CN110931139B - Flow equalization duct assembly for pool nuclear reactor - Google Patents

Flow equalization duct assembly for pool nuclear reactor Download PDF

Info

Publication number
CN110931139B
CN110931139B CN201911249170.2A CN201911249170A CN110931139B CN 110931139 B CN110931139 B CN 110931139B CN 201911249170 A CN201911249170 A CN 201911249170A CN 110931139 B CN110931139 B CN 110931139B
Authority
CN
China
Prior art keywords
reactor
pool
fluid
flow
flow distribution
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
Application number
CN201911249170.2A
Other languages
Chinese (zh)
Other versions
CN110931139A (en
Inventor
周寅鹏
郭志家
衣大勇
彭朝晖
范月容
姚成志
石辰蕾
柯国土
刘兴民
张金山
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN201911249170.2A priority Critical patent/CN110931139B/en
Publication of CN110931139A publication Critical patent/CN110931139A/en
Application granted granted Critical
Publication of CN110931139B publication Critical patent/CN110931139B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/14Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

The invention discloses a flow equipartition pipeline assembly for a pool type nuclear reactor, comprising: an inflow conduit; a flow distribution unit connected to the inflow pipe, the flow distribution unit being provided in a reactor water tank accommodating a reactor body; a plurality of flow distribution pipes connected to the fluid distribution unit, the plurality of flow distribution pipes being arranged to extend in a plurality of directions to guide fluid to a plurality of locations in a circumferential direction within the reactor pool; and the outflow pipeline is used for guiding the fluid after heat exchange with the reactor body out of the reactor water pool.

