cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.57760/sciencedb.04165
title: Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR
title: Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR

description: The water cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese Fusion Engineering Testing Reactor (CFETR). The WCCB blanket design has been updated according to the latest core parameters of CFETR in 2018. The Primary Heat Transfer System (PHTS) of the WCCB blanket is required to remove heat and convert fusion energy under multiple operation modes of CFETR. It is challenging as the heat sources of the PHTS differ greatly with the fusion power ranging from 200 MW to 1.5 GW for multiple operation modes of CFETR. Therefore, the PHTS is designed taking 1.5 GW of fusion power as full power. Then lower fusion power modes can be satisfied with margin. Based on the WCCB blanket module structure, the PHTS is characterized by 2 independent systems, namely Cooling System (CS) 1 for the First Wall (FW), CS 2 for Breeding Zones (BZs). Both systems have two identical and symmetrical loops. Detailed design of the PHTS is performed, including system layout, pipe sizing, system components configuration (e.g., pump, steam generator, pressurizer) and operation schemes. The reliability of the PHTS design is verified by simulation using RELAP5/MOD3.4 under steady states of 200 MW, 500 MW, 1.0 GW and 1.5 GW of fusion power.
description: The water cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese Fusion Engineering Testing Reactor (CFETR). The WCCB blanket design has been updated according to the latest core parameters of CFETR in 2018. The Primary Heat Transfer System (PHTS) of the WCCB blanket is required to remove heat and convert fusion energy under multiple operation modes of CFETR. It is challenging as the heat sources of the PHTS differ greatly with the fusion power ranging from 200 MW to 1.5 GW for multiple operation modes of CFETR. Therefore, the PHTS is designed taking 1.5 GW of fusion power as full power. Then lower fusion power modes can be satisfied with margin. Based on the WCCB blanket module structure, the PHTS is characterized by 2 independent systems, namely Cooling System (CS) 1 for the First Wall (FW), CS 2 for Breeding Zones (BZs). Both systems have two identical and symmetrical loops. Detailed design of the PHTS is performed, including system layout, pipe sizing, system components configuration (e.g., pump, steam generator, pressurizer) and operation schemes. The reliability of the PHTS design is verified by simulation using RELAP5/MOD3.4 under steady states of 200 MW, 500 MW, 1.0 GW and 1.5 GW of fusion power.
DOI: 10.57760/sciencedb.04174
title: Alarm System for EAST Poloidal Field Power Supply
title: Alarm System for EAST Poloidal Field Power Supply

description:  The poloidal field (PF) power supply is an important subsystem of the EAST (ExperimentalAdvanced Superconducting Tokamak as the device status detection and protection are essential. The PFpower supply monitor system is based on the Experimental Physics and Industrial Control System andthe human machine interface is the Control System Studio (CSS). The alarm is a plugin of CSS, used tohelp operators take correct action at the correct time. This technical note creates the alarm system,including server, client, Java Message Service interface, and relational database and configures thealarm attribute and sets the action for all variables that may trigger the alarm. When the alarm istriggered, the system goes into fault mode, the alarm server sends mail or pops up a windowautomatically to prompt operators, and some actions may be executed automatically to protect thedevice. Then operators solve the fault according to the guidance and the system returns to normal,realizing device status monitoring and protection in real time. The EAST experiment shows the alarmsystem has better function and stable performance.
description:  The poloidal field (PF) power supply is an important subsystem of the EAST (ExperimentalAdvanced Superconducting Tokamak as the device status detection and protection are essential. The PFpower supply monitor system is based on the Experimental Physics and Industrial Control System andthe human machine interface is the Control System Studio (CSS). The alarm is a plugin of CSS, used tohelp operators take correct action at the correct time. This technical note creates the alarm system,including server, client, Java Message Service interface, and relational database and configures thealarm attribute and sets the action for all variables that may trigger the alarm. When the alarm istriggered, the system goes into fault mode, the alarm server sends mail or pops up a windowautomatically to prompt operators, and some actions may be executed automatically to protect thedevice. Then operators solve the fault according to the guidance and the system returns to normal,realizing device status monitoring and protection in real time. The EAST experiment shows the alarmsystem has better function and stable performance.
DOI: 10.57760/sciencedb.04164
title: Figure-Experimental study on heat load of plasma-facing components by the calorimetry system in the EAST tokamak
title: 图片-基于EAST 装置量热系统的 第一壁热负荷实验研究

