Using deionized water as the working fluid, an experimental study on the resistance characteristics of single-phase and two-phase flow under natural circulation conditions is carried out in a 3 × 3 rod bundle channel. For the single-phase flow, the flow regime transition of rod bundle channel is not as obvious as that of conventional channels such as a circular tube. The flow regime transition in the channel is judged by the change trend of drag coefficient and the flow regime division is obtained. The transition Reynolds number from laminar flow to turbulent flow is approximately 800, and the correlations of the single-phase frictional resistance coefficient for different flow regimes are given. The natural circulation and forced circulation conditions have no obvious influence on the flow state transition. For the two-phase flow, under vertical conditions, a new two-phase frictional pressure drop correlation is fitted on the basis of the Chisholm correlation based on the experimental results. Moreover, the experiment for two-phase flow resistance under the inclined conditions are carried out, and the variation of the two-phase resistance with the mass quality is given, and the correlations of the two-phase friction pressure drop based on different inclination angles are proposed.
{"title":"Study on Natural Circulation Flow Resistance Characteristics in a Rod Bundle Channel","authors":"Zhiqiang Zhu, Tingting Ren, Shuaijun Li, Chunping Tian, Chang-qi Yan, Jianjun Wang","doi":"10.1115/icone29-93292","DOIUrl":"https://doi.org/10.1115/icone29-93292","url":null,"abstract":"\u0000 Using deionized water as the working fluid, an experimental study on the resistance characteristics of single-phase and two-phase flow under natural circulation conditions is carried out in a 3 × 3 rod bundle channel. For the single-phase flow, the flow regime transition of rod bundle channel is not as obvious as that of conventional channels such as a circular tube. The flow regime transition in the channel is judged by the change trend of drag coefficient and the flow regime division is obtained. The transition Reynolds number from laminar flow to turbulent flow is approximately 800, and the correlations of the single-phase frictional resistance coefficient for different flow regimes are given. The natural circulation and forced circulation conditions have no obvious influence on the flow state transition. For the two-phase flow, under vertical conditions, a new two-phase frictional pressure drop correlation is fitted on the basis of the Chisholm correlation based on the experimental results. Moreover, the experiment for two-phase flow resistance under the inclined conditions are carried out, and the variation of the two-phase resistance with the mass quality is given, and the correlations of the two-phase friction pressure drop based on different inclination angles are proposed.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"86 ","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120875299","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Guofu Sun, Y. Zhan, T. Okawa, Mitsuhiro Aoyagi, A. Uchibori, Y. Okano
When a liquid sodium leakage accident occurs in a sodium-cooled fast reactor, the injected sodium collides with structures to produce splashing droplets, which can result in a violent combustion. According to previous studies on circular nozzles, the amount of splash is affected by the state of the jet at the moment of impact. However, the outlet shape of damaged area is hardly to be circular; and meanwhile it influences the flow pattern of jet a lot. Considering about this, in the present work, high-speed cameras were used to observe the jet discharged from oval nozzles vertically downward to investigate the falling process of the jet. The result shows that surface wave appears on the jet and within a certain range of flow velocity it can be observed obviously, meanwhile accelerate the breakup of jet.
{"title":"Experiment Study on the Effect of Nozzle Shape on Liquid Jet Breakup","authors":"Guofu Sun, Y. Zhan, T. Okawa, Mitsuhiro Aoyagi, A. Uchibori, Y. Okano","doi":"10.1115/icone29-93074","DOIUrl":"https://doi.org/10.1115/icone29-93074","url":null,"abstract":"\u0000 When a liquid sodium leakage accident occurs in a sodium-cooled fast reactor, the injected sodium collides with structures to produce splashing droplets, which can result in a violent combustion. According to previous studies on circular nozzles, the amount of splash is affected by the state of the jet at the moment of impact. However, the outlet shape of damaged area is hardly to be circular; and meanwhile it influences the flow pattern of jet a lot. Considering about this, in the present work, high-speed cameras were used to observe the jet discharged from oval nozzles vertically downward to investigate the falling process of the jet. The result shows that surface wave appears on the jet and within a certain range of flow velocity it can be observed obviously, meanwhile accelerate the breakup of jet.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"6 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133307027","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Zhiwei Cao, Zhikang Lin, Miaomiao Xu, Jimin He, Jianyang Song
During a loss-of-coolant-accident (LOCA) transient, the ballooning and burst of the cladding can lead to blockage of flow path and worsen core coolability. Studies have shown that the core coolability is not changed much up to about 60% blockage ratio, while can be threatened by a severe blockage with a high blockage ratio and long blockage length. A blockage simulation model based on the non-coplanar assumption is widely used in LOCA transient analysis. However, regarding the coplanar deformation observed in experiments, validity of this assumption is questionable. Furthermore, it is found that this model cannot predict reasonable results for severe blockage conditions. In this paper, the blockage model is modified for the thermal hydraulic simulation of LOCA transients with the occurrence of severe blockages. Pre-test simulations of a test facility studying the influence of blockage on core coolability have been conducted with the modified model. The results show that, the modified model shows better agreement with the observations in the experiments.
