cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.57760/sciencedb.04239
title: An Optimized Method for Bonner Sphere Spectrometer Design and Validation by Measuring 252 Cf Spectra
title: An Optimized Method for Bonner Sphere Spectrometer Design and Validation by Measuring 252 Cf Spectra

description: A methodology for designing a Bonner sphere spectrometer was proposed based on the singular value decomposition (SVD) and information entropy theory. First, features of Bonner spheres were classified based on SVD, and then, the rationality of the selected spheres was analyzed. Second, the information entropy is used as the quantitative evaluation standard; combined with the unfolding method, the contribution of each Bonner sphere on the information entropy of the unfolded spectra was quantitatively analyzed. The spheres that have high influence on the information entropy of solution spectra can be identified, and then, the information entropy variation of the solution spectra can be suppressed by reducing the count fluctuation of these spheres. According to the proposed method, an optimized spectrometer was developed and applied to measuring 252Cf spectra.
description: A methodology for designing a Bonner sphere spectrometer was proposed based on the singular value decomposition (SVD) and information entropy theory. First, features of Bonner spheres were classified based on SVD, and then, the rationality of the selected spheres was analyzed. Second, the information entropy is used as the quantitative evaluation standard; combined with the unfolding method, the contribution of each Bonner sphere on the information entropy of the unfolded spectra was quantitatively analyzed. The spheres that have high influence on the information entropy of solution spectra can be identified, and then, the information entropy variation of the solution spectra can be suppressed by reducing the count fluctuation of these spheres. According to the proposed method, an optimized spectrometer was developed and applied to measuring 252Cf spectra.
DOI: 10.57760/sciencedb.04243
title: Thermo-mechanical analysis on the full module of water cooled ceramic breeder blanket for CFETR
title: Thermo-mechanical analysis on the full module of water cooled ceramic breeder blanket for CFETR

description: As one of blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR), the concept design of the Water Cooled Ceramic Breeder (WCCB) blanket is being carried out and the analyses of the neutronics and thermal hydraulics have been fifinished. To investigate the thermo-mechanical behavior of the current WCCB blanket design version under normal operation and accidental operation scenarios (e.g. in-box loss of coolant accident (LOCA)), the fifinite element thermo-mechanical analyses of a full blanket module were performed by using ANSYS Multiphysics code. The stress results were assessed referring to ITER SDC-IC code. Under normal operation scenario, the blanket shows a satisfying mechanical behavior withstanding 15.5 MPa coolant pressure on its cooling channel walls and thermal deformations. However, under in-box LOCA scenario, the blanket fails to withstand 15.5 MPa coolant pressure on its internal walls at normal operation thermal level. In this situation, the relief valve is proposed as a mitigation measure to release coolant pressure to maintain the structural integrity of blanket box under in-box LOCA accident.
description: As one of blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR), the concept design of the Water Cooled Ceramic Breeder (WCCB) blanket is being carried out and the analyses of the neutronics and thermal hydraulics have been fifinished. To investigate the thermo-mechanical behavior of the current WCCB blanket design version under normal operation and accidental operation scenarios (e.g. in-box loss of coolant accident (LOCA)), the fifinite element thermo-mechanical analyses of a full blanket module were performed by using ANSYS Multiphysics code. The stress results were assessed referring to ITER SDC-IC code. Under normal operation scenario, the blanket shows a satisfying mechanical behavior withstanding 15.5 MPa coolant pressure on its cooling channel walls and thermal deformations. However, under in-box LOCA scenario, the blanket fails to withstand 15.5 MPa coolant pressure on its internal walls at normal operation thermal level. In this situation, the relief valve is proposed as a mitigation measure to release coolant pressure to maintain the structural integrity of blanket box under in-box LOCA accident.
DOI: 10.57760/sciencedb.04247
title: Thermo-mechanical assessment of the optimized CFETR water cooled ceramic breeder blanket
title: Thermo-mechanical assessment of the optimized CFETR water cooled ceramic breeder blanket

