CN114999682B - Passive residual heat hydraulic test device and method for polar environment nuclear power device - Google Patents

Passive residual heat hydraulic test device and method for polar environment nuclear power device Download PDF

Info

Publication number
CN114999682B
CN114999682B CN202210663304.0A CN202210663304A CN114999682B CN 114999682 B CN114999682 B CN 114999682B CN 202210663304 A CN202210663304 A CN 202210663304A CN 114999682 B CN114999682 B CN 114999682B
Authority
CN
China
Prior art keywords
ice
test
heat exchange
tube
temperature
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.)
Expired - Fee Related
Application number
CN202210663304.0A
Other languages
Chinese (zh)
Other versions
CN114999682A (en
Inventor
王明军
张洪铭
赖志贤
章静
秋穗正
苏光辉
田文喜
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.)
Xian Jiaotong University
Original Assignee
Xian Jiaotong University
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 Xian Jiaotong University filed Critical Xian Jiaotong University
Priority to CN202210663304.0A priority Critical patent/CN114999682B/en
Publication of CN114999682A publication Critical patent/CN114999682A/en
Application granted granted Critical
Publication of CN114999682B publication Critical patent/CN114999682B/en
Expired - Fee Related 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
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • 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)
  • Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)

Abstract

The test device comprises an ice making circulation loop and a pool type passive waste heat discharging system test loop, wherein the ice making loop in the ice making circulation loop is connected with a centrifugal pump through a check valve to form a test heat exchange water pool inlet, and an outlet pipeline of the heat exchange water pool is connected with the centrifugal pump and then enters the ice making loop inlet to form a circulation loop. The outlet pipeline of the electric heating evaporator in the test loop of the pool type passive waste heat discharging system is connected with the upper inlet of the tube bundle type heater, the outlet pipeline of the tube bundle type heat exchanger is connected with the shell side inlet of the shell type cooling system, and the shell side outlet pipeline of the shell type cooling system is connected with the inlet of the electric heating evaporation system to form a loop. The invention can simulate the thermal hydraulic characteristics of the passive waste heat discharging system of the nuclear power plant under the environment of motion and extreme low temperature superposition, and provides an effective test device for the related research of the thermal hydraulic characteristics of the passive waste heat discharging system in the environment of extreme low temperature.

Description

极地环境核动力装置非能动余排热工水力试验装置与方法Thermal-hydraulic test device and method for passive residual exhaust of nuclear power plant in polar environment

技术领域technical field

本发明属于极地环境核动力装置非能动余热排出系统热工水力特性试验领域,具体涉及一种极地环境核动力装置非能动余排热工水力试验装置与方法。The invention belongs to the thermal-hydraulic characteristic test field of a passive waste heat discharge system of a nuclear power plant in a polar environment, and specifically relates to a thermal-hydraulic test device and a method for a passive waste heat discharge thermal-hydraulic test device and method of a nuclear power plant in a polar environment.

背景技术Background technique

随着全球气候变化,北极地区海域出现了较长的夏季无冰期,相较常规动力船只,核动力装置具有续航能力强、能量密度高、燃料体积小等优点,能够在极地的苛刻环境下执行各类航行任务。当前我国的极地核动力装置起步较晚,且大多基于能动的安全系统,在发生安全事故时,必须依靠外部的电力输入来驱动泵等机械装置为反应堆提供足够的冷却水,防止堆芯温度过高发生融毁事故。历史上的三次重大核事故都体现了能动安全装置具有很大的局限性。非能动的安全设计目的在于不依靠外部能源输入即可在一段时间内仅依靠重力、冷却剂自然循环、压缩空气膨胀做功等自然力作用使冷却剂注入堆芯中冷却,再将冷却剂的热量导出,保证堆芯得到充分而持续的冷却。非能动余热排出系统在正常余热排出系统失效后开始投入运行,利用冷却剂蒸发、冷凝的过程实现系统回路内的自然循环导出堆芯衰变余热。低温环境由于海水中混有固体冰晶,在换热性能不佳的情况下容易堵塞船只海水系统,造成冷却水无法流入,换热器无法有效冷却的影响。With global climate change, there is a longer summer ice-free period in the seas of the Arctic region. Compared with conventional powered ships, nuclear power devices have the advantages of strong endurance, high energy density, and small fuel volume, and can operate in the harsh environment of the polar regions. Various navigation missions. At present, my country's polar nuclear power plants started relatively late, and most of them are based on active safety systems. In the event of a safety accident, they must rely on external power input to drive pumps and other mechanical devices to provide sufficient cooling water for the reactor to prevent the core temperature from being too high. High occurrence of meltdown accidents. The three major nuclear accidents in history all reflect the great limitations of active safety devices. The purpose of the passive safety design is to inject the coolant into the core for cooling for a period of time by relying only on gravity, natural circulation of the coolant, expansion of compressed air and other natural forces without relying on external energy input, and then export the heat of the coolant , to ensure sufficient and continuous cooling of the core. The passive waste heat removal system is put into operation after the failure of the normal waste heat removal system, and uses the process of coolant evaporation and condensation to realize the natural circulation in the system loop to export the core decay waste heat. In the low-temperature environment, due to the solid ice crystals mixed in the seawater, it is easy to block the seawater system of the ship under the condition of poor heat transfer performance, resulting in the inability of cooling water to flow in and the effect that the heat exchanger cannot be effectively cooled.

中国专利申请公开号CN106653109A公开了一种二次侧非能动余热排出系统的试验研究装置,包括三个水箱模拟体,蒸发器模拟体等装置,用于模拟三代反应堆技术中二次侧非能动余热排出系统设计的可靠性。该发明的模拟对象为陆上静止的反应堆非能动安全系统,无法模拟海洋运动环境对非能动余热排出系统的影响,同时该发明采用液态水进行冷却,不适用于模拟低温条件下余热排出换热器冰水混合物的传热流动试验。Chinese Patent Application Publication No. CN106653109A discloses a test and research device for secondary side passive waste heat removal system, including three water tank simulation bodies, evaporator simulation body and other devices, which are used to simulate secondary side passive waste heat in third-generation reactor technology Reliability of discharge system design. The simulation object of this invention is the static reactor passive safety system on land, and it is impossible to simulate the influence of the ocean movement environment on the passive waste heat removal system. At the same time, the invention uses liquid water for cooling, which is not suitable for simulating waste heat removal and heat transfer under low temperature conditions. Heat transfer flow test of ice-water mixture.

中国专利申请公开号CN209149828U公开了一种多回路耦合的非能动余热排出系统试验装置。非能动余热排出系统入口冷凝管与蒸汽发生器二次侧蒸汽出口连接,可对三个回路的自然循环工况进行模拟试验。该装置同样使用水箱中的液态水对余热排出换热器进行换热试验,没有制冰回路无法进行低温条件下的换热模拟试验。Chinese patent application publication number CN209149828U discloses a multi-loop coupled passive waste heat removal system test device. The condensing pipe at the inlet of the passive waste heat removal system is connected to the steam outlet on the secondary side of the steam generator, which can simulate the natural circulation conditions of the three circuits. This device also uses the liquid water in the water tank to conduct heat exchange tests on the waste heat discharge heat exchanger. Without an ice making circuit, it is impossible to conduct heat exchange simulation tests under low temperature conditions.

