Fusion Engineering and Design最新文献_第3页

Specimen size effects on tensile properties of cold worked RAFM steel 试样尺寸对冷加工RAFM钢拉伸性能的影响

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-23 DOI: 10.1016/j.fusengdes.2025.115093

Pinghan Chen , Xiaochen Li , Chang Li , Mingjie Zheng , Wenyi Ding

引用次数: 0

In-situ measurement of tritium accumulation and decontamination of tungsten 钨的氚累积和去