{"title":"A Modified Simulation Model of Blocked Regions After Rod Cladding Deformation During LOCA Transient","authors":"Zhiwei Cao, Zhikang Lin, Miaomiao Xu, Jimin He, Jianyang Song","doi":"10.1115/icone29-92787","DOIUrl":"https://doi.org/10.1115/icone29-92787","url":null,"abstract":"\u0000 During a loss-of-coolant-accident (LOCA) transient, the ballooning and burst of the cladding can lead to blockage of flow path and worsen core coolability. Studies have shown that the core coolability is not changed much up to about 60% blockage ratio, while can be threatened by a severe blockage with a high blockage ratio and long blockage length. A blockage simulation model based on the non-coplanar assumption is widely used in LOCA transient analysis. However, regarding the coplanar deformation observed in experiments, validity of this assumption is questionable. Furthermore, it is found that this model cannot predict reasonable results for severe blockage conditions.\u0000 In this paper, the blockage model is modified for the thermal hydraulic simulation of LOCA transients with the occurrence of severe blockages. Pre-test simulations of a test facility studying the influence of blockage on core coolability have been conducted with the modified model. The results show that, the modified model shows better agreement with the observations in the experiments.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"54 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124937170","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Jesse S. Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang
This paper summarizes the development of a multi-physics code system for evaluation of Crud Induced Power Shift (CIPS) phenomenon experienced in some Pressurized Water Reactors (PWR). CIPS is an unexpected change in reactor core axial power distribution, caused by boron compounds in crud deposited in the high-power fuel assemblies undergoing subcooled boiling. The approach includes a more robust method compared to previous attempts at coupling codes to account for boron deposition at the nodal level within the neutronic model based on the BOA generated CIPS results. This paper describes the updated linkage with a Python script wrapper around the multi-physics code system ANC9/FUELDUTYDRV/VIPRE-W/BOA. The multi-physics code system can then evaluate changes in core power distributions due to boron deposited in the crud for comparison to measured plant cycle flux trace data. The plant flux trace data provides additional wealth of information for reducing BOA conservatism in the CIPS analysis and benchmarking the multi-physics to the plant-specific source term and plant operation. The linkage of the code system along with the application results will be the base for future development to improve CIPS/Crud Induced Localized Corrosion (CILC) risk for a plant, allowing for the potential benefits of more aggressive fuel management via higher duty cores or improved fuel economics.
{"title":"Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models","authors":"Jesse S. Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang","doi":"10.1115/icone29-94476","DOIUrl":"https://doi.org/10.1115/icone29-94476","url":null,"abstract":"\u0000 This paper summarizes the development of a multi-physics code system for evaluation of Crud Induced Power Shift (CIPS) phenomenon experienced in some Pressurized Water Reactors (PWR). CIPS is an unexpected change in reactor core axial power distribution, caused by boron compounds in crud deposited in the high-power fuel assemblies undergoing subcooled boiling. The approach includes a more robust method compared to previous attempts at coupling codes to account for boron deposition at the nodal level within the neutronic model based on the BOA generated CIPS results. This paper describes the updated linkage with a Python script wrapper around the multi-physics code system ANC9/FUELDUTYDRV/VIPRE-W/BOA. The multi-physics code system can then evaluate changes in core power distributions due to boron deposited in the crud for comparison to measured plant cycle flux trace data. The plant flux trace data provides additional wealth of information for reducing BOA conservatism in the CIPS analysis and benchmarking the multi-physics to the plant-specific source term and plant operation. The linkage of the code system along with the application results will be the base for future development to improve CIPS/Crud Induced Localized Corrosion (CILC) risk for a plant, allowing for the potential benefits of more aggressive fuel management via higher duty cores or improved fuel economics.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"56 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116839247","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
An experimental research on the condensation heat transfer characteristic of surface chromium-plated tube was put forwards with non condensation gas. The experimental result suggests that the factors of pressure, air mass fraction and wall subcooling affect the condensation heat transfer process of surface chromium-plated tube, which is similar to that of stainless steel tube. In addition, by comparing with the stainless steel tube, the chromium-plated tube condensation heat transfer capacity changes more obviously with the variation of air mass fraction. That is to say, under the low air mass fraction condition, due to the existence of non condensation gas layer, the difference between those two tube-types is little; but under the high air mass fraction condition, the condensation heat transfer capacity of surface chromium-plated tube is higher than stainless steel tubes lightly. At last, by fitting the experimental data, the empirical formula of condensation heat transfer of surface chrome-plated tube under the condition of non condensing gas is obtained. The deviation is less than 20%.