中国专利申请公开号CN201589481U公开了一种利用海水制取流化冰的系统,该装置主要由冷却压缩机、冷凝器、制冰换热器、干燥过滤器等设备组成,可利用海水的结晶技术原理可连续制成海水与冰晶的混合物,但该系统回路无法对海水中冰晶的比例进行调控,不适用于需要精确控制冰晶比例以进行低温环境换热试验的研究。Chinese Patent Application Publication No. CN201589481U discloses a system for producing fluidized ice using seawater. The device is mainly composed of cooling compressors, condensers, ice-making heat exchangers, drying filters and other equipment, and can use seawater crystallization technology. The principle can continuously make a mixture of seawater and ice crystals, but the system loop cannot regulate the proportion of ice crystals in seawater, so it is not suitable for research that requires precise control of the proportion of ice crystals for heat transfer experiments in low-temperature environments.

发明内容Contents of the invention

对于上述发明装置中不适用于核动力设备在海洋运动条件与低温条件叠加状态下热工水力特性试验的需求,提出了一种极地环境核动力装置非能动余排热工水力试验装置与方法,本发明可通过对应的运动平台设备模拟船只在海洋上遭遇的运动工况,研究倾斜摇摆运动对系统流动换热特性的影响。通过制冰回路与非能动余热排出系统回路耦合实现低温换热条件的模拟。其中制冰回路能够对制取的冰水混合物中冰晶比例进行调节,满足试验不同冰晶浓度对换热特性影响的需求。In view of the requirement that the above-mentioned inventive device is not applicable to the thermal-hydraulic characteristic test of nuclear power equipment under the superimposed state of ocean motion and low temperature conditions, a thermal-hydraulic test device and method for passive residual exhaust of nuclear power plant in polar environment are proposed. The present invention can simulate the motion working condition encountered by the ship on the ocean through the corresponding motion platform equipment, and study the influence of the tilting and rocking motion on the flow and heat transfer characteristics of the system. The simulation of low temperature heat transfer conditions is realized by coupling the ice making loop with the passive waste heat removal system loop. Among them, the ice-making circuit can adjust the proportion of ice crystals in the prepared ice-water mixture to meet the needs of testing the influence of different ice crystal concentrations on heat transfer characteristics.

为了满足上述试验目的,本发明采用如下的技术方案:In order to meet the above test purpose, the present invention adopts the following technical solutions:

一种极地环境核动力装置非能动余排热工水力试验装置,包括制冰循环回路与池式非能动余热排出系统试验回路,其中制冰循环回路包括制冰回路11和六自由度运动换热水池12,制冰回路11主要包含制冰机1,连接制冰机的储冰保温容器2和低温水箱301。低温水箱301的主要作用是调配海水为制冰机提供充足的水源,同时也能将低温海水注入到储冰保温容器2中调配试验所需冰晶比例的冰水混合物。A thermal-hydraulic test device for passive residual heat removal of a nuclear power plant in a polar environment, including an ice-making circulation loop and a pool-type passive waste heat removal system test loop, wherein the ice-making circulation loop includes an ice-making loop 11 and a six-degree-of-freedom motion heat exchange The pool 12 and the ice making circuit 11 mainly include an ice maker 1 , an ice storage and heat preservation container 2 connected to the ice maker and a low-temperature water tank 301 . The main function of the low-temperature water tank 301 is to deploy seawater to provide sufficient water source for the ice machine, and at the same time, it can also inject low-temperature seawater into the ice storage and heat preservation container 2 to prepare the ice-water mixture with the proportion of ice crystals required for the test.

制冰回路11位于冰水混合物循环回路上游,其输出管道经过第二止回阀802连接第一离心泵401,将制取的固定比例混合物注入循环回路管道中,第一离心泵401下游出口管道连接第三控制阀门703和第一流量监测仪器901,用于控制试验换热水池入口管道流量输入以及检测试验循环回路上游流量。试验换热水池5入口设置第一温度监测仪器1001,监测入口流体的温度参数。试验换热水池5底部连接六自由度运动台架的上支撑面,采用螺栓固定,六自由度运动台架下支撑面同样使用螺栓固定在地面上,上下支撑面间通过六根活塞液压杆连接。位于试验换热水池底部的出口的第二温度监测仪器1002,监测试验换热水池出口流体的温度参数,试验换热水池出口管道连接第二流量监测仪器902和第四控制阀门704,用于监测试验换热水池下游流量,以及调节试验换热水池的输出流量,试验换热水池进出口管道之间由连接差压传感器18,作用为测量流体经过试验换热水池的压差变化。第四控制阀门704下游出口管道连接第二离心泵402,提供足够的驱动力实现冰水混合物流体的流动循环,第二离心泵402下游连接储冰保温容器入口管道最终构成循环回路。The ice-making circuit 11 is located upstream of the ice-water mixture circulation circuit, and its output pipeline is connected to the first centrifugal pump 401 through the second check valve 802, and the prepared fixed ratio mixture is injected into the circulation circuit pipeline, and the downstream outlet pipeline of the first centrifugal pump 401 The third control valve 703 is connected with the first flow monitoring instrument 901 for controlling the flow input of the inlet pipe of the test heat exchange pool and detecting the flow upstream of the test circulation loop. A first temperature monitoring instrument 1001 is installed at the inlet of the test heat exchange pool 5 to monitor the temperature parameters of the inlet fluid. The bottom of the test heat exchange pool 5 is connected to the upper support surface of the six-degree-of-freedom motion platform, which is fixed with bolts. The lower support surface of the six-degree-of-freedom movement platform is also fixed on the ground with bolts, and the upper and lower support surfaces are connected by six piston hydraulic rods. The second temperature monitoring instrument 1002 located at the outlet of the test heat exchange pool bottom monitors the temperature parameters of the outlet fluid of the test heat exchange pool, and the outlet pipe of the test heat exchange pool is connected with the second flow monitoring instrument 902 and the fourth control valve 704 for monitoring The downstream flow of the test heat exchange pool and the adjustment of the output flow of the test heat exchange pool are connected with a differential pressure sensor 18 between the inlet and outlet pipes of the test heat exchange pool to measure the pressure difference change of the fluid passing through the test heat exchange pool. The downstream outlet pipeline of the fourth control valve 704 is connected to the second centrifugal pump 402 to provide sufficient driving force to realize the flow circulation of the ice-water mixture fluid. The downstream of the second centrifugal pump 402 is connected to the inlet pipeline of the ice storage and heat preservation container to form a circulation loop.