description: The Water Cooled Ceramic Breeder (WCCB) blanket is one of the candidates for Chinese Fusion Engineering Test Reactor (CFETR). Within the framework of the engineering design of CFETR, an updated design of WCCB blanket was proposed corresponding to the latest core parameters (major radius=7.2 m, minus radius=2.2 m). Thermalhydraulic analyses preliminarily showed the feasibility of the previous blanket design. However, the flow distribution of the blanket was unsatisfactory. Thus, optimization of cooling systems of the blanket was performed accordingly. The optimized blanket design as well as the hydraulic analysis results are presented. Then, in order to investigate the thermal-hydraulic and thermo-mechanical behaviors of the optimized WCCB blanket under normal and accidental operation scenarios, thermo-mechanical analyses were performed following a computational approach based on the Finite Element Method (FEM), using the ANSYS commercial FEM code. The obtained results were assessed in order to verify the compliance with the blanket design criteria ITER SDC-IC code. Structural feasibility of the optimized blanket design was verified. 
description: The Water Cooled Ceramic Breeder (WCCB) blanket is one of the candidates for Chinese Fusion Engineering Test Reactor (CFETR). Within the framework of the engineering design of CFETR, an updated design of WCCB blanket was proposed corresponding to the latest core parameters (major radius=7.2 m, minus radius=2.2 m). Thermalhydraulic analyses preliminarily showed the feasibility of the previous blanket design. However, the flow distribution of the blanket was unsatisfactory. Thus, optimization of cooling systems of the blanket was performed accordingly. The optimized blanket design as well as the hydraulic analysis results are presented. Then, in order to investigate the thermal-hydraulic and thermo-mechanical behaviors of the optimized WCCB blanket under normal and accidental operation scenarios, thermo-mechanical analyses were performed following a computational approach based on the Finite Element Method (FEM), using the ANSYS commercial FEM code. The obtained results were assessed in order to verify the compliance with the blanket design criteria ITER SDC-IC code. Structural feasibility of the optimized blanket design was verified.
DOI: 10.57760/sciencedb.04251
title: Original data for "RNF12 catalyzes BRF1 ubiquitination and regulates RNA polymerase III-dependent transcription".
title: Original data for "RNF12 catalyzes BRF1 ubiquitination and regulates RNA polymerase III-dependent transcription".

description: These original data were obtained by performing Real-time RT-PCR, Immunofluorescence, Western blotting, Co-immunoprecipitation, CHIP assay, In vivo and in vitro ubiquitination experiments.
description: These original data were obtained by performing Real-time RT-PCR, Immunofluorescence, Western blotting, Co-immunoprecipitation, CHIP assay, In vivo and in vitro ubiquitination experiments.
DOI: 10.57760/sciencedb.04253
title: Conceptual design of a blanket module integrated with divertor for CFETR
title: Conceptual design of a blanket module integrated with divertor for CFETR

description: Achieving tritium self-sufficiency (tritium breeding ratio (TBR)≥1.1) is one of the most important missions of the Chinese Fusion Engineering Test Reactor (CFETR). The neutronics analysis shows that the global TBR of the CFETR water-cooled ceramic breeder (WCCB) blanket is 1.147 when the plasma is surrounded by blankets (without any windows), which can meet the tritium self-sufficiency requirement. In the engineering design phase, however, a number of blanket modules are replaced by auxiliary systems. It would lead to decline of TBR and failure of tritium self-sufficiency. Therefore, a new blanket module concept extended to the divertor region and integrated with the divertor is proposed to increase TBR. The blanket module is located at the back of the divertor target plates. This paper presents the design of the proposed blanket module. The feasibility of the blanket design is evaluated considering neutronics, thermal and mechanical performances.  
description: Achieving tritium self-sufficiency (tritium breeding ratio (TBR)≥1.1) is one of the most important missions of the Chinese Fusion Engineering Test Reactor (CFETR). The neutronics analysis shows that the global TBR of the CFETR water-cooled ceramic breeder (WCCB) blanket is 1.147 when the plasma is surrounded by blankets (without any windows), which can meet the tritium self-sufficiency requirement. In the engineering design phase, however, a number of blanket modules are replaced by auxiliary systems. It would lead to decline of TBR and failure of tritium self-sufficiency. Therefore, a new blanket module concept extended to the divertor region and integrated with the divertor is proposed to increase TBR. The blanket module is located at the back of the divertor target plates. This paper presents the design of the proposed blanket module. The feasibility of the blanket design is evaluated considering neutronics, thermal and mechanical performances.
DOI: 10.57760/sciencedb.04257
title: ITER PF6 double pancakes stacking
title: ITER PF6双饼线圈堆叠组装关键技术