description: Fig.1 Distribution of the water cooling modules in the EAST, which is produced by CAD.Fig.2 Heat load distribution estimated from the calorimetry system in discharges with an upper single null divetor configuration in the EAST tokamak. Data is from the calorimetry system in EAST.Fig.3 Waveforms of the total heating power, heat load in the upper divertor and its change rate. The results are derived from the measurement by the calorimetry system in EAST.Fig.4 Time evolution of the water temperature difference for upper and lower divertor, respectively. The corresponding characteristical time can be used as a measure of the cooling capabitlity of the water cooling system.
description: Fig.1 Distribution of the water cooling modules in the EAST, which is produced by CAD.Fig.2 Heat load distribution estimated from the calorimetry system in discharges with an upper single null divetor configuration in the EAST tokamak. Data is from the calorimetry system in EAST.Fig.3 Waveforms of the total heating power, heat load in the upper divertor and its change rate. The results are derived from the measurement by the calorimetry system in EAST.Fig.4 Time evolution of the water temperature difference for upper and lower divertor, respectively. The corresponding characteristical time can be used as a measure of the cooling capabitlity of the water cooling system.
DOI: 10.57760/sciencedb.04169
title: A DEM-CFD numerical model for the prediction of the effective thermal conductivity of pebble beds with contact conduction
title: A DEM-CFD numerical model for the prediction of the effective thermal conductivity of pebble beds with contact conduction

description: Pebble beds are main schemes for tritium breeding zones in the solid blanket for fusion reactors. The effective thermal conductivity of pebble beds (keff ) is an important thermal property used in the thermal hydraulic design of solid blankets. In this study, a 3D DEM-CFD one-way coupling method considering contact conduction is applied to analyze the influence of solid contact conduction and solid-fluid-solid conduction on the effective thermal conductivity of pebble beds. The current numerical model gives a keff consistent with experimental data in a wide range of solid-to-fluid conductivity ratio k k s f / from 1 to 10,000. It can be concluded that when the k k s f / is more than 20, contact conduction should be taken into account to make a good prediction for keff .
description: Pebble beds are main schemes for tritium breeding zones in the solid blanket for fusion reactors. The effective thermal conductivity of pebble beds (keff ) is an important thermal property used in the thermal hydraulic design of solid blankets. In this study, a 3D DEM-CFD one-way coupling method considering contact conduction is applied to analyze the influence of solid contact conduction and solid-fluid-solid conduction on the effective thermal conductivity of pebble beds. The current numerical model gives a keff consistent with experimental data in a wide range of solid-to-fluid conductivity ratio k k s f / from 1 to 10,000. It can be concluded that when the k k s f / is more than 20, contact conduction should be taken into account to make a good prediction for keff .
DOI: 10.25835/iuv28jg9
title: Data for the paper about the Citizens' Working Group in the project TRANSENS

description: Interview data for each category. Used software: MAXQDA
Paper in Ambio: A transdisciplinary approach to nuclear waste management: opening research with a Citizens’ Working Group
DOI: 10.57760/sciencedb.04173
title: Experimental measurements for the effective thermal conductivity of pebble beds with uncertainty analysis
title: Experimental measurements for the effective thermal conductivity of pebble beds with uncertainty analysis

description: The lithium ceramic pebble bed is a vital functional component of solid blankets in fusion reactors to realize tritium breeding. The effective thermal conductivity of the lithium ceramic pebble bed is a key thermal property which has a significant impact on the design and analysis of the fusion blanket. An experimental platform including a test section and a helium loop was designed to measure the effective thermal conductivity. The test section was based on the principle of the hot wire method and the helium loop was designed to satisfy different experimental conditions. For the Li2TiO3 and the Li4SiO4 pebble bed, experiments were performed in the presence of stagnant helium at atmospheric pressure. An increase of the effective thermal conductivity was detected in the temperature range RT-400 °C and the results were compared with numerical results. For the binary glass pebble beds with different diameter ratios, experiments were performed at room temperature in the presence of stagnant helium and air. The effective thermal conductivity was found strongly dependent on the packing factor.
description: The lithium ceramic pebble bed is a vital functional component of solid blankets in fusion reactors to realize tritium breeding. The effective thermal conductivity of the lithium ceramic pebble bed is a key thermal property which has a significant impact on the design and analysis of the fusion blanket. An experimental platform including a test section and a helium loop was designed to measure the effective thermal conductivity. The test section was based on the principle of the hot wire method and the helium loop was designed to satisfy different experimental conditions. For the Li2TiO3 and the Li4SiO4 pebble bed, experiments were performed in the presence of stagnant helium at atmospheric pressure. An increase of the effective thermal conductivity was detected in the temperature range RT-400 °C and the results were compared with numerical results. For the binary glass pebble beds with different diameter ratios, experiments were performed at room temperature in the presence of stagnant helium and air. The effective thermal conductivity was found strongly dependent on the packing factor.
DOI: 10.57760/sciencedb.04176
title: Study on the effective thermal conductivity of different packing schemes of tritium breeder pebble beds
title: Study on the effective thermal conductivity of different packing schemes of tritium breeder pebble beds