池式非能动余热排出系统试验回路包括电加热蒸发系统13、管束式换热器14、管壳式换热系统17和供水箱303。电加热蒸发系统13主要作用为将供水箱303中的液态水加热为试验所需的蒸汽,并根据试验需求控制对应的蒸汽参数,电加热蒸发系统13下游管道连接第五控制阀门705和第三流量计903,用于监测和控制蒸汽流量。第三流量计903下游管道连接管束式换热器14上端管侧入口,同时管侧入口管道设置第三温度传感器1003,监测进入管束式换热器管侧入口的蒸汽温度参数。管束式换热器14浸没在试验换热水池5中的冰水混合物流体中进行换热,并研究与低温流体的换热特性,管束式换热器出口管道位于管束式换热器14下端,与入口有一定的高度差便于形成自然循环。管束式换热器14下端出口管道连接第四流量计904和第六控制阀门706,控制和监测余热排出换热器出口流体流量,同时下端出口管道设置第四温度传感器1004,监测管束出口流体温度参数。第六控制阀门706下游连接管壳式换热系统17壳侧入口,管壳式换热系统17用于将管道中未完全冷凝的蒸汽冷凝为液态水便于重新加热为蒸汽,同时当试验回路中流体温度过高时进行冷却,防止事故的发生。管壳式换热系统17中电加热蒸发器15壳侧下游连接电加热蒸发系统13入口,将冷凝后的流体重新导入电加热蒸发器中加热构成循环回路。管壳式换热系统17中电加热蒸发器15管侧依次通过第七控制阀门707、水泵16和冷却水箱302构成闭合回路,使壳侧流体循环流动将管侧流体的热量导出。The test circuit of the pool-type passive waste heat removal system includes an electric heating evaporation system 13 , a tube-bundle heat exchanger 14 , a shell-and-tube heat exchange system 17 and a water supply tank 303 . The main function of the electric heating evaporation system 13 is to heat the liquid water in the water supply tank 303 into the steam required for the test, and control the corresponding steam parameters according to the test requirements. The downstream pipeline of the electric heating evaporation system 13 is connected to the fifth control valve 705 and the third control valve 705. The flow meter 903 is used to monitor and control the steam flow. The downstream pipeline of the third flowmeter 903 is connected to the upper tube side inlet of the tube bundle heat exchanger 14, and the tube side inlet pipeline is provided with a third temperature sensor 1003 to monitor the temperature parameters of the steam entering the tube side inlet of the tube bundle heat exchanger. The tube-bundle heat exchanger 14 is immersed in the ice-water mixture fluid in the test heat exchange pool 5 for heat exchange, and the heat exchange characteristics with the low-temperature fluid are studied. The outlet pipe of the tube-bundle heat exchanger is located at the lower end of the tube-bundle heat exchanger 14. There is a certain height difference from the entrance to facilitate the formation of natural circulation. The outlet pipe at the lower end of the tube bundle heat exchanger 14 is connected to the fourth flowmeter 904 and the sixth control valve 706 to control and monitor the fluid flow rate at the outlet of the heat exchanger for waste heat discharge, and at the same time, the outlet pipe at the lower end is provided with a fourth temperature sensor 1004 to monitor the fluid temperature at the outlet of the tube bundle parameter. The downstream of the sixth control valve 706 is connected to the shell-side inlet of the shell-and-tube heat exchange system 17. The shell-and-tube heat exchange system 17 is used to condense the incompletely condensed steam in the pipeline into liquid water for reheating into steam. When the fluid temperature is too high, it is cooled to prevent accidents. In the shell-and-tube heat exchange system 17, the shell side downstream of the electric heating evaporator 15 is connected to the inlet of the electric heating evaporation system 13, and the condensed fluid is reintroduced into the electric heating evaporator for heating to form a circulation loop. In the shell-and-tube heat exchange system 17, the tube side of the electrically heated evaporator 15 passes through the seventh control valve 707, the water pump 16, and the cooling water tank 302 to form a closed loop in sequence, so that the shell-side fluid circulates and the heat of the tube-side fluid is exported.

所述制冰回路11能够控制冰水混合物中冰晶含量。The ice-making circuit 11 can control the content of ice crystals in the ice-water mixture.

所述试验换热水池5中使用一个挡板将流动空间分为两部分,出口位于试验换热水池5底部。A baffle plate is used in the test heat exchange pool 5 to divide the flow space into two parts, and the outlet is located at the bottom of the test heat exchange pool 5 .

所述制冰循环回路中连接管道表面均覆盖有保温材料,能够使回路运行温度维持在-5℃—0℃范围内。The surfaces of the connecting pipes in the ice-making circulation loop are all covered with thermal insulation materials, which can maintain the operating temperature of the loop within the range of -5°C to 0°C.

管束式换热器14管外与-5℃-0℃的冰水混合物直接接触,管内流动320℃-350℃的蒸汽。The outside of the tube bundle heat exchanger 14 is in direct contact with the ice-water mixture at -5°C-0°C, and the steam at 320°C-350°C flows inside the tube.

六自由度运动换热水池中试验换热水池5具有透明观测窗口用于观察冰水混合物流型变化。The test heat exchange pool 5 in the six-degree-of-freedom motion heat exchange pool has a transparent observation window for observing the flow pattern change of the ice-water mixture.

六自由度运动台架6有多根活塞支撑杆连接上支撑面和下支撑面,试验换热水池5与上支撑面之间采用螺栓固定。The six-degree-of-freedom motion bench 6 has multiple piston support rods connecting the upper support surface and the lower support surface, and the test heat exchange pool 5 and the upper support surface are fixed by bolts.

所述的一种极地环境核动力装置非能动余排热工水力试验装置的试验方法,进行极地低温环境模拟试验时开启制冰循环回路,同时开启电加热蒸发器15生成320℃-350℃的蒸汽,使管束式换热器管14内通过高温蒸汽,管外接触-5℃-0℃的冰水混合物,通过调节六自由度运动台架6上支撑面的水平角度模拟非能动余热排出系统在极地低温环境叠加海洋倾斜工况下的热工水力特性过程,该过程中各循环回路的流量、温度、压力参数通过第一至第四流量监测仪器、第一至第四温度监测仪器、差压传感器18测量;通过试验过程中从储冰保温容器2提取冰水混合物进行检测确定冰晶颗粒含量,透过试验换热水池5的观测窗观察测量冰水混合物流型变化,在试验换热水池5出入口分别采样,检测换热过程前后冰晶颗粒的含量变化,以研究冰晶颗粒在换热过程中的动力学特征。According to the test method of the thermal-hydraulic test device for the passive residual discharge of the nuclear power plant in the polar environment, the ice-making circulation loop is turned on when the polar low-temperature environment simulation test is carried out, and the electric heating evaporator 15 is turned on at the same time to generate 320°C-350°C Steam, so that high-temperature steam passes through the tube bundle heat exchanger tube 14, and the outside of the tube contacts the ice-water mixture at -5°C-0°C, and the passive waste heat removal system is simulated by adjusting the horizontal angle of the support surface on the six-degree-of-freedom motion platform 6 The thermal-hydraulic characteristic process under the polar low temperature environment superimposed ocean tilting conditions, the flow, temperature and pressure parameters of each circulation loop in the process are measured by the first to fourth flow monitoring instruments, the first to fourth temperature monitoring instruments, differential The pressure sensor 18 measures; during the test process, the ice-water mixture is extracted from the ice storage and heat preservation container 2 to detect and determine the content of ice crystal particles, and the flow pattern change of the ice-water mixture is observed and measured through the observation window of the test heat exchange pool 5. In the test heat exchange pool 5 Sampling at the inlet and outlet respectively to detect the content change of ice crystal particles before and after the heat exchange process, so as to study the dynamic characteristics of ice crystal particles during the heat exchange process.