{"title":"Experimental Study on Condensation Heat Transfer Characteristics of Vertical Surface Chromium-Plated Tube With Condensate Gas","authors":"Xiaofan Hou, Shiwei Yao, Jinrong Jiu, Qianglong Wang, Hanying Chen","doi":"10.1115/icone29-93350","DOIUrl":"https://doi.org/10.1115/icone29-93350","url":null,"abstract":"\u0000 An experimental research on the condensation heat transfer characteristic of surface chromium-plated tube was put forwards with non condensation gas. The experimental result suggests that the factors of pressure, air mass fraction and wall subcooling affect the condensation heat transfer process of surface chromium-plated tube, which is similar to that of stainless steel tube. In addition, by comparing with the stainless steel tube, the chromium-plated tube condensation heat transfer capacity changes more obviously with the variation of air mass fraction. That is to say, under the low air mass fraction condition, due to the existence of non condensation gas layer, the difference between those two tube-types is little; but under the high air mass fraction condition, the condensation heat transfer capacity of surface chromium-plated tube is higher than stainless steel tubes lightly. At last, by fitting the experimental data, the empirical formula of condensation heat transfer of surface chrome-plated tube under the condition of non condensing gas is obtained. The deviation is less than 20%.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"26 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129163819","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The helical-coiled once-through steam generator (H-OTSG) is a key equipment in small modular reactor (SMRs) to be used in heat exchanging between primary side and secondary side. In this study, a 1D Code HTAC (H-OTSG Thermo-hydraulics Analysis Code) is developed to simulate the heat transfer characteristic of H-OTSG and used to prepare the experimental study in future. The H-OTSG is composed by 74 helical tubes which is divided into 10 layers according to the coil diameters. Firstly, a 1D code of H-OTSG is developed with the tube-side thermal-hydraulic model proposed by the present authors and the shell-side model using the thermal-hydraulic model of straight-tube bundle in cross flow. Secondly, 10 inclined straight pipes with different coil curvature ratio are stablished in the 1D code to respectively simulate the helical tube bundle of 10 layers and the shell-side of H-OTSG is model with a vertical annulus. Furthermore, the sensitivity study on the node number is conducted and 99 nodes for each pipe and annulus are fine enough. Thirdly, the simulated result shows the 1D code can used to predict the steady-state heat transfer rate of the H-OTSG under various thermal power. Finally, the sensitivity analysis of the system parameters on the heat transfer rate of H-OTSG is conducted, and the result shows the decrease of tube-side pressure and the increase of shell-side inlet temperature can rise the average HTC of H-OTSG.