description: 论文描述了ITER PF6线圈的多层双饼结构堆叠组装过程的关键技术难题与解决方案，以及最终装配成果。
description: 论文描述了ITER PF6线圈的多层双饼结构堆叠组装过程的关键技术难题与解决方案，以及最终装配成果。
DOI: 10.57760/sciencedb.04260
title: Evaluation of point-core approximation effect on the positron energy levels in diamond structure solids
title: Evaluation of point-core approximation effect on the positron energy levels in diamond structure solids

description: 这篇文章的主要内容是评估所谓的“点心”近似对金刚石固体结构中正电子能级、正电子寿命等参数的影响，其核心是利用赝势平面波方法计算正电子相关波函数等。文章给出了主要的数据图，但没有给出计算这些参数所涉及的重要过程数据，如金刚石结构的中构成原子核心电子密度、价电子密度等。这个数据集即给出文章中未给出的重要的过程数据。
description: 这篇文章的主要内容是评估所谓的“点心”近似对金刚石固体结构中正电子能级、正电子寿命等参数的影响，其核心是利用赝势平面波方法计算正电子相关波函数等。文章给出了主要的数据图，但没有给出计算这些参数所涉及的重要过程数据，如金刚石结构的中构成原子核心电子密度、价电子密度等。这个数据集即给出文章中未给出的重要的过程数据。
DOI: 10.57760/sciencedb.04259
title: Numerical simulation of airflow characteristics during the loss of vacuum accident of CFETR
title: Numerical simulation of airflow characteristics during the loss of vacuum accident of CFETR

description: During a loss of vacuum accident (LOVA) of China Fusion Engineering Test Reactor (CFETR), the high velocity airflow will result in the migration, re-suspension even explosion of theradioactive dust deposited in the vacuum vessel (VV) during plasma burning. In addition, large amounts of hydrogen may be produced from the exothermic reaction between tungsten and water/steam. In order to minimize the risk of explosion and the leakage of radioactivity, the airflow characteristics must be well studied at the first step. In this paper,a break due to a failed component is assumed to take place at the equatorial port. The numerical simulation has been performed by using ANSYS CFX code with a simplified VV model of CFETR. The airflow field during LOVA has been studied in detail under different initial pressure and first wall (FW) temperature. The results show that the FW temperature significantly affects the pressurization process. Besides, the friction velocity is also greatly affected by the FW temperature and initial pressure. From the 3D airflow distribution, the velocity near the lower part of torus can reach up to 87.4 m/s. This study provides indispensable basis for the research about dust resuspension, migration, dust/hydrogen explosion and the radiological safety of CFETR.
description: During a loss of vacuum accident (LOVA) of China Fusion Engineering Test Reactor (CFETR), the high velocity airflow will result in the migration, re-suspension even explosion of theradioactive dust deposited in the vacuum vessel (VV) during plasma burning. In addition, large amounts of hydrogen may be produced from the exothermic reaction between tungsten and water/steam. In order to minimize the risk of explosion and the leakage of radioactivity, the airflow characteristics must be well studied at the first step. In this paper,a break due to a failed component is assumed to take place at the equatorial port. The numerical simulation has been performed by using ANSYS CFX code with a simplified VV model of CFETR. The airflow field during LOVA has been studied in detail under different initial pressure and first wall (FW) temperature. The results show that the FW temperature significantly affects the pressurization process. Besides, the friction velocity is also greatly affected by the FW temperature and initial pressure. From the 3D airflow distribution, the velocity near the lower part of torus can reach up to 87.4 m/s. This study provides indispensable basis for the research about dust resuspension, migration, dust/hydrogen explosion and the radiological safety of CFETR.
DOI: 10.57760/sciencedb.04262
title: Neutronic analyses of Upper port ECRH antenna system for CFETR
title: Neutronic analyses of Upper port ECRH antenna system for CFETR