和现有技术相比较,本发明具有如下优点:Compared with the prior art, the present invention has the following advantages:

1、本发明的试验系统与方法可模拟海洋运动环境与低温环境叠加状态下核动力装置非能动余热排出系统的热工水力特性,对非能动余热排出系统在特殊环境下的性能与可靠性进行充分的试验研究;1. The test system and method of the present invention can simulate the thermal-hydraulic characteristics of the passive waste heat removal system of the nuclear power plant under the superimposed state of the ocean motion environment and the low temperature environment, and conduct an investigation on the performance and reliability of the passive waste heat removal system in a special environment. Sufficient experimental research;

2、本发明的制冰循环回路可通过试验换热水池的透明观测窗口与储冰保温容器中的采样数据,研究不同冰水混合物流型特征对换热特性的影响,以及冰晶在换热融化过程中的动力学行为特征。2. The ice-making circulation circuit of the present invention can study the influence of flow pattern characteristics of different ice-water mixtures on the heat transfer characteristics, and the melting of ice crystals during heat transfer by testing the transparent observation window of the heat transfer pool and the sampling data in the ice storage insulation container. The dynamic behavior characteristics of the process.

3、通过运动平台实现对船只在海洋工况的模拟,六自由度运动平台可通过倾斜摇摆的方式模拟船只在海洋中的沿坐标系不同坐标轴的横摇、纵摇、横倾、纵倾等运动对非能动余热排出系统的影响。3. Realize the simulation of the ship's working conditions in the ocean through the motion platform. The six-degree-of-freedom motion platform can simulate the roll, pitch, heel, and trim of the ship along the different coordinate axes of the coordinate system in the ocean by tilting and swinging. Effect of isomotion on passive waste heat removal system.

附图说明Description of drawings

图1为制冰循环回路系统图。Figure 1 is a system diagram of the ice making cycle loop.

图2为非能动余热排出系统图。Figure 2 is a diagram of the passive waste heat removal system.

具体实施方式Detailed ways

下面结合附图和实例对本发明进行详细说明:The present invention is described in detail below in conjunction with accompanying drawing and example:

如图1和图2所示,本发明一种极地环境核动力装置非能动余排热工水力试验装置,低温水箱301出口管道上游连接第二控制阀门702,第二控制阀门702下游连接位于较低高度的储冰保温容器2入口,该设置的主要作用是通过重力将低温水箱301中配置的低温海水注入储冰保温容器2中调节冰晶颗粒和水的比例。低温水箱301出口通过保温管道经过第一控制阀门701后连接位于较低高度的制冰机1入口管道,为制冰机1提供制冰所需的海水。进行试验时优先开启低温水箱301与制冰机1之间的第一控制阀门701将低温海水注入到制冰机1中开始制冰,当制冰机中的冰晶颗粒满足试验基本需求后,开启制冰机输出口,使混合物流体进入储冰保温容器2,测量其中冰水混合物冰晶含量。该过程同时打开低温水箱301出口管道第二控制阀门702向储冰保温容器2中注入低温海水进一步调控冰晶含量。制冰机1和储冰保温容器2间的保温管道上设置第一止回阀801防止冰水混合物倒流。As shown in Fig. 1 and Fig. 2, the present invention is a thermal-hydraulic test device for passive residual discharge of a nuclear power plant in a polar environment. The main function of the low-height ice storage and heat preservation container 2 is to inject the low-temperature seawater configured in the low temperature water tank 301 into the ice storage heat preservation container 2 by gravity to adjust the ratio of ice crystal particles and water. The outlet of the low-temperature water tank 301 passes through the first control valve 701 through the insulation pipe and then connects to the inlet pipe of the ice maker 1 at a lower height to provide the ice maker 1 with seawater required for ice making. During the test, the first control valve 701 between the low-temperature water tank 301 and the ice maker 1 is preferentially opened to inject low-temperature seawater into the ice maker 1 to start making ice. When the ice crystal particles in the ice maker meet the basic requirements of the test, open The output port of the ice maker allows the mixture fluid to enter the ice storage and heat preservation container 2, and measures the ice crystal content of the ice-water mixture therein. During this process, the second control valve 702 of the outlet pipeline of the low-temperature water tank 301 is opened to inject low-temperature seawater into the ice storage and heat preservation container 2 to further regulate the ice crystal content. A first check valve 801 is provided on the insulation pipeline between the ice maker 1 and the ice storage and insulation container 2 to prevent the ice-water mixture from flowing back.

如图1所示,储冰保温容器2出口管道下游连接第二止回阀802,以及第一离心泵401,在冰水混合物调配过程中关闭储冰保温容器2输出口,当冰晶采样结果满足试验需求后,开启储冰保温容器2输出口与第三控制阀门703与第一离心泵401将冰水混合物导入制冰循环回路管道,并保持控制第三控制阀门703开启的状态,保持第四控制阀门704的关闭状态,当冰水混合物流体在试验换热水池5中的水位达到试验需求后,调节第四控制阀门704的开度以及第二离心泵402的功率,使试验换热水池5进出口流量保持平衡,内部水位始终在试验要求范围内。在水位保持稳定的过程中由第一流量监测仪器901与第二流量监测仪器902记录试验换热水池5进出口流量数据,通过第一温度监测仪器1001和第二温度监测仪器1002,记录试验换热水池5进出口流体温度数据,由差压传感器18记录流体通过试验换热水池后的压降数据。As shown in Figure 1, the downstream of the outlet pipeline of the ice storage and heat preservation container 2 is connected with the second check valve 802 and the first centrifugal pump 401, and the outlet of the ice storage and heat preservation container 2 is closed during the preparation of the ice-water mixture. After the test requirement, open the output port of the ice storage and heat preservation container 2, the third control valve 703 and the first centrifugal pump 401 to introduce the ice-water mixture into the ice-making circulation circuit pipeline, and keep the state of controlling the opening of the third control valve 703, and keep the fourth Control the closed state of the valve 704. When the water level of the ice-water mixture fluid in the test heat exchange pool 5 reaches the test requirement, adjust the opening degree of the fourth control valve 704 and the power of the second centrifugal pump 402 to make the test heat exchange pool 5 The inlet and outlet flows are kept in balance, and the internal water level is always within the range required by the test. In the process of keeping the water level stable, the first flow monitoring instrument 901 and the second flow monitoring instrument 902 record the flow data at the inlet and outlet of the test heat exchange pool 5, and the first temperature monitoring instrument 1001 and the second temperature monitoring instrument 1002 record the test exchange flow data. The temperature data of the fluid at the inlet and outlet of the hot water pool 5 is recorded by the differential pressure sensor 18 as the pressure drop data after the fluid passes through the test heat exchange pool.