Description

Flow equalization duct assembly for pool nuclear reactor
Technical Field
The embodiment of the invention relates to the technical field of nuclear engineering, in particular to a flow equipartition pipeline assembly for a pool type nuclear reactor.
Background
Pool type nuclear reactor is an ordinary pressure nuclear reactor of the static pressure of the deep water layer of utilization, and it arranges the reactor body in the reactor water pool, and the fluid in the reactor water pool carries out the heat transfer with the reactor body, and the fluid after the heat transfer is derived to the outer loop system in reactor water pool by outflow conduit to with the heat transfer of reactor body production to a loop system, can guarantee the intrinsic safety of reactor body, simultaneously can effectively utilize the heat.
In the prior art, the fluid generally enters the reactor sump from an inflow conduit mounted to a sidewall of the reactor sump, and the inflow conduit is provided as a single straight conduit. Because the fluid temperature that flows into in the pipeline is less than the fluid temperature in the reactor pond, it is lower to lead to being close to the fluid temperature that flows into pipeline one side in the reactor pond from this, and it is higher to keep away from the fluid temperature that flows into pipeline one side, thereby make and carry out the fluid of heat transfer along not equidirectional and reactor body and have the temperature difference, further lead to the inside temperature distribution of reactor body inhomogeneous, can evenly derive the production certain influence to reactor body heat like this, the while still can influence the working property and the security of reactor body.
Disclosure of Invention
The invention mainly aims to provide a flow equalization pipeline assembly for a pool type nuclear reactor, so as to ensure that the temperature of fluid in a water pool of the reactor is uniformly distributed.
According to one aspect of the present invention, there is provided a flow equalization duct assembly for a pool nuclear reactor, comprising: an inflow conduit; a flow distribution unit connected to the inflow pipe, the flow distribution unit being provided in a reactor water tank accommodating a reactor body; a plurality of flow distribution pipes connected to the fluid distribution unit, the plurality of flow distribution pipes being arranged to extend in a plurality of directions to guide fluid to a plurality of locations in a circumferential direction within the reactor pool; and the outflow pipeline is used for guiding the fluid after heat exchange with the reactor body out of the reactor water pool.
According to some embodiments, the flow distribution unit is disposed at a position near the center of the bottom of the reactor pool, and the plurality of branch pipes form a central symmetrical structure.
According to some embodiments, the plurality of diversion conduits direct fluid to a plurality of locations proximate the reactor basin sidewall.
According to some embodiments, the nozzle of each flow distribution pipe is connected to one or more flow distribution members, which are connected in series.
According to some embodiments, the inflow conduit includes a first portion mounted to a sidewall of the reactor pool and a second portion mounted to a bottom of the reactor pool, and the flow equalization conduit assembly includes a mounting member for mounting the inflow conduit.
According to some embodiments, the flow equalization conduit assembly further comprises a pump configured to drive fluid within the reactor pool into the reactor body from a first inlet located in an upper portion of the reactor body, and the outflow conduit is mounted to a first outlet located in a lower portion of the reactor body.
According to some embodiments, the inflow and outflow pipes of the flow equalization pipe assembly are connected to a loop system outside the reactor pool to form a pipe loop.
According to some embodiments, the side wall of the reactor basin is provided with a second inlet and a second outlet, the inflow conduit being mounted to the second inlet and the outflow conduit being mounted to the second outlet.
In the flow equalization pipeline assembly for the pool-type nuclear reactor according to the embodiment of the invention, the flow distribution unit and the plurality of flow distribution pipelines extending along a plurality of directions are arranged, so that the fluid can be guided to a plurality of positions along the circumferential direction in the reactor water pool, the temperature of the fluid in the reactor water pool is uniformly distributed along the circumferential direction, the temperature of the fluid exchanging heat with the reactor body along different directions tends to be consistent, the heat of the reactor body can be uniformly led out, and the good working performance and safety of the pool-type nuclear reactor can be ensured.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the invention which refers to the accompanying drawings, and may assist in a comprehensive understanding of the invention.
FIG. 1 illustrates an interior elevation view of a pool nuclear reactor in accordance with an exemplary embodiment of the present invention;
FIG. 2 shows a top view of the interior of the pool nuclear reactor of FIG. 1;
FIG. 3 illustrates a schematic diagram of a plurality of split flow conduits of a flow equalization conduit assembly for a pool nuclear reactor in accordance with an exemplary embodiment of the present invention; and
fig. 4 shows a schematic view of the inflow pipe and the flow distribution unit of the flow averaging pipe assembly of fig. 3.
Detailed Description
The technical scheme of the invention is further specifically described by the following embodiments and the accompanying drawings. In the specification, the same or similar reference numerals denote the same or similar components.
In the following detailed description, for purposes of explanation, numerous specific details are set forth in order to provide a thorough understanding of the embodiments of the disclosure. It may be evident, however, that one or more embodiments may be practiced without these specific details. In other instances, well-known structures and devices are shown in schematic form in order to simplify the drawing.
Fig. 1 shows an interior front view of a pool nuclear reactor 200 according to an exemplary embodiment of the present invention, and fig. 2 shows an interior top view of the pool nuclear reactor 200 of fig. 1. As shown in fig. 1 and 2, the pool nuclear reactor 200 includes: a reactor body 7; a reactor pool 6 configured to house a reactor body 7; and a flow equalization conduit assembly 100 for a pool nuclear reactor 200.