{"title":"Development of a 1d Code for Heat Transfer Characteristics of Helical-Coiled Once-Through Steam Generators","authors":"Maolong Liu, Zihan Xu, Yao Xiao, H. Gu","doi":"10.1115/icone29-93035","DOIUrl":"https://doi.org/10.1115/icone29-93035","url":null,"abstract":"\u0000 The helical-coiled once-through steam generator (H-OTSG) is a key equipment in small modular reactor (SMRs) to be used in heat exchanging between primary side and secondary side. In this study, a 1D Code HTAC (H-OTSG Thermo-hydraulics Analysis Code) is developed to simulate the heat transfer characteristic of H-OTSG and used to prepare the experimental study in future. The H-OTSG is composed by 74 helical tubes which is divided into 10 layers according to the coil diameters. Firstly, a 1D code of H-OTSG is developed with the tube-side thermal-hydraulic model proposed by the present authors and the shell-side model using the thermal-hydraulic model of straight-tube bundle in cross flow. Secondly, 10 inclined straight pipes with different coil curvature ratio are stablished in the 1D code to respectively simulate the helical tube bundle of 10 layers and the shell-side of H-OTSG is model with a vertical annulus. Furthermore, the sensitivity study on the node number is conducted and 99 nodes for each pipe and annulus are fine enough. Thirdly, the simulated result shows the 1D code can used to predict the steady-state heat transfer rate of the H-OTSG under various thermal power. Finally, the sensitivity analysis of the system parameters on the heat transfer rate of H-OTSG is conducted, and the result shows the decrease of tube-side pressure and the increase of shell-side inlet temperature can rise the average HTC of H-OTSG.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"14 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127644989","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hajime Furuichi, Shunya Kawada, Y. Mizushima, T. Sanada
This study aims at developing a liquid film sensor with an optical waveguide film (OWF-based sensor) that provides accurate measurements of liquid film thickness. The OWF measurement principle employs detection of light reflected at the liquid film surface with high spatial resolution. Since the curved surface of the liquid film reflects the light and increases measurement error, we proposed a signal processing method to remove the error factor in calculation of the time-averaged thickness. This method requires knowing an appropriate range for the thickness measurement and predicting the surface curvature. We experimentally simulated a liquid film curved surface with a metal test piece, and the test piece was moved with a constant velocity in an acrylic water vessel. We found that an output signal from the OWF-based sensor peaked when the wave passed above the sensor. We calculated the output signal with our 3D ray-tracing simulator of the OWF-based sensor. The simulation results showed that the effect of the curved surface up to the surface curvature of 5.0 mm−1 was negligible based on the good agreement of the liquid film thickness with that of the flat liquid film surface within 6 % difference. Furthermore, we found the surface curvature in the range of 0.1–20.0 mm−1 was able to be predicted using a characteristic of the output signal peak. Consequently, we confirmed the effectiveness of the developed sensor with the OWF-based sensor.
{"title":"Development of Liquid Film Thickness Measurement Considering Effect of Curved Gas-Liquid Interface Based on Optical Waveguide Film","authors":"Hajime Furuichi, Shunya Kawada, Y. Mizushima, T. Sanada","doi":"10.1115/icone29-93405","DOIUrl":"https://doi.org/10.1115/icone29-93405","url":null,"abstract":"\u0000 This study aims at developing a liquid film sensor with an optical waveguide film (OWF-based sensor) that provides accurate measurements of liquid film thickness. The OWF measurement principle employs detection of light reflected at the liquid film surface with high spatial resolution. Since the curved surface of the liquid film reflects the light and increases measurement error, we proposed a signal processing method to remove the error factor in calculation of the time-averaged thickness. This method requires knowing an appropriate range for the thickness measurement and predicting the surface curvature. We experimentally simulated a liquid film curved surface with a metal test piece, and the test piece was moved with a constant velocity in an acrylic water vessel. We found that an output signal from the OWF-based sensor peaked when the wave passed above the sensor. We calculated the output signal with our 3D ray-tracing simulator of the OWF-based sensor. The simulation results showed that the effect of the curved surface up to the surface curvature of 5.0 mm−1 was negligible based on the good agreement of the liquid film thickness with that of the flat liquid film surface within 6 % difference. Furthermore, we found the surface curvature in the range of 0.1–20.0 mm−1 was able to be predicted using a characteristic of the output signal peak. Consequently, we confirmed the effectiveness of the developed sensor with the OWF-based sensor.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"62 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124706738","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
