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Dynamic scaling characteristics of single-phase natural circulation based on different strain transformations

Nuclear Science and Techniques 2023年第9期34卷 128-141页

作者： Jia-Ning Xu Xiang-Bin Li Zhong-Yi Wang Yu-Sheng Liu De-Chen Zhang Qiao Wu School of Nuclear Science and Engineering North China Electric Power UniversityBeijing 102206China Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy Beijing 102206China China Institute of Nuclear Industry Strategy BeijingChina Nuclear and Radiation Safety Center MEEBeijing 100082China Department of Nuclear Engineering Oregon State UniversityCorvallisOR 97331USA

To understand the dynamical system scaling(DSS)analysis theory,the applicability of DSSβ-andω-strain transformation methods for the scaling analysis of complex loops was explored.A simplified model consisting of two loops was established based on the primary and secondary sides of a nuclear reactor,andβ-andω-strain transformation methods were used to ana-lyze the single-phase natural circulation in the primary *** comparison with the traditional method,simplified DSSβ-andω-strain methods were developed based on the standard scaling *** strain parameters in these four methods were modified to form multiple groups of scaled-down *** transient process of the natural circulation was simulated using the Relap5 code,and the variation in the dynamic flow characteristics with the strain numbers was obtained using different scaling *** results show that both the simplified and standard DSS methods can simulate the dynamic characteristics of natural circulation in the primary *** scaled-down cases in the simplified method exhibit the same geometric scaling and correspond to small core power *** contrast,different scaled-down cases in the standard DSS method correspond to different geometric scaling criteria and require more *** dynamic process of natural circula-tion can be simulated more accurately using the standard DSS method.

关键词： Dynamical system scaling analysis β-strain transformation ω-strain transformation natural circulation

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Research on the natural circulation characteristic of deep borehole heat exchanger and the influences on the water circulation resistance

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Building Simulation 2024年第12期17卷 2213-2232页

作者： Jiewen Deng Yanhui Wang Yangyang Su Yuanguo Wang Yin Chen Minghui Ma Chenwei Peng Wanlong Cai Ji Li Qingpeng Wei Hubei Key Laboratory of Multi-media Pollution Cooperative Control in Yangtze Basin School of Environmental Science&EngineeringHuazhong University of Science and TechnologyWuhanHubei 430074China Department of Building Science Tsinghua UniversityBeijing 100084China School of Human Settlements and Civil engineering Xi'an Jiaotong UniversityXi'anShaanxi 710049China China Academy of Building Research Bejing 100101China

As deep borehole heat exchangers(DBHEs)extract heat from geothermal energy with depth of 2–3 kilometers,the circulation water pressure drop is larger than that of shallow-depth borehole heat exchangers,influenced by the water flow *** paper conducted field tests and simulation analysis to study the heat transfer performance and water circulation resistance of DBHE in coupled,where the natural circulation characteristic has been discovered and analyzed *** show that the water temperature and density variation along DBHE forms the driving force of natural *** mechanical flow rate of 6.0 kg/s and inlet water temperature of 20.0℃,the natural circulation flow rate reaches about 2.2 kg/s with transient heat extraction power of 78.5 kW,without energy consumption of water *** the larger inlet water temperature,smaller mechanical water flow rate,higher inner tube thermal conductivity coefficient and larger depth of DBHE all contribute to the larger natural circulation water flow *** addition,the natural circulation could effectively decrease the comprehensive water pressure drops of DBHE,which is about 47.3%smaller than the calculated value of traditional *** the natural circulation characteristic has significant influence on the heat transfer performance of DBHE,and also on the energy performance of whole heat pump systems.

关键词： deep borehole heat exchangers water circulation resistance natural circulation field tests simulation analysis

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Thermo-hydraulic experimental validation of an integrated modular small reactor operating in full power natural circulation

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Science China(Technological Sciences) 2014年第1期57卷 1-8页

作者： YANG XingTuan REN Cheng LIU ZhiYong TU JiYuan JIANG ShengYao Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education Institute of Nuclear and New Energy Technology Tsinghua University

Small reactors have become a new hotspot of international nuclear energy *** nuclear heating reactor(NHR)technology developed by Tsinghua University is an important multipurpose small reactor solution with features such as high integration,modular design and full power natural circulation.A new small reactor based on the existing NHR-200 reactor was developed by the Institute of Nuclear and New Energy Technology of Tsinghua University.A full-scale natural circulation test loop with the same operating parameters as the actual reactor was built in order to experimentally validate the natural circulation ability of the reactor primary loop and heat-transfer ability of fuel assemblies and heat *** results are given in detail,including parameter validation of the reactor primary loop,flow rules of the natural circulation and heat-transfer coefficients of heaters and heat exchangers,which can be directly used in the actual reactor as a reference for optimization ***,a characteristic parameter k is proposed to represent the natural circulation ability of a *** using the new data arrangement method in the form of parameter k,comprehensive experimental results of the natural circulation can be represented by a simple integrated *** work in this paper is of importance in broadening application fields and pushing forward commercialization of the NHR type reactors.