description: A heat transfer analysis model of pebble beds is established based on discrete element method and computational fluid dynamics coupling method (DEM-CFD). The validation of DEM model, grid sensitivity analysis and heat transfer model are carried out. Based on the above model, the effective thermal conductivity of Li2TiO3 pebble beds with particle size distribution, unitary Li2TiO3 pebble beds and binary Li2TiO3 pebble beds is further simulated and calculated. The influence of particle size distribution, different particle sizes and mixing on the effective thermal conductivity of Li2TiO3 pebble beds is studied. The results show that for the Li2TiO3 pebble beds with similar packing factor, the effective thermal conductivity of Li2TiO3 pebble beds with particle size distribution is similar with unitary Li2TiO3 pebble beds with equivalent particle size. In the case of negligible radiation heat transfer, the effect of particle size on the effective thermal conductivity of unitary pebble bed is negligible. Compared with unitary Li2TiO3 pebble bed, the binary Li2TiO3 pebble bed has higher packing factor and effective thermal conductivity.
description: A heat transfer analysis model of pebble beds is established based on discrete element method and computational fluid dynamics coupling method (DEM-CFD). The validation of DEM model, grid sensitivity analysis and heat transfer model are carried out. Based on the above model, the effective thermal conductivity of Li2TiO3 pebble beds with particle size distribution, unitary Li2TiO3 pebble beds and binary Li2TiO3 pebble beds is further simulated and calculated. The influence of particle size distribution, different particle sizes and mixing on the effective thermal conductivity of Li2TiO3 pebble beds is studied. The results show that for the Li2TiO3 pebble beds with similar packing factor, the effective thermal conductivity of Li2TiO3 pebble beds with particle size distribution is similar with unitary Li2TiO3 pebble beds with equivalent particle size. In the case of negligible radiation heat transfer, the effect of particle size on the effective thermal conductivity of unitary pebble bed is negligible. Compared with unitary Li2TiO3 pebble bed, the binary Li2TiO3 pebble bed has higher packing factor and effective thermal conductivity.
DOI: 10.57760/sciencedb.04177
title: Research on data strorage and reading method of EAST poloidal field power supply
title: EAST极向场电源的数据存储及读取方法

description: The plasma discharge duration of EAST (Experimental Advanced Super—conducting Tokamak) is designed to be 1000s, the time has exceeded 100s at present. As the core subsystem, poloidal filed power supply(PF) has nearly 200 signals to be stored. For every discharge, the amount of data is very large, the ordinary database can’t meet the requirement of long pulse data storage. This paper uses HDF5 (Hierarchical Data Format) to store the long pulse data, HDF5 is a file format that can store different types of images and data. Using C interface of HDF5 to design a dataset with compound datatype, to realize real-time writing and reading, the primary discharge time is segmented and the data is wrote and read as chunk. Visualization tool Hdfview is used to view the dataset, and Qt is used to read HDF5 file and display waveform. It proves the correctness of compound datatype and chunk dataset, and the feasibility of writing and reading as chunk. Simple time test proves that writing and reading as chunk are efficient.
description: The plasma discharge duration of EAST (Experimental Advanced Super—conducting Tokamak) is designed to be 1000s, the time has exceeded 100s at present. As the core subsystem, poloidal filed power supply(PF) has nearly 200 signals to be stored. For every discharge, the amount of data is very large, the ordinary database can’t meet the requirement of long pulse data storage. This paper uses HDF5 (Hierarchical Data Format) to store the long pulse data, HDF5 is a file format that can store different types of images and data. Using C interface of HDF5 to design a dataset with compound datatype, to realize real-time writing and reading, the primary discharge time is segmented and the data is wrote and read as chunk. Visualization tool Hdfview is used to view the dataset, and Qt is used to read HDF5 file and display waveform. It proves the correctness of compound datatype and chunk dataset, and the feasibility of writing and reading as chunk. Simple time test proves that writing and reading as chunk are efficient.
DOI: 10.57760/sciencedb.04183
title: Tritium transport analysis for water cooled ceramic breeder blanket
title: Tritium transport analysis for water cooled ceramic breeder blanket