In Generation IV nuclear systems, Sodium Cooled Fast Reactor has attracted extensive attention for its particular advantages. Intermediate Heat Exchanger (IHX) is a significant equipment connecting the primary circuit system and secondary circuit system in Sodium Cooled Fast Reactor. Under normal and accident conditions, the temperature fluctuation of the IHX component may cause the alternating change of the local stress, such as sealing weld zones mixing chamber, and the area between inner and outer sleeves. This fluctuation may result in the thermal fatigue of IHX and consequently affect the safety and economy of the reactor operation. Therefore, it is essential to carry out mechanical analysis by experiments or simulations to ensure the structural stability under complex conditions. However, the mechanical analysis must take transient thermal-hydraulic characteristics as boundary and input conditions. Thus, a thorough thermal-hydraulic assessment of IHX is required to guarantee its security under accident conditions. In this paper, a thermal-hydraulic simulation of IHX was carried out using system code under steady and transient state conditions. Thermal parameters of steady-state calculation agreed well with the design requirements. Transient-state accident conditions, such as emergency shutdown, Station Blackout (SBO), and Steam Generator Tube Rupture (SGTR), were conducted in this paper. In the emergency shutdown, the wall temperature increased from 703.15 K to 798.41 K in three seconds, and then decreased slowly and stabilized at 626.15K. In the SBO accident, the temperature of the primary and secondary circuit fluids fluctuated violently from 0 to 100 seconds. When the secondary side flow drops to 0, the wall temperature of typical positions changes with the inlet temperature of the primary side, showing a trend of rapid decline and stable. In the SGTR accident, the temperature of the heat transfer tube wall increased rapidly during the early stage of the accident. After that, the primary side flow reduced gradually to 0 with the decrease of the secondary side flow. Because of the trend of flow, the temperature of the tube wall decreased rapidly and then increased slowly. Therefore, the results of various accident conditions in this investigation can contribute to the thermal fatigue analysis of IHX in the near future.
{"title":"Numerical Simulation of Transient Thermal-Hydraulic Characteristics of Intermediate Heat Exchanger for Sodium Cooled Fast Reactor Under Accident Conditions","authors":"Xiehu Zeng, Q. Wen, Genxing Bai","doi":"10.1115/icone29-93387","DOIUrl":"https://doi.org/10.1115/icone29-93387","url":null,"abstract":"\u0000 In Generation IV nuclear systems, Sodium Cooled Fast Reactor has attracted extensive attention for its particular advantages. Intermediate Heat Exchanger (IHX) is a significant equipment connecting the primary circuit system and secondary circuit system in Sodium Cooled Fast Reactor. Under normal and accident conditions, the temperature fluctuation of the IHX component may cause the alternating change of the local stress, such as sealing weld zones mixing chamber, and the area between inner and outer sleeves. This fluctuation may result in the thermal fatigue of IHX and consequently affect the safety and economy of the reactor operation. Therefore, it is essential to carry out mechanical analysis by experiments or simulations to ensure the structural stability under complex conditions. However, the mechanical analysis must take transient thermal-hydraulic characteristics as boundary and input conditions. Thus, a thorough thermal-hydraulic assessment of IHX is required to guarantee its security under accident conditions.\u0000 In this paper, a thermal-hydraulic simulation of IHX was carried out using system code under steady and transient state conditions. Thermal parameters of steady-state calculation agreed well with the design requirements. Transient-state accident conditions, such as emergency shutdown, Station Blackout (SBO), and Steam Generator Tube Rupture (SGTR), were conducted in this paper. In the emergency shutdown, the wall temperature increased from 703.15 K to 798.41 K in three seconds, and then decreased slowly and stabilized at 626.15K. In the SBO accident, the temperature of the primary and secondary circuit fluids fluctuated violently from 0 to 100 seconds. When the secondary side flow drops to 0, the wall temperature of typical positions changes with the inlet temperature of the primary side, showing a trend of rapid decline and stable. In the SGTR accident, the temperature of the heat transfer tube wall increased rapidly during the early stage of the accident. After that, the primary side flow reduced gradually to 0 with the decrease of the secondary side flow. Because of the trend of flow, the temperature of the tube wall decreased rapidly and then increased slowly. Therefore, the results of various accident conditions in this investigation can contribute to the thermal fatigue analysis of IHX in the near future.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"3 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122466858","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Shuo Ouyang, Z. Xiong, Wei Zhao, Ruiqi Kang, Zhen Li
In swirl-vane separators, the liquid phase is separated from the rotating gas flow under the action of centrifugal force. The droplets are carried by the rotating gas flow to the wall of the separator. In this paper, the phenomenon of a single droplet hitting on a stationary droplet on the wall in the rotating flow field is recorded by using a high-speed camera. Different types of droplet collisions appear as the inlet airflow velocity increases from 4 m/s to 4.8 m/s. Results show that the binary droplet impacts in the rotating flow field occur in asymmetric outcomes such as coalescence, finger spreading, finger breaking and splashing with the increase of the Weber number. The spiral characteristic of the rotating flow field leads to the asymmetry of the droplet collision. The bag breaking occurs in the rotating flow field. The number of droplets of bag breaking and breaking time are increased with Weber number increasing. This study provides basic characteristics for the impact of binary droplets in the rotating flow field and bag breaking, as well as improves the understanding of the separation efficiency mechanism of the gas-liquid separator.