关键词： small reactor natural circulation validation experiment

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Startup scheme optimization and flow instability of natural circulation lead-cooled fast reactor SNCLFR-100

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Nuclear Science and Techniques 2021年第11期32卷 191-200页

作者： Wen-Shun Duan Ze-Ren Zou Xiao Luo Hong-Li Chen School of Nuclear Science and Technology University of Science and Technology of ChinaHefei 230027China

Owing to the inherent instability of the natural circulation system,flow instability can easily occur during the operation of a natural circulation lead-cooled fast reactor,especially during the startup phase.A comprehensive startup scheme for SNCLFR-100,including primary and secondary circuits,is proposed in this *** references existing more mature startup schemes in various reactor *** additionally considers the restriction conditions on the power increase in other schemes and the characteristics of lead-based *** this basis,the multi-scale coupling code ATHLET-OpenFOAM was used to study the flow instability in the startup phase under different power-step amplitudes and power duration *** results showed that obvious flow instability phenomena were found in the different startup schemes,such as the short-term backflow phenomenon of the core at the initial time of the ***,an obvious increase in the flow rate and temperature to the peak value at the later stage of a continuous power rise was observed,as well as continuous oscillations before reaching a steady *** was determined that the scheme with smaller power-step amplitude and a longer power duration time requires more time to start the ***,it will be more conducive to the safe and stable startup of the reactor.

关键词： natural circulation Lead-cooled fast reactor Startup scheme Flow instability Multi-scale coupling

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Calculation of natural circulation under heaving motion

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Science China(Technological Sciences) 2014年第8期57卷 1658-1669页

作者： FENG BeiBei YANG XingTuan JIANG ShengYao Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education Institute of Nuclear and New Energy TechnologyTsinghua University

Wide validation of self-developed program of natural circulation under oceanic conditions has been conducted compared with experimental data of inclination,zero-power condition and hot-state *** were performed on a full-scale,whole parameterization natural circulation loop designed with reference to 5 MW experimental low temperature nuclear heating reactor(NHR)of Tsinghua *** of natural circulation and parameter effect under heaving motion was carried out using the program and comparison of heaving,inclination and rolling on natural circulation respectively to reveal the influence *** indicate that:(1)significant influence of heaving motion on natural circulation was observed,and heaving motion with high level of strength and long cycle would lead to severe flow fluctuation;(2)slight effect was caused by short cycle heaving motion which was completely different from long cycle heaving motion;(3)comprehensive action of alternating force and flow density distribution would result in natural circulation under heaving motion;(4)most severe accidents maybe result from the long cycle heaving motion rather than inclination and rolling *** of influence of heaving motion on natural circulation could have important reference significance in the optimization design of nuclear reactors.

关键词： natural circulation oceanic condition NHR nuclear engineering

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Onset of Nucleate Boiling in natural circulation Systems Predicted Using the Second Stir Theory

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Tsinghua Science and Technology 2010年第4期15卷 441-446页

作者：周涛杨瑞昌李臻洋张明刘梦影 School of Nuclear Science and Engineering North China Electric Power University Department of Thermal Engineering Tsinghua University

Experimental data and calculated results for the onset of nucleate boiling （ONB） in natural circula- tion systems show that for the same operating conditions, the equilibrium vapor quality for ONB in natural circulation is lower than for forced convections. The differences can be explained using second stir theory. The weak vortices and small stir energy in natural circulation systems result in nucleate boiling occurring earlier than in forced convection systems. In natural circulation systems high mass flow rates are accompa- nied by large kinetic energies and large stir energies, which enables changes in the directions of flow eddies and energy transport. The equilibrium vapor qualities at ONB are then higher at higher mass flow rates. The influence of other flow parameters on ONB can be evaluated by the relationships between these flow pa- rameters and the mass flow rate. The same values can lead to different results due to different eddy direc- tions. This indicates that the quantitative comparability in mathematics cannot be considered as only scien- tific standard. The second stir theory offers a new visual angle for researches on natural circulation.