The flow equalization conduit assembly 100 includes: an inflow conduit 1; a flow distribution unit 2 connected to the inflow conduit 1, the flow distribution unit 2 being provided in a reactor pool 6 housing a reactor body 7; a plurality of branch pipes 3 connected to the fluid distribution unit 2, the plurality of branch pipes 3 being provided to extend in a plurality of directions to guide the fluid to a plurality of positions in a circumferential direction within the reactor water pool 6; and the outflow pipeline 4 is used for guiding the fluid after heat exchange with the reactor body 7 out of the reactor water pool 6. In the flow equalization pipe assembly 100 for the pool nuclear reactor according to the embodiment of the present invention, by providing the flow distribution unit 2 and the plurality of flow distribution pipes 3 extending in a plurality of directions, the fluid can be guided to a plurality of positions in the reactor pool 6 in the circumferential direction, so that the temperature of the fluid in the reactor pool 6 is uniformly distributed in the circumferential direction, the temperature of the fluid exchanging heat with the reactor body 7 in different directions tends to be uniform, the heat of the reactor body 7 can be uniformly discharged, and the good working performance and safety of the pool nuclear reactor 200 can be ensured.
The reactor body 7 may include components such as a core where chain fission reactions occur and generate a large amount of heat, internals, and control rod drive mechanisms. The reactor sump 6 may be a three-dimensional structure having a cavity including a top, a bottom, and a side wall, and the reactor sump 6 may be, for example, a hollow cylindrical structure. The reactor body 7 may be disposed at the bottom of the reactor sump 6 through a bearing member 73. The reactor body 7 may be located below the level H of the fluid in the reactor sump 6. The fluid may comprise a substance capable of flowing for heat exchange, for example, the fluid may comprise water.
Referring to fig. 1, a first inlet 71 is provided at an upper portion of a reactor body 7 for fluid inflow; the lower part of the reactor body 7 is provided with a first outlet 72, and the outflow pipe 4 is mounted to the first outlet 72. The fluid in the reactor water tank 6 enters the reactor body 7 through the first inlet 71, absorbs heat generated from the core, and flows out through the first outlet 72 to remove the heat, thereby performing heat exchange with the reactor body 7. The side wall of the reactor sump 6 is provided with a second inlet 61 and a second outlet 62, the inflow pipe 1 being mounted to the second inlet 61, and the outflow pipe 4 being mounted to the second outlet 62. The second inlet 61 and the second outlet 62 may be disposed on the same side wall of the reactor sump 6, or may be disposed on different side walls of the reactor sump 6, for example, two adjacent side walls or two opposite side walls of the reactor sump 6. In the embodiment of the present invention, the second inlet 61 has a height higher than that of the second outlet 62. Of course, in other embodiments, the height of the second inlet 61 may be equal to or lower than the height of the second outlet 62. The inflow pipe 1 may be fixed to the second inlet 61 by means of, for example, welding, bonding, or providing a fastener, etc., to ensure smooth inflow of the fluid into the reactor sump 6. Similarly, the outlet pipe 4 may be fixed to the second outlet 62 to ensure smooth flow of the fluid out of the reactor sump 6.
Referring to fig. 2, the flow distribution unit 2 may be disposed near the center of the bottom of the reactor sump 6, and the plurality of branch pipes 3 may form a central symmetrical structure. In one embodiment, the plurality of branch pipes 3 may extend from the bottom of the reactor sump 6 near the center in different directions, the included angle between adjacent branch pipes 3 is the same, and the extension length of each branch pipe 3 is the same. For example, the number of the branch pipes 3 may be six, and the branch pipes 3 form an included angle of 60 ° between each other. The plurality of branch pipes 3 may guide the fluid to a plurality of positions on the same circumference centering on the center of the bottom of the reactor pool 6. Through setting up a plurality of reposition of redundant personnel pipelines 3 into central symmetry structure, can guarantee that the resistance that each reposition of redundant personnel pipeline 3 receives of fluid flow is the exact same to make along a plurality of positions entering reactor water tank 6's fluid flow unanimous, the fluid in the reactor water tank 6 is more even along the temperature distribution of circumference from this.
In one embodiment, a plurality of shunt tubes 3 may direct fluid to a plurality of locations near the side walls of the reactor sump 6, i.e. the extension of the shunt tubes 3 is approximately the distance from the bottom centre to the side walls of the reactor sump 6. In the case of a cylindrical reactor basin 6, the extension of the shunt tubes 3 is approximately the radius of the bottom surface of the reactor basin 6. In other embodiments, other choices for the extension length of the shunt tubes 3 are possible.
Fig. 3 shows a schematic view of a plurality of diversion conduits 3 of a flow equalization conduit assembly 100 for a pool nuclear reactor according to an exemplary embodiment of the present invention. As shown in fig. 3, one or more flow dividing members 31 may be connected to the nozzle of each flow dividing pipe 3, and a plurality of flow dividing members 31 may be connected in sequence. The flow dividing pipe 3 and the flow dividing member 31, and the plurality of flow dividing members 31 may be connected together by welding. By providing the flow dividing member 31, on the one hand, the inflow speed of the fluid can be increased, and on the other hand, the number of inflow positions of the fluid can be increased, so that the plurality of inflow positions are arranged more densely in the circumferential direction, and the uniformity of the temperature distribution of the fluid is further improved. The flow splitting component 31 may comprise a tee having one inlet and two outlets for changing the direction of fluid flow. For the case of providing a plurality of tee fittings, two outlets of one tee fitting may be connected to another tee fitting, respectively, thereby expanding the orifice of the branch pipe 3 into a plurality of orifices. In some embodiments, the number, specifications and arrangement of the diversion members 31 connected to each diversion pipe 3 are consistent with each other, so as to ensure that the resistance of the fluid flowing through each diversion pipe 3 and each diversion member 31 is completely the same, so that the flow rate of the fluid flowing out from each pipe orifice is consistent, and the fluid can uniformly enter the reactor pool 6 along the circumferential direction.