description: Based on twater cooled ceramic breeder (WCCB) blanket modules surrounding the plasma, a tritium transport model has been developed. Tritium transport analysis has been carried out for each blanket module with different breeding zones, purge gas loop, coolant loop and steam generator.[…]
description: Based on twater cooled ceramic breeder (WCCB) blanket modules surrounding the plasma, a tritium transport model has been developed. Tritium transport analysis has been carried out for each blanket module with different breeding zones, purge gas loop, coolant loop and steam generator.[…]
DOI: 10.57760/sciencedb.04185
title: Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR
title: Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR

description: A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as a candidate blanket concept for the Chinese Fusion Engineering Test Reactor (CFETR). Based on a poloidal-radial slice model, thermal hydraulic analysis is performed for this blanket to validate the feasibility of design goals. Results show that the present design can achieve the outlet temperature in the range of 600–700 ◦C, with all the material temperatures safely below the upper limits. A series of sensitivity analyses are also carried out. It indicates that the thermal conductivity (TC) of SiC would have a signifificant inflfluence on the temperature fifield, streamlines and pressure drop; that is, lower TC of SiC can maintain the temperature of PbLi at a high level, and induce an increased number of vortices in the liquid PbLi flflow as well as a larger pressure drop. On this basis, the joint effects of the TC of SiC and inlet velocity on the performance of blanket thermal hydraulics are analyzed, then the so-called “attainable region” is proposed. Finally, optimization design studies are carried out by decreasing the width of the front channel. Comparison results show that the present design is the most reasonable.
description: A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as a candidate blanket concept for the Chinese Fusion Engineering Test Reactor (CFETR). Based on a poloidal-radial slice model, thermal hydraulic analysis is performed for this blanket to validate the feasibility of design goals. Results show that the present design can achieve the outlet temperature in the range of 600–700 ◦C, with all the material temperatures safely below the upper limits. A series of sensitivity analyses are also carried out. It indicates that the thermal conductivity (TC) of SiC would have a signifificant inflfluence on the temperature fifield, streamlines and pressure drop; that is, lower TC of SiC can maintain the temperature of PbLi at a high level, and induce an increased number of vortices in the liquid PbLi flflow as well as a larger pressure drop. On this basis, the joint effects of the TC of SiC and inlet velocity on the performance of blanket thermal hydraulics are analyzed, then the so-called “attainable region” is proposed. Finally, optimization design studies are carried out by decreasing the width of the front channel. Comparison results show that the present design is the most reasonable.
DOI: 10.57760/sciencedb.04187
title: Verification of the on-the-fly global variance reduction technique on Monte Carlo global coupled neutron photon shielding calculations
title: Verification of the on-the-fly global variance reduction technique on Monte Carlo global coupled neutron photon shielding calculations

description: Using Monte Carlo (MC) transport codes for fusion device shielding calculation is very challenging due to the complexity and heavy shielding of a fusion reactor. An effective on-the-fly (OTF) global variance reduction method was developed and verified before. The OTF method is designed to speed up the general-purpose MC global total neutron distribution by generating and updating the global weight window mesh (WWM) internally in the MC code. In this work, this method has been further extended for accelerating global coupled neutron photon transportation calculation. The goal of this paper is to evaluate the applicability of OTF to enhance the efficiency of the global total neutron and photon fluxes calculation of challenging problems. For verification purposes, the ITER C-model and IFMIF-DONES have been chosen as test cases. The OTF has achieved a substantial reduction in computational time comparing with analogue method.
description: Using Monte Carlo (MC) transport codes for fusion device shielding calculation is very challenging due to the complexity and heavy shielding of a fusion reactor. An effective on-the-fly (OTF) global variance reduction method was developed and verified before. The OTF method is designed to speed up the general-purpose MC global total neutron distribution by generating and updating the global weight window mesh (WWM) internally in the MC code. In this work, this method has been further extended for accelerating global coupled neutron photon transportation calculation. The goal of this paper is to evaluate the applicability of OTF to enhance the efficiency of the global total neutron and photon fluxes calculation of challenging problems. For verification purposes, the ITER C-model and IFMIF-DONES have been chosen as test cases. The OTF has achieved a substantial reduction in computational time comparing with analogue method.
DOI: 10.57760/sciencedb.j00133.00167
title: Statistical analysis and mapping of experimental dates
title: 实验结果统计与分析、制图

description: Statistical analysis and mapping of experimental dates
description: Statistical analysis and mapping of experimental dates