关键词： natural circulation onset of nucleate boiling (ONB) second stir theory boiling direction

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Thermal-hydraulic stability of a natural circulation system with nuclear feedback

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Nuclear Science and Techniques 1997年第4期 16-21页

作者： Xu Zhan Jie, Chen Li Qiang,Ma Chang Wen and Wu Shao Rong ( Institute of Nuclear Energy Technology, Tsinghua University, Beijing 100084)

ＴｈｅｒｍａｌｈｙｄｒａｕｌｉｃｓｔａｂｉｌｉｔｙｏｆａｎａｔｕｒａｌｃｉｒｃｕｌａｔｉｏｎｓｙｓｔｅｍｗｉｔｈｎｕｃｌｅａｒｆｅｅｄｂａｃｋＸｕＺｈａｎＪｉｅ，ＣｈｅｎＬｉＱｉａｎｇ，ＭａＣｈａｎｇＷｅｎ... 详细信息

ＴｈｅｒｍａｌｈｙｄｒａｕｌｉｃｓｔａｂｉｌｉｔｙｏｆａｎａｔｕｒａｌｃｉｒｃｕｌａｔｉｏｎｓｙｓｔｅｍｗｉｔｈｎｕｃｌｅａｒｆｅｅｄｂａｃｋＸｕＺｈａｎＪｉｅ，ＣｈｅｎＬｉＱｉａｎｇ，ＭａＣｈａｎｇＷｅｎａｎｄＷｕＳｈａｏＲｏｎｇ（Ｉｎ...

关键词： Stability Nuclear feedback Density wave oscillation natural circulation

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An Experimental Research of natural circulation Heat Transfer for PRHR Heat Exchanger in AP1000

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Journal of Energy and Power Engineering 2016年第9期10卷 545-554页

作者： Minghui Duan Yuzhou Chen Yvfeng Lv Weiqing Li Keming Bi Wei Wang Kaiwen Du Han Wang China Institute of Atomic Energy P.O Box 275(59) Beijing 102413 China State Nuclear Power Technology Research & Development Centre Beijing 102209 China

The heat transfer characteristics of the PRHR （passive residual heat removal） HX （heat exchanger） are very important to reactor design and safety assessment of AP1000. The purpose of the present experiment was to obtain the natural circulation data in HX to research the heat transfer behavior. The PRHR HX was simulated by three C-type tubes with prototype sizes immerged in a cooling tank. Separate-effect tests of natural circulation in HX tubes have been performed within wide conditions which could cover the operation conditions in AP1000. The experiment provided lots of important data to indicate heat transfer phenomena of PRHR HX. The test conditions were calculated by RELAP5/MOD3.3. The calculation results agreed well with the experiment. RELAP5 could be applied with proper correlations to analyze the heat transfer in PRHR HX under the test conditions.

关键词： PRHR HX natural circulation separate-effect tests AP1000

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Experimental Study of a Stoppage natural circulation during a Nuclear Heating Reactor LOCA

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Tsinghua Science and Technology 2001年第1期6卷 89-92页

作者：博金海张佑杰姜胜耀 Institute of Nuclear Energy Technology Tsinghua University Beijing 100084 China

The 5MW nuclear heating reactor is an integral natural circulation reactor. The rupture of the coolant penetrating tube is a typical accident causing coolant loss. When the water level drops down to the upper edge of the inlet of the heat exchanger, the natural circulation stops. This influences the core cooling and the stability of the main loop. A series of tests showed that there is a stable drop of pressure, and the heated element temperature is not too high to cause burnout. But the backward flow or flow oscillation in the primary coolant circuit occurs when the flow breaks completely in the end. The whole flow process is described and the mechanism is discussed.

关键词： Nuclear Heating Reactor (NHR) Loss of Coolant Accident (LOCA) natural circulation safety stability

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Scaling Analysis of Thermal-Hydraulics for Steam Generator Passive Heat Removal System

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Journal of Shanghai Jiaotong university(Science) 2014年第2期19卷 219-225页

作者：周源林萌陈金波王汉林 School of Nuclear Science and Engineering Shanghai Jiaotong University The Nuclear Power Institute of China

Steam generator passive heat removal system(SG-PHRS) is used as a passively safe mode to provide decay heat removal in some advanced pressurized water reactors. Due to the structure characteristics of steam generator(SG), there are two natural circulation loops coupling in SG-PHRS in case of a safety-related event. The existing natural circulation scaling criteria could be used to simulate the natural circulation inside SG. Two-phase natural circulation loop is studied carefully, and the dominant effects of SG on behaviors of natural circulation in passive heat removal system are presented. Based on the understanding of SG-PHRS operation, system pressure transient scaling and two-phase natural circulation scaling are analyzed by establishing the relevant continuity,integral momentum and energy equations in one-dimensional area-averaged forms. With modified equations,similarity criteria for SG-PHRS are obtained for engineering application. In addition, equal height simulation and reduced height simulation are studied.

关键词： steam generator natural circulation scaling simulation thermal hydraulics

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