Fig. 4 shows a schematic view of the inflow pipe 1 and the flow distribution unit 2 of the flow averaging pipe assembly 100 of fig. 3, and referring to fig. 3 and 4, the flow distribution unit 2 may be a symmetrical structure having a circular cross-section, for example, may be cylindrical, spherical, or conical, etc. The side wall of the flow distribution unit 2 may be uniformly provided with a plurality of branch pipes 3 along the circumferential direction, and each branch pipe 3 may be welded to the flow distribution unit 2. In one embodiment, a plurality of connection pipes may be uniformly arranged along the circumferential direction on the side wall of the flow distribution unit 2, and the branch pipes 3 may be connected to the connection pipes, respectively. The flow distribution unit 2 and the plurality of connection pipes, and the plurality of connection pipes and the plurality of branch pipes 3 may be connected together by welding. The inflow pipe 1 may be connected to the top of the flow distribution unit 2, and the inflow pipe 1 may be welded with the flow distribution unit 2.
Referring to fig. 1 and 4, the inflow pipe 1 may include a first portion 11 mounted to a sidewall of the reactor sump 6 and a second portion 12 mounted to a bottom of the reactor sump 6, and the flow equalization pipe assembly 100 may include a mounting part 5 for mounting the inflow pipe 1. The first portion 11 may be parallel to the side wall of the reactor sump 6, the second portion 12 may be parallel to the bottom of the reactor sump 6, and the first portion 11 and the second portion 12 are perpendicular to each other. In other embodiments, the inlet conduit 1 may comprise only the second portion 12 parallel to the bottom of the reactor sump 6, in which case the second inlet 61 is provided near the bottom on the side wall of the reactor sump 6, and the inlet conduit 1 need not extend on the side wall of the reactor sump 6.
The mounting member 5 may support and secure the first portion 11 to the side wall of the reactor sump 6 and the second portion 12 to the bottom of the reactor sump 6. The number of the mounting parts 5 may be plural and arranged at intervals. By providing a plurality of mounting members 5, the inlet conduit 1 can be secured to the reactor sump 6, ensuring a smooth flow of fluid in the inlet conduit 1. Similarly, the outlet pipe 4 may be supported and fixed to a sidewall of the reactor sump 6 by the mounting member 5 to ensure smooth flow of the fluid in the outlet pipe 4.
The flow equalization conduit assembly 100 may further include a pump configured to drive fluid within the reactor pool 6 into the reactor body 7 from a first inlet 71 located at an upper portion of the reactor body 7, and the outflow conduit 4 is mounted to a first outlet 72 located at a lower portion of the reactor body 7. According to the arrow of fig. 1, the plurality of diversion pipes 3 guide the fluid to the bottom of the reactor water pool 6, the fluid is accumulated from the bottom, under the driving action of the pump, the fluid in the reactor water pool 6 can enter the first inlet 71 of the reactor body 7 from different directions, and after heat exchange, the fluid enters the outflow pipe 4 from the first outlet 72 and flows out of the reactor water pool 6 through the outflow pipe 4. The reactor body 7 may be located near the center of the bottom of the reactor pool 6. Because the fluid temperature in the reactor pool 6 is evenly distributed along the circumference, and the reactor body 7 is arranged near the bottom center of the reactor pool 6, the fluid temperature entering the first inlet 71 from different directions is consistent, so that the temperature distribution in the reactor body 7 is even, and even heat exchange can be realized.
In an embodiment of the present invention, the inflow conduit 1 and the outflow conduit 4 of the flow equalization conduit assembly 100 may be connected to a loop system outside the reactor pool 6, forming a conduit loop. The fluid with the increased temperature in the outflow pipeline 4 can exchange heat with the two loops in the primary loop to reduce the temperature to the initial temperature, and the fluid with the initial temperature further enters the reactor pool 6 from the inflow pipeline 1, so that the fluid is recycled, and meanwhile, the heat is transferred to other systems through the primary loop system for further heat supply and other purposes.
The process of uniformly introducing the fluid in the reactor water tank 6 into the reactor body 7 and performing uniform heat exchange by using the flow equalizing pipe assembly 100 of the present invention will be briefly described.
Feeding a fluid having an initial temperature into an inflow pipe 1, the fluid flowing along the inflow pipe 1 to a flow distribution unit 2; the fluid is distributed to the plurality of branch pipes 3 and flows in the plurality of branch pipes 3 simultaneously to reach a plurality of positions at the bottom of the reactor pool 6 along the circumferential direction; under the driving action of the pump, the fluid moves upwards from multiple directions to the first inlet 71 of the reactor body 7 and enters the reactor body 7 from the first inlet 71 for uniform heat exchange; the fluid after heat exchange flows out of the first outlet 72 of the reactor body 7, enters the outflow pipe 4, and flows out of the reactor water pool 6 through the outflow pipe 4, so that heat is transferred out of the reactor water pool 6.
Although the present invention has been described in connection with the accompanying drawings, the embodiments disclosed in the drawings are intended to be illustrative of embodiments of the invention and should not be construed as limiting the invention. The various components in the drawings are not to scale in order to clearly illustrate the details of the various components, and so the proportions of the various components in the drawings should not be taken as limiting.
Although a few embodiments of the present general inventive concept have been shown and described, it would be appreciated by those skilled in the art that changes may be made in these embodiments without departing from the principles and spirit of the general inventive concept, the scope of which is defined in the claims and their equivalents.