description: Electron Cyclotron Resonance Heating (ECRH) is one of the auxiliary heating systems designed for CFETR. The antenna of ECRH system is planned to be plugged into CFETR through 3 upper ports and 2 blanket modules of each port will be penetrated for the transmission of wave. In this study, three dimensional neutronic analysis has been performed to evaluate the shielding effect and conduct the optimization of ECRH antenna design. The simulation has been done on the integration of ECRH antenna system with 22.5-degree CFETR model. The particle transport has been done by MCNP with the support of FENDL-2.1 nuclear data library. An accurate neutron flux distribution has been obtained by employing the ‘on-the-fly’ global variance reduction technique. The neutron damage of TFC, VV and port was analysed to assess the shielding performance of ECRH antenna system. Initial results demonstrated that the fast neutron fluence and nuclear heating density of TFC and helium production rate of VV port were beyond the design limit. By adding shielding blocks, these parameters didn’t exceed the limits. The irradiation damage on antenna components were calculated for estimating its life after neutron irradiation and providing the support of cooling system design. The TBR decreased due to the blanket opening from original 1.149 to 1.137 in the whole reactor.
description: Electron Cyclotron Resonance Heating (ECRH) is one of the auxiliary heating systems designed for CFETR. The antenna of ECRH system is planned to be plugged into CFETR through 3 upper ports and 2 blanket modules of each port will be penetrated for the transmission of wave. In this study, three dimensional neutronic analysis has been performed to evaluate the shielding effect and conduct the optimization of ECRH antenna design. The simulation has been done on the integration of ECRH antenna system with 22.5-degree CFETR model. The particle transport has been done by MCNP with the support of FENDL-2.1 nuclear data library. An accurate neutron flux distribution has been obtained by employing the ‘on-the-fly’ global variance reduction technique. The neutron damage of TFC, VV and port was analysed to assess the shielding performance of ECRH antenna system. Initial results demonstrated that the fast neutron fluence and nuclear heating density of TFC and helium production rate of VV port were beyond the design limit. By adding shielding blocks, these parameters didn’t exceed the limits. The irradiation damage on antenna components were calculated for estimating its life after neutron irradiation and providing the support of cooling system design. The TBR decreased due to the blanket opening from original 1.149 to 1.137 in the whole reactor.
DOI: 10.57760/sciencedb.04265
title: A DEM-based heat transfer model for the evaluation of effective thermal conductivity of packed beds filled with stagnant fluid: Thermal contact theory and numerical simulation
title: A DEM-based heat transfer model for the evaluation of effective thermal conductivity of packed beds filled with stagnant fluid: Thermal contact theory and numerical simulation