{"title":"Experimental Study of Droplets Collision and Bag Breaking in Rotating Gas Flow Field","authors":"Shuo Ouyang, Z. Xiong, Wei Zhao, Ruiqi Kang, Zhen Li","doi":"10.1115/icone29-92947","DOIUrl":"https://doi.org/10.1115/icone29-92947","url":null,"abstract":"\u0000 In swirl-vane separators, the liquid phase is separated from the rotating gas flow under the action of centrifugal force. The droplets are carried by the rotating gas flow to the wall of the separator. In this paper, the phenomenon of a single droplet hitting on a stationary droplet on the wall in the rotating flow field is recorded by using a high-speed camera. Different types of droplet collisions appear as the inlet airflow velocity increases from 4 m/s to 4.8 m/s. Results show that the binary droplet impacts in the rotating flow field occur in asymmetric outcomes such as coalescence, finger spreading, finger breaking and splashing with the increase of the Weber number. The spiral characteristic of the rotating flow field leads to the asymmetry of the droplet collision. The bag breaking occurs in the rotating flow field. The number of droplets of bag breaking and breaking time are increased with Weber number increasing. This study provides basic characteristics for the impact of binary droplets in the rotating flow field and bag breaking, as well as improves the understanding of the separation efficiency mechanism of the gas-liquid separator.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"172 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124190426","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Likai Fei, Bin Gao, Pucheng Fan, Haowei Yuan, Husheng Wang, Fuming Yang, Lianyue Du, Lin Zheng
The coverage of cooling water film outside the containment shell is one of the most important boundary conditions for Passive Containment Cooling System (PCS) of AP/CAP reactor. The reduced coverage of the water film reduces the heat removal capacity of the containment vessel, which may result in the temperature and pressure within the containment can not be kept at a safe level. In this paper, the effect of cooling water flow rate and water film coverage on the heat removal capacity of PCS was studied experimentally under the loss-of-coolant accident (LOCA). Based on the CAP1400 passive containment water distribution test facility, the cooling water boundary conditions were set according to the combination of different cooling water flow rate and water film coverage rate, and the mass energy was released corresponding to the typical design basis accident condition. The response of parameters within the containment obtained from the test was compared and analyzed with the design condition. The experimental results show that the water film coverage rate has a greater impact on the parameters response within the containment than that of the cooling water flow rate.
{"title":"Preliminary Investigations on the Effect of Cooling Water Boundary Conditions on PCS Performance","authors":"Likai Fei, Bin Gao, Pucheng Fan, Haowei Yuan, Husheng Wang, Fuming Yang, Lianyue Du, Lin Zheng","doi":"10.1115/icone29-93163","DOIUrl":"https://doi.org/10.1115/icone29-93163","url":null,"abstract":"\u0000 The coverage of cooling water film outside the containment shell is one of the most important boundary conditions for Passive Containment Cooling System (PCS) of AP/CAP reactor. The reduced coverage of the water film reduces the heat removal capacity of the containment vessel, which may result in the temperature and pressure within the containment can not be kept at a safe level. In this paper, the effect of cooling water flow rate and water film coverage on the heat removal capacity of PCS was studied experimentally under the loss-of-coolant accident (LOCA). Based on the CAP1400 passive containment water distribution test facility, the cooling water boundary conditions were set according to the combination of different cooling water flow rate and water film coverage rate, and the mass energy was released corresponding to the typical design basis accident condition. The response of parameters within the containment obtained from the test was compared and analyzed with the design condition. The experimental results show that the water film coverage rate has a greater impact on the parameters response within the containment than that of the cooling water flow rate.","PeriodicalId":325659,"journal":{"name":"Volume 7B: Thermal-Hydraulics and Safety Analysis","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130713602","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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