Claims (6)

1. A flow equalization conduit assembly for a pool nuclear reactor, comprising:
an inflow conduit;
a flow distribution unit connected to the inflow pipe, the flow distribution unit being provided in a reactor water tank accommodating a reactor body;
a plurality of flow distribution pipes connected to the flow distribution unit, the plurality of flow distribution pipes being arranged to extend in a plurality of directions to guide a fluid to a plurality of positions in a circumferential direction within the reactor pool; and
the outflow pipeline is used for guiding the fluid after heat exchange with the reactor body out of the reactor water pool;
the plurality of diversion conduits directing fluid to a plurality of locations proximate a sidewall of the reactor basin;
the pipe orifice of each shunting pipeline is connected with one or more shunting components, and the shunting components are connected in sequence.
2. The flow equalization duct assembly of claim 1, wherein said flow distribution unit is located near the center of the bottom of said reactor pool, and said plurality of flow distribution ducts form a centrally symmetric structure.
3. The flow equalization duct assembly of claim 1, wherein said inlet duct includes a first portion mounted to a sidewall of said reactor pool and a second portion mounted to a bottom of said reactor pool, said flow equalization duct assembly further including a mounting member for mounting said inlet duct.
4. The flow equalization duct assembly of claim 1, further comprising a pump configured to drive fluid within a reactor sump into the reactor body from a first inlet located in an upper portion of the reactor body, and wherein the outflow duct is mounted to a first outlet located in a lower portion of the reactor body.
5. The flow equalization duct assembly of claim 1, wherein said flow equalization duct assembly inlet and outlet ducts are connected to a loop system external to said reactor pool to form a duct loop.
6. The flow equalization duct assembly of claim 1, wherein a sidewall of said reactor basin defines a second inlet and a second outlet, said inlet duct being mounted to said second inlet and said outlet duct being mounted to said second outlet.
CN201911249170.2A 2019-12-06 2019-12-06 Flow equalization duct assembly for pool nuclear reactor Active CN110931139B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201911249170.2A CN110931139B (en) 2019-12-06 2019-12-06 Flow equalization duct assembly for pool nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201911249170.2A CN110931139B (en) 2019-12-06 2019-12-06 Flow equalization duct assembly for pool nuclear reactor

Publications (2)

Publication Number Publication Date
CN110931139A CN110931139A (en) 2020-03-27
CN110931139B true CN110931139B (en) 2022-04-08

