that the virtual circle formed by the axis of the first control drum 4 and the virtual circle formed by the axis of the second control drum 5 may or may not overlap each other, depending on the actual spatial position.
When the first control drums 4 are uniformly distributed between the adjacent second control drums 5, the power distribution in the reactor core is more uniform, and the reactivity difference of different positions in the reactor core is prevented from forming too large.
Referring to fig. 1, in one embodiment of the present application, two second control drums 5 and four first control drums 4 are provided, the included angles between the adjacent drums are all 60 °, and the two second control drums 5 and the four first control drums 4 are distributed in a central symmetry manner.
According to an alternative technical scheme of the embodiment of the application, the first absorber 41 and the second absorber 51 are both arc-shaped plate-shaped structures and are B with the thickness of 1cm4And the coating C is coated on the side surface of the first control drum 4 or the second control drum 5. The arc-shaped plate-shaped structure is matched with the shape of the first control drum 4 or the second control drum 5, so that the area of the first absorber 41 or the second absorber 51 can be increased, and the neutron absorption capacity is further enhanced.
Optionally, the wrap angle of the first absorber 41 and the second absorber 51 is set at 90 ° -135 °. It should be noted that, taking the first absorber 41 as an example, the wrap angle described herein refers to an angle formed by a line connecting both ends of the first absorber 41 and the axis of the first control drum 4. In some implementations of embodiments of the present application, the wrap angle is set to 120 °.
According to an alternative embodiment of the present application, the enrichment of the fuel in the second fuel zone 52 is greater than the enrichment of the fuel in the first fuel zone 11. It will be appreciated that the uranium element in the fuel consists essentially of U235And U238Two isotopes, the enrichment of the fuel thus referred to in this application as U235Mass ratio in uranium element.
In the actual operation process of the reactor, the reactivity of the center of the reactor core is strong, and the heat is higher than that of the peripheral edge area. The enrichment degree of the fuel in the second fuel area 52 is greater than that of the fuel in the first fuel area 11, so that the radial neutron flux distribution of the reactor core can be adjusted, the power distribution in the reactor core is more uniform, and the heat distribution is more uniform.
Referring to fig. 1, according to an optional technical solution of the embodiment of the present application, the heat exchange structures 2 are heat pipes inserted into the core active area 1, the heat pipes are uniformly distributed in the core active area 1, one end of each heat pipe is a cold end, and the other end of each heat pipe is a hot end, so that heat conduction is realized under the action of capillary force.
Referring to fig. 6, in another possible implementation form of the present application, the heat exchange structure 2 is a cooling channel disposed between the core active region 1 and the reflective layer 3, both ends of the cooling channel are communicated with the outside, and through continuously introducing a cooling medium such as helium or liquid alkali metal into the cooling channel, heat is continuously conducted away, and the core temperature is reduced. It should be understood that the cooling channels may be arranged in a plurality of uniform rows within the core.
The embodiment of the application also discloses a spatial nuclear reactor which comprises the core structure in any embodiment, and the core structure is arranged in a pressure vessel of the reactor.
The embodiments of the present application are described in detail above. The principle and the implementation of the present application are explained herein by applying specific examples, and the above description of the embodiments is only used to help understand the technical solutions and the core ideas of the present application. Therefore, the person skilled in the art should, according to the idea of the present application, change or modify the embodiments and applications of the present application based on the scope of protection of the present application. In view of the above, the description should not be taken as limiting the application.

Claims (10)

1. A core structure, comprising:
a core active region in which a first fuel region is arranged;
the heat exchange structure is arranged in the core active area and used for leading out heat;
a reflective layer covering the outside of the core active region;
the first control drum is rotatably arranged in the reflecting layer, a first absorber is arranged on the side surface of the first control drum, and a gap is formed between the first control drum and the core active area; and
the second control drum is rotatably arranged in the reflecting layer, and a second absorber and a second fuel area are arranged on the side surface of the second control drum at intervals;
wherein, be provided with the holding tank on the core active area, the second control drum part imbeds in the holding tank to can rotate relatively the holding tank.
2. The core structure of claim 1 wherein the diameter of the second control drum is greater than the diameter of the first control drum.
3. The core structure as set forth in claim 1, wherein a plurality of the first and second control drums are provided, and the included angles between the adjacent second control drums are the same.
4. The core structure of claim 3 wherein at least one first control drum is disposed between adjacent second control drums;
the first control drums between the adjacent second control drums are uniformly distributed along the circular arcs between the adjacent second control drums.
5. The core structure of any one of claims 1-4 wherein the first and second absorbers are each provided as an arcuate plate-like structure.
6. The core structure of claim 4 wherein the first absorber and the second absorber have a wrap angle of 90 ° -135 °.
7. The core structure of claim 1 wherein the enrichment of the fuel in the second fuel zone is greater than the enrichment of the fuel in the first fuel zone.
8. The core structure of claim 1 wherein the heat exchange structure is a plurality of heat pipes interposed within the core active area.
9. The core structure of claim 1 wherein the heat exchange structure is a cooling channel disposed between the core active region and the reflector layer.
10. A spatial nuclear reactor comprising a core structure as claimed in any one of claims 1 to 9.
CN202210069356.5A 2022-01-21 2022-01-21 Reactor core structure and spatial nuclear reactor Pending CN114628050A (en)

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Application Number Priority Date Filing Date Title
CN202210069356.5A CN114628050A (en) 2022-01-21 2022-01-21 Reactor core structure and spatial nuclear reactor

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Application Number Priority Date Filing Date Title
CN202210069356.5A CN114628050A (en) 2022-01-21 2022-01-21 Reactor core structure and spatial nuclear reactor

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CN114628050A true CN114628050A (en) 2022-06-14

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN117153435A (en) * 2023-09-01 2023-12-01 华能核能技术研究院有限公司 Heat pipe integrated high-temperature reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN117153435A (en) * 2023-09-01 2023-12-01 华能核能技术研究院有限公司 Heat pipe integrated high-temperature reactor
CN117153435B (en) * 2023-09-01 2024-06-04 华能核能技术研究院有限公司 Heat pipe integrated high-temperature reactor

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