图2为池式非能动余热排出系统试验回路,进行试验操作时,依次开启第七控制阀门707,水泵16,使管壳式换热系统17管侧冷却水进行循环。当制冰循环回路能够维持换热水池水位稳定后,开启第八控制阀门708根据试验的蒸汽参数需求使供水箱303注入对应的水量,随后保持第五控制阀门705与第六控制阀门706的开启,逐步提高电加热蒸发器功率产生蒸汽,记录第三流量计903与第四流量计904显示的流量数据,当蒸汽需求达到试验要求参数后关闭管壳式换热系统17独立回路水泵16,仅由试验换热水池5对管内蒸汽进行冷却并建立自然循环。试验装置完全启动后,通过试验换热水池5的透明窗口观测冰晶融化现象,判断冰水混合物流型特征,通过各监测系统记录试验换热水池5与管束式换热器14,进出口流量,压力,温度参数变化。试验停机阶段,开启管壳式换热系统17独立回路水泵16,进行额外冷凝,逐步降低电加热蒸发系统13功率。电加热蒸发系统13完全关闭后,关闭制冰机1以及低温水池第二控制阀门702,同时关闭第一控制阀门701,以及第一离心泵401,保持第四控制阀门704与第二离心泵402的开启,直至将回路管道中冰水混合物全部抽入储冰保温容器2中,最终关闭第四控制阀门704与第二离心泵402,清理试验换热水池底部残留杂物。Figure 2 is the test circuit of the pool-type passive waste heat removal system. During the test operation, the seventh control valve 707 and the water pump 16 are opened in sequence to circulate the cooling water on the tube side of the shell-and-tube heat exchange system 17. When the ice-making circulation circuit can maintain the water level in the heat exchange pool stable, open the eighth control valve 708 to inject the corresponding amount of water into the water supply tank 303 according to the steam parameter requirements of the test, and then keep the fifth control valve 705 and the sixth control valve 706 open , gradually increase the power of the electric heating evaporator to generate steam, record the flow data displayed by the third flowmeter 903 and the fourth flowmeter 904, and turn off the independent loop water pump 16 of the shell-and-tube heat exchange system 17 when the steam demand reaches the required parameters of the test. The steam in the pipe is cooled by the test heat exchange pool 5 and a natural circulation is established. After the test device is fully started, observe the ice crystal melting phenomenon through the transparent window of the test heat exchange pool 5, judge the flow pattern characteristics of the ice-water mixture, record the test heat exchange pool 5 and the tube bundle heat exchanger 14, the inlet and outlet flow rates through each monitoring system, Pressure, temperature parameters change. During the shutdown stage of the test, the independent loop water pump 16 of the shell-and-tube heat exchange system 17 was turned on for additional condensation, and the power of the electric heating evaporation system 13 was gradually reduced. After the electric heating evaporation system 13 is completely closed, close the ice maker 1 and the second control valve 702 of the low-temperature pool, and at the same time close the first control valve 701 and the first centrifugal pump 401, and keep the fourth control valve 704 and the second centrifugal pump 402 until all the ice-water mixture in the loop pipeline is pumped into the ice storage and heat preservation container 2, and finally close the fourth control valve 704 and the second centrifugal pump 402 to clean up the residual debris at the bottom of the test heat exchange pool.

Claims (8)