Family

ID=69857582

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201911249170.2A Active CN110931139B (en) 2019-12-06 2019-12-06 Flow equalization duct assembly for pool nuclear reactor

Country Status (1)

Country Link
CN (1) CN110931139B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113990533B (en) * 2021-10-22 2024-05-10 中国原子能科学研究院 Reactor and coolant conveying structure thereof

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4708852A (en) * 1985-04-08 1987-11-24 Texaco Inc. Uniform flow distributing means for a trickle bed flow reactor
CN103377735A (en) * 2012-04-27 2013-10-30 上海核工程研究设计院 Reactor internal on lower part of reactor
CN104409114A (en) * 2014-12-12 2015-03-11 中国科学院合肥物质科学研究院 Flow distribution device used for tank-type forced circulation reactor
CN109461506A (en) * 2018-11-12 2019-03-12 中国原子能科学研究院 A kind of swimming pool formula region low temperature heating reactor

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2971460B1 (en) * 1998-10-15 1999-11-08 三菱重工業株式会社 Structure to promote mixing of fluid to be heated in reactor vessel
ES2243146B1 (en) * 2005-06-24 2006-12-01 Univ Pais Vasco PROCEDURE FOR OBTAINING HYDROGEN FROM NATURAL GAS

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4708852A (en) * 1985-04-08 1987-11-24 Texaco Inc. Uniform flow distributing means for a trickle bed flow reactor
CN103377735A (en) * 2012-04-27 2013-10-30 上海核工程研究设计院 Reactor internal on lower part of reactor
CN104409114A (en) * 2014-12-12 2015-03-11 中国科学院合肥物质科学研究院 Flow distribution device used for tank-type forced circulation reactor
CN109461506A (en) * 2018-11-12 2019-03-12 中国原子能科学研究院 A kind of swimming pool formula region low temperature heating reactor

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
Swimming pool-type low-temperature heating reactor:recent progress in research and application;zhang yi-xuan,cheng hui-ping,liu xing-min;《Energy procedia》;20171231;3.recent progress in SPLTHR,FIG.1 *
中国先进研究堆停堆冷却措施及其主要特点;庄毅,柯国土,刘天才等;《原子能科学技术》;20091231;2.CARR停堆冷却措施,图1 *
池式研究堆回路系统总体配置分析;黄兴蓉,庄毅,张金山等;《原子能科学技术》;20091231;全文 *

Also Published As

Publication number Publication date
CN110931139A (en) 2020-03-27

Similar Documents

Publication Publication Date Title
CN110931139B (en) Flow equalization duct assembly for pool nuclear reactor
CN104409114A (en) Flow distribution device used for tank-type forced circulation reactor
CN105909566B (en) A kind of pumping plant water inlet flow field combined type control whirlpool facility
CN104797344A (en) Nozzle for distribution of a fluid
JP2021177093A (en) Flow straightening device used in pipeline
CN106643227B (en) A kind of mixing deflector type reboiler
CN101837268B (en) Gas circulation distributor
CN110940209B (en) Large-scale three-dimensional heat exchange plate type heat exchanger
CN202532953U (en) Jet flow pipe and jet flow heat exchanger with same
CN104039066A (en) Wrapping-wire type windowed target system
CN102794152B (en) Loop reactor
CN102735093A (en) Shell-and-tube heat exchanger
CN101922874A (en) Combined-type heat exchanger and fluidized bed reactor
CN205403572U (en) Heat exchanger import guide plate type distributor
CN203053274U (en) Wastewater waste-heat recovering device and bathing system using same
JP6757002B2 (en) Heat exchanger
CN214470291U (en) Spiral-flow type water distribution device and energy storage system
CN204854414U (en) Shell type heat exchanger
CN216499266U (en) Series-type microreactor
CN201930592U (en) Water distribution device of drifting sand filter
CN101603784B (en) Titanium tube heat exchanger
CN202803233U (en) Ring pipe reactor
CN106629996B (en) A kind of microbubble circulation reaction system
CN204084708U (en) Accumulation of energy pond H type pipe laying structure
CN109473194B (en) Attenuation tube for deep water tank type low-temperature heat supply stack

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