description: The Effective thermal conductivity (keff) is one of the key thermal properties for packed beds in the presence of a stagnant fluid. In this study, a thermal discrete element model (DEM) based on the original Cheng-Yu-Zulli analytical model for mono-sized packed beds has been improved and implemented especially for mixed beds of different particle sizes or materials. In order to perform the DEM simulation for packed beds, a thermal contact theory considering three heat transfer mechanisms (solid contact conduction, solid-fluid-solid conduction and radiation) was derived and applied in the network of Voronoi cells obtained by radical Voronoi tessellation of the relevant beds. The numerical model was validated through a comparison with experimental results already reported in literature and a good prediction for the effective thermal conductivity was obtained for both mono-sized and multi sized packed beds in a wide range of solid-to-fluid conductivity ratio. The model also showed a good performance to study the heat flow distribution as well as the coupled thermo-mechanical behavior of packed beds.
description: The Effective thermal conductivity (keff) is one of the key thermal properties for packed beds in the presence of a stagnant fluid. In this study, a thermal discrete element model (DEM) based on the original Cheng-Yu-Zulli analytical model for mono-sized packed beds has been improved and implemented especially for mixed beds of different particle sizes or materials. In order to perform the DEM simulation for packed beds, a thermal contact theory considering three heat transfer mechanisms (solid contact conduction, solid-fluid-solid conduction and radiation) was derived and applied in the network of Voronoi cells obtained by radical Voronoi tessellation of the relevant beds. The numerical model was validated through a comparison with experimental results already reported in literature and a good prediction for the effective thermal conductivity was obtained for both mono-sized and multi sized packed beds in a wide range of solid-to-fluid conductivity ratio. The model also showed a good performance to study the heat flow distribution as well as the coupled thermo-mechanical behavior of packed beds.
DOI: 10.57760/sciencedb.04267
title: Thermo-mechanical analysis on the full module of water cooled ceramic breeder blanket for CFETR
title: Thermo-mechanical analysis on the full module of water cooled ceramic breeder blanket for CFETR

description: As one of blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR), the concept design of the Water Cooled Ceramic Breeder (WCCB) blanket is being carried out and the analyses of the neutronics and thermal hydraulics have been finished. To investigate the thermo-mechanical behavior of the current WCCB blanket design version under normal operation and accidental operation scenarios (e.g. in-box loss of coolant accident (LOCA)), the finite element thermo-mechanical analyses of a full blanket module were performed by using ANSYS Multiphysics code. The stress results were assessed referring to ITER SDC-IC code. Under normal operation scenario, the blanket shows a satisfying mechanical behavior withstanding 15.5 MPa coolant pressure on its cooling channel walls and thermal deformations. However, under in-box LOCA scenario, the blanket fails to withstand 15.5 MPa coolant pressure on its internal walls at normal operation thermal level. In this situation, the relief valve is proposed as a mitigation measure to release coolant pressure to maintain the structural integrity of blanket box under in-box LOCA accident.
description: As one of blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR), the concept design of the Water Cooled Ceramic Breeder (WCCB) blanket is being carried out and the analyses of the neutronics and thermal hydraulics have been finished. To investigate the thermo-mechanical behavior of the current WCCB blanket design version under normal operation and accidental operation scenarios (e.g. in-box loss of coolant accident (LOCA)), the finite element thermo-mechanical analyses of a full blanket module were performed by using ANSYS Multiphysics code. The stress results were assessed referring to ITER SDC-IC code. Under normal operation scenario, the blanket shows a satisfying mechanical behavior withstanding 15.5 MPa coolant pressure on its cooling channel walls and thermal deformations. However, under in-box LOCA scenario, the blanket fails to withstand 15.5 MPa coolant pressure on its internal walls at normal operation thermal level. In this situation, the relief valve is proposed as a mitigation measure to release coolant pressure to maintain the structural integrity of blanket box under in-box LOCA accident.
DOI: 10.57760/sciencedb.04268
title: Study of Power Conversion System for Chinese Fusion Engineering Testing Reactor
title: 中国聚变工程实验堆的热电转换循环研究

description: This data set is the original supporting data of the article Study of Power Conversion System for Chinese Fusion Engineering Testing Reactor. In this document, there are 7 sub tables corresponding to the calculation data under different working conditions. 
description: This data set is the original supporting data of the article Study of Power Conversion System for Chinese Fusion Engineering Testing Reactor. In this document, there are 7 sub tables corresponding to the calculation data under different working conditions.