1.一种极地环境核动力装置非能动余排热工水力试验装置,包括制冰循环回路和池式非能动余热排出系统试验回路;1. A thermal-hydraulic test device for passive residual heat removal of a nuclear power plant in a polar environment, including an ice-making cycle circuit and a pool-type passive waste heat removal system test circuit; 所述制冰循环回路包括制冰回路(11)和六自由度运动换热水池(12),所述制冰回路(11)包括由保温管道连接的制冰机(1)、储冰保温容器(2)和低温水箱(301),储冰保温容器(2)中的冰晶用于储存制冰机(1)输入的冰水混合物,制冰机(1)和储冰保温容器(2)间的保温管道上设置第一止回阀(801)防止冰水混合物倒流;低温水箱(301)通过保温管道向制冰机(1)与储冰保温容器(2)提供低温海水,并分别由保温管道上的第一控制阀门(701)和第二控制阀门(702)控制流量;储冰保温容器(2)输出的冰水混合物进入输出管道并通过第二止回阀(802)后,由第一离心泵(401)驱动进入制冰循环回路主管道中;六自由度运动换热水池(12)由六自由度运动台架(6)、设置在六自由度运动台架(6)上的试验换热水池(5)组成,试验换热水池(5)入口和出口间设置差压传感器(18);六自由度运动换热水池(12)上游第一离心泵(401)输出的冰水混合物进入制冰循环回路主管道后依次通过第三控制阀门(703)、第一流量监测仪器(901)和第一温度监测仪器(1001)后进入试验换热水池(5)壁面入口管道中;试验换热水池(5)底面出口管道输出的流体进入制冰循环回路主管道后依次经过第二温度监测仪器(1002),第二流量监测仪器(902)、第四控制阀门(704)和第二离心泵(402)后进入储冰保温容器(2)构成回路;The ice-making circulation loop includes an ice-making loop (11) and a six-degree-of-freedom motion heat exchange pool (12), and the ice-making loop (11) includes an ice maker (1) connected by an insulation pipeline, an ice storage insulation container (2) and the low-temperature water tank (301), the ice crystals in the ice-storage insulation container (2) are used to store the ice-water mixture input by the ice machine (1), between the ice machine (1) and the ice-storage insulation container (2) The first check valve (801) is set on the insulation pipeline to prevent the ice-water mixture from flowing back; The first control valve (701) and the second control valve (702) on the pipeline control the flow; the ice-water mixture output from the ice storage container (2) enters the output pipeline and passes through the second check valve (802). A centrifugal pump (401) is driven into the main pipeline of the ice-making circulation circuit; the six-degree-of-freedom motion heat exchange pool (12) is composed of a six-degree-of-freedom motion bench (6), and the test set on the six-degree-of-freedom motion bench (6) The heat exchange pool (5) consists of a differential pressure sensor (18) installed between the inlet and outlet of the test heat exchange pool (5); the ice-water mixture output by the first centrifugal pump (401) upstream of the six-degree-of-freedom movement heat exchange pool (12) After entering the main pipeline of the ice-making circulation loop, it passes through the third control valve (703), the first flow monitoring instrument (901) and the first temperature monitoring instrument (1001) in sequence, and then enters the wall inlet pipeline of the test heat exchange pool (5); The fluid output from the outlet pipe on the bottom surface of the heat exchange pool (5) enters the main pipe of the ice making circulation circuit and then passes through the second temperature monitoring instrument (1002), the second flow monitoring instrument (902), the fourth control valve (704) and the second The centrifugal pump (402) enters into the ice storage heat preservation container (2) to form a circuit; 所述池式非能动余热排出系统试验回路包括电加热蒸发系统(13)、管束式换热器(14)、管壳式换热系统(17)和供水箱(303);电加热蒸发系统(13)主要作用为将供水箱(303)中的液态水加热为试验所需的蒸汽,并根据试验需求控制对应的蒸汽参数,电加热蒸发系统(13)下游管道连接第五控制阀门(705)和第三流量计(903),用于监测和控制蒸汽流量;第三流量计(903)下游管道连接管束式换热器(14)上端管侧入口,同时管侧入口管道设置第三温度传感器(1003),监测进入管束式换热器管侧入口的蒸汽温度参数;管束式换热器(14)浸没在试验换热水池(5)中的冰水混合物流体中进行换热,并研究与低温流体的换热特性,管束式换热器出口管道位于管束式换热器(14)下端,与入口有一定的高度差便于形成自然循环;管束式换热器(14)下端出口管道连接第四流量计(904)和第六控制阀门(706),控制和监测余热排出换热器出口流体流量,同时下端出口管道设置第四温度传感器(1004),监测管束出口流体温度参数;第六控制阀门(706)下游连接管壳式换热系统(17)壳侧入口,管壳式换热系统(17)用于将管道中未完全冷凝的蒸汽冷凝为液态水便于重新加热为蒸汽,同时当试验回路中流体温度过高时进行冷却,防止事故的发生;管壳式换热系统(17)中电加热蒸发器(15)壳侧下游连接电加热蒸发系统(13)入口,将冷凝后的流体重新导入电加热蒸发系统中加热构成循环回路;管壳式换热系统(17)中电加热蒸发器(15)管侧依次通过第七控制阀门(707)、水泵(16)和冷却水箱(302)构成闭合回路,使壳侧流体循环流动将管侧流体的热量导出。The test circuit of the pool type passive waste heat removal system includes an electric heating evaporation system (13), a tube bundle heat exchanger (14), a shell and tube heat exchange system (17) and a water supply tank (303); the electric heating evaporation system ( 13) The main function is to heat the liquid water in the water supply tank (303) into the steam required for the test, and control the corresponding steam parameters according to the test requirements. The downstream pipeline of the electric heating evaporation system (13) is connected to the fifth control valve (705) And the third flowmeter (903), used to monitor and control the steam flow; the downstream pipeline of the third flowmeter (903) is connected to the tube side inlet on the upper end of the tube bundle heat exchanger (14), and the tube side inlet pipeline is provided with a third temperature sensor (1003), monitoring the steam temperature parameter entering the tube side inlet of the tube bundle heat exchanger; the tube bundle heat exchanger (14) is immersed in the ice-water mixture fluid in the test heat exchange pool (5) for heat exchange, and research and The heat transfer characteristics of the low-temperature fluid, the outlet pipe of the tube bundle heat exchanger is located at the lower end of the tube bundle heat exchanger (14), and there is a certain height difference from the inlet to facilitate the formation of natural circulation; the outlet pipe at the lower end of the tube bundle heat exchanger (14) is connected to the second The four flowmeters (904) and the sixth control valve (706) control and monitor the outlet fluid flow rate of the waste heat discharge heat exchanger, and at the same time, the fourth temperature sensor (1004) is installed on the outlet pipe at the lower end to monitor the temperature parameters of the outlet fluid of the tube bundle; the sixth control The downstream of the valve (706) is connected to the shell-side inlet of the shell-and-tube heat exchange system (17). When the fluid temperature in the test loop is too high, it is cooled to prevent accidents; in the shell-and-tube heat exchange system (17), the shell side of the electric heating evaporator (15) is connected to the inlet of the electric heating evaporation system (13) downstream, and the condensed The fluid is re-introduced into the electric heating evaporation system for heating to form a circulation loop; in the shell-and-tube heat exchange system (17), the tube side of the electric heating evaporator (15) passes through the seventh control valve (707), the water pump (16) and the cooling water tank ( 302) A closed circuit is formed, so that the fluid on the shell side circulates and the heat of the fluid on the tube side is exported. 2.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,所述制冰回路(11)能够控制冰水混合物中冰晶含量。2. A thermal-hydraulic test device for passive residual exhaust of a nuclear power plant in a polar environment according to claim 1, wherein the ice-making circuit (11) can control the ice crystal content in the ice-water mixture. 3.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,所述试验换热水池(5)中使用一个挡板将流动空间分为两部分,出口位于试验换热水池(5)底部。3. The thermal-hydraulic test device for passive residual exhaust of a nuclear power plant in a polar environment according to claim 1, wherein a baffle plate is used in the test heat exchange pool (5) to divide the flow space into two parts. part, the outlet is located at the bottom of the test heat exchange pool (5). 4.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,所述制冰循环回路中连接管道表面均覆盖有保温材料,能够使回路运行温度维持在-5℃—0℃范围内。4. The thermal-hydraulic test device for passive residual discharge of a nuclear power plant in a polar environment according to claim 1, wherein the surfaces of the connecting pipes in the ice-making circulation loop are covered with heat-insulating materials to enable the loop to run The temperature is maintained in the range of -5°C to 0°C. 5.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,管束式换热器(14)管外与-5℃-0℃的冰水混合物直接接触,管内流动320℃-350℃的蒸汽。5. The thermal-hydraulic test device for passive residual exhaust of a nuclear power plant in a polar environment according to claim 1, characterized in that the tube-bundle heat exchanger (14) is connected with ice water at -5°C-0°C outside the tube The mixture is in direct contact, and steam at 320°C-350°C flows in the tube. 6.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,六自由度运动换热水池中试验换热水池(5)具有透明观测窗口用于观察冰水混合物流型变化。6. A kind of thermal-hydraulic test device for passive residual discharge of nuclear power plant in polar environment according to claim 1, characterized in that, the test heat exchange pool (5) in the six-degree-of-freedom motion heat exchange pool has a transparent observation window. To observe the change of flow pattern of ice-water mixture. 7.根据权利要求1所述的一种极地环境核动力装置非能动余排热工水力试验装置,其特征在于,六自由度运动台架(6)有多根活塞支撑杆连接上支撑面和下支撑面,试验换热水池(5)与上支撑面之间采用螺栓固定。7. A kind of thermal-hydraulic test device for passive residual discharge of nuclear power plant in polar environment according to claim 1, characterized in that, the six-degree-of-freedom motion bench (6) has multiple piston support rods connected to the upper support surface and The lower support surface, the test heat exchange pool (5) and the upper support surface are fixed by bolts. 8.权利要求1至7任一项所述的一种极地环境核动力装置非能动余排热工水力试验装置的试验方法,其特征在于:进行极地低温环境模拟试验时开启制冰循环回路,同时开启电加热蒸发器(15)生成320℃-350℃的蒸汽,使管束式换热器(14)管内通过高温蒸汽,管外接触-5℃-0℃的冰水混合物,通过调节六自由度运动台架(6)上支撑面的水平角度模拟非能动余热排出系统在极地低温环境叠加海洋倾斜工况下的热工水力特性过程,该过程中各循环回路的流量、温度、压力参数通过第一至第四流量监测仪器、第一至第四温度监测仪器、差压传感器(18)测量;通过试验过程中从储冰保温容器(2)提取冰水混合物进行检测确定冰晶颗粒含量,透过试验换热水池(5)的观测窗观察测量冰水混合物流型变化,在试验换热水池(5)出入口分别采样,检测换热过程前后冰晶颗粒的含量变化,以研究冰晶颗粒在换热过程中的动力学特征。8. The test method of a passive residual exhaust thermal-hydraulic test device for a nuclear power plant in a polar environment according to any one of claims 1 to 7, characterized in that: the ice-making circulation loop is opened when performing a simulation test of a polar low-temperature environment, At the same time, the electric heating evaporator (15) is turned on to generate steam at 320°C-350°C, so that high-temperature steam passes through the tube bundle heat exchanger (14), and the outside of the tube contacts the ice-water mixture of -5°C-0°C. The horizontal angle of the support surface on the high-degree motion platform (6) simulates the thermal-hydraulic characteristic process of the passive waste heat removal system in the polar low-temperature environment superimposed on the ocean tilting condition. In this process, the flow, temperature and pressure parameters of each circulation loop are passed The first to fourth flow monitoring instruments, the first to fourth temperature monitoring instruments, and the differential pressure sensor (18) measure; during the test process, the ice-water mixture is extracted from the ice storage and heat preservation container (2) to detect and determine the content of ice crystal particles. Through the observation window of the test heat exchange pool (5), observe and measure the flow pattern change of the ice-water mixture, take samples at the entrance and exit of the test heat exchange pool (5), and detect the content change of ice crystal particles before and after the heat exchange process, so as to study the effect of ice crystal particles on heat exchange. Kinetic characteristics of the process.
CN202210663304.0A 2022-06-13 2022-06-13 Passive residual heat hydraulic test device and method for polar environment nuclear power device Expired - Fee Related CN114999682B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202210663304.0A CN114999682B (en) 2022-06-13 2022-06-13 Passive residual heat hydraulic test device and method for polar environment nuclear power device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202210663304.0A CN114999682B (en) 2022-06-13 2022-06-13 Passive residual heat hydraulic test device and method for polar environment nuclear power device

Publications (2)

Publication Number Publication Date
CN114999682A CN114999682A (en) 2022-09-02
CN114999682B true CN114999682B (en) 2023-06-20

Family

ID=83033252

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202210663304.0A Expired - Fee Related CN114999682B (en) 2022-06-13 2022-06-13 Passive residual heat hydraulic test device and method for polar environment nuclear power device

Country Status (1)

Country Link
CN (1) CN114999682B (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115312214B (en) * 2022-09-16 2024-08-20 中国核动力研究设计院 Self-resetting type inclination-resistant swinging CIS water inlet heat-insulating valve device
CN116884655B (en) * 2023-09-08 2023-11-10 中国核动力研究设计院 Method and device for determining influence of external force field on thermal safety, nuclear reactor and equipment

Citations (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07181279A (en) * 1993-12-24 1995-07-21 Hitachi Ltd Floating nuclear power plant
JP2003167089A (en) * 2001-11-29 2003-06-13 Toshiba Corp Nuclear energy facility internal cooling system
JP2004084964A (en) * 2002-08-22 2004-03-18 Toyo Eng Works Ltd Ice heat accumulator
CN201589481U (en) * 2009-09-25 2010-09-22 天津商业大学 A system for producing fluidized ice from seawater
CN104021823A (en) * 2014-05-23 2014-09-03 中国核动力研究设计院 Waste heat long-term passive lead-out system of floating-type nuclear power station
CN106653109A (en) * 2016-12-30 2017-05-10 福建福清核电有限公司 Experimental research device for secondary side passive residual heat removal system (PRS)
KR101815958B1 (en) * 2016-11-25 2018-02-21 한국과학기술원 Passive containment cooling system for pressurized water reactor using phase-change material
CN108109708A (en) * 2017-12-08 2018-06-01 西安交通大学 Villiaumite cools down ball bed high-temperature heap reactor core fluid interchange experimental system for simulating
FR3061709A1 (en) * 2017-01-08 2018-07-13 Claude Favy DEVICE FOR THE PRODUCTION OF A MIXTURE OF CRYSTALS OF ICE AND FRESHWATER.
CN110021447A (en) * 2018-01-10 2019-07-16 中广核(北京)仿真技术有限公司 A kind of secondary side passive residual heat deriving system
CN209149828U (en) * 2018-11-13 2019-07-23 中国舰船研究设计中心 A kind of passive residual heat removal system experimental rig of multiple-loop coupling
CN110164569A (en) * 2019-05-14 2019-08-23 中国舰船研究设计中心 A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship
CN111446013A (en) * 2020-04-24 2020-07-24 上海核工程研究设计院有限公司 Marine environment secondary side passive waste heat removal system and use method
CN112880967A (en) * 2021-01-11 2021-06-01 西安交通大学 Multi-loop natural circulation experimental device and method under six-degree-of-freedom motion condition
CN112881386A (en) * 2021-01-11 2021-06-01 西安交通大学 Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition
CN112885491A (en) * 2021-01-11 2021-06-01 西安交通大学 Loop cycle characteristic experiment system and method under six-degree-of-freedom motion condition
RU2758159C1 (en) * 2020-12-29 2021-10-26 Акционерное Общество "Атомэнергопроект" Passive heat removal system

Patent Citations (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07181279A (en) * 1993-12-24 1995-07-21 Hitachi Ltd Floating nuclear power plant
JP2003167089A (en) * 2001-11-29 2003-06-13 Toshiba Corp Nuclear energy facility internal cooling system
JP2004084964A (en) * 2002-08-22 2004-03-18 Toyo Eng Works Ltd Ice heat accumulator
CN201589481U (en) * 2009-09-25 2010-09-22 天津商业大学 A system for producing fluidized ice from seawater
CN104021823A (en) * 2014-05-23 2014-09-03 中国核动力研究设计院 Waste heat long-term passive lead-out system of floating-type nuclear power station
KR101815958B1 (en) * 2016-11-25 2018-02-21 한국과학기술원 Passive containment cooling system for pressurized water reactor using phase-change material
CN106653109A (en) * 2016-12-30 2017-05-10 福建福清核电有限公司 Experimental research device for secondary side passive residual heat removal system (PRS)
FR3061709A1 (en) * 2017-01-08 2018-07-13 Claude Favy DEVICE FOR THE PRODUCTION OF A MIXTURE OF CRYSTALS OF ICE AND FRESHWATER.
CN108109708A (en) * 2017-12-08 2018-06-01 西安交通大学 Villiaumite cools down ball bed high-temperature heap reactor core fluid interchange experimental system for simulating
CN110021447A (en) * 2018-01-10 2019-07-16 中广核(北京)仿真技术有限公司 A kind of secondary side passive residual heat deriving system
CN209149828U (en) * 2018-11-13 2019-07-23 中国舰船研究设计中心 A kind of passive residual heat removal system experimental rig of multiple-loop coupling
CN110164569A (en) * 2019-05-14 2019-08-23 中国舰船研究设计中心 A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship
CN111446013A (en) * 2020-04-24 2020-07-24 上海核工程研究设计院有限公司 Marine environment secondary side passive waste heat removal system and use method
RU2758159C1 (en) * 2020-12-29 2021-10-26 Акционерное Общество "Атомэнергопроект" Passive heat removal system
CN112880967A (en) * 2021-01-11 2021-06-01 西安交通大学 Multi-loop natural circulation experimental device and method under six-degree-of-freedom motion condition
CN112881386A (en) * 2021-01-11 2021-06-01 西安交通大学 Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition
CN112885491A (en) * 2021-01-11 2021-06-01 西安交通大学 Loop cycle characteristic experiment system and method under six-degree-of-freedom motion condition

Non-Patent Citations (15)

* Cited by examiner, † Cited by third party
Title
Comparison of flow instabilities under static condition and marine motion conditions based on experiments;Yu Tang;Annals of Nuclear Energy;第70卷;全文 *
Experimental study on thermal hydraulic characteristics of natural circulation loop under motion condition;Zhixian Lai;Applied Thermal Engineering;207;全文 *
Flow fluctuations and flow friction characteristics of vertical narrow rectangular channel under rolling motion conditions;Sichao Tan;Experimental Thermal and Fluid Science;第50卷;全文 *
Research on thermal hydraulic characteristics of integrated reactor in natural circulation operation under ocean motions;Wu Jianbang;Progress in Nuclear Energy;第126卷;全文 *
Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions;Jae-Hak Kim;Nuclear Engineering and Design;第207卷(第1期);全文 *
二次侧非能动余热排出系统传热能力试验研究;徐海岩;吴小航;卢冬华;苏前华;;原子能科学技术(03);全文 *
二次侧非能动余热排出系统运行及换热特性研究;李亮国;苏前华;郝陈玉;余健明;孟祥飞;吴小航;卢冬华;朱峰;;核科学与工程(04);全文 *
先进堆非能动余热排出系统综合试验研究;卓文彬;黄彦平;肖泽军;刘军;卢姗姗;荚川;;中国核科技报告(02);全文 *
摇摆条件下非能动余热排出系统运行特性的试验与理论研究;李勇全;鄢炳火;于雷;;原子能科学技术(05);全文 *
海水淡化堆非能动余热排出特性模拟实验研究;聂常华;许世杰;刘逊;卓文彬;李长林;郑华;李朋洲;余庆林;;核动力工程(06);全文 *
海洋条件对船用核动力堆余热排出系统特性的影响;苏光辉,张金玲,郭玉君秋穗正,喻真烷,贾斗南;原子能科学技术(06);全文 *
自流冷却在船用堆非能动余热排出系统中的初步应用研究;袁添鸿;蔡琦;于雷;傅晟威;郝建立;;海军工程大学学报(02);全文 *
舰船核动力装置非能动余热排出系统运行特性;彭军;于雷;;舰船科学技术(07);全文 *
非能动余热排出系统数学模型研究与运行特性分析;于雷;谢海燕;蔡章生;;核科学与工程(03);全文 *
非能动安全壳冷却系统瞬态特性试验研究;程诚;文青龙;卢冬华;吴小航;牛文华;魏淑虹;;核动力工程(01);全文 *

Also Published As

Publication number Publication date
CN114999682A (en) 2022-09-02

Similar Documents

Publication Publication Date Title
CN114999682B (en) Passive residual heat hydraulic test device and method for polar environment nuclear power device
CN104966536B (en) A kind of high temperature refrigerant heat transfer experiments system and method with conduction oil as hot fluid
CN109473187B (en) Visualization experiment system and method for two-layer fluid turbulence process and heat transfer characteristics under ocean conditions
CN108761022B (en) Liquid lead bismuth alloy thermal hydraulic characteristic and corrosion characteristic experiment system
CN107238627B (en) Comprehensive experiment loop system for forced circulation of heat conduction oil working medium
CN107402231A (en) One kind is applied under dynamic condition hot-working hydraulic characteristic research experiment device in heating rod beam passage
CN108918175B (en) Thermal performance test system
CN106248673A (en) A Visual Research Device for Bubble Dynamics under Dynamic Motion Conditions
CN202216925U (en) Open heat exchanger pilot test platform
CN107632042B (en) Shell and tube heat exchanger single-phase heat transfer experimental test platform and test method
CN110223790B (en) External cooling test bed for pressure vessel for retention in melt pile
CN109520915B (en) Low-pressure low-altitude difference natural circulation test device
CN114441587B (en) An experimental device for measuring the performance of phase change materials in temperature difference utilization processes
CN108732304A (en) A kind of non-metallic pipe pipe water delivery dynamic scale formation experiment circuit and method
CN204760047U (en) Structural integrity test platform under reactor pressure vessel IVR condition
CN207423766U (en) A kind of experimental rig
CN207623492U (en) A kind of battery performance test device based on liquid cooling technology
CN107860704A (en) A kind of salt resistance class erosion test device
CN118837505A (en) Gas phase leading flowing system hydrate loop experiment system and test method
CN114965566B (en) A universal experimental bench and experimental method for high-temperature heat pipe startup and flow heat transfer
CN208736687U (en) A thermal performance testing system
CN216285014U (en) A Visualized CO2 Mixed Working Fluid Saturation State Point Test System
CN115541280A (en) Thermal performance and flow resistance testing rack for small-temperature-difference plate heat exchanger
CN115013139B (en) A simulation test system for performance analysis of welded pipe fittings in marine cooling water systems
CN219121940U (en) An experimental device for investigating the shear behavior of rocks

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
CF01 Termination of patent right due to non-payment of annual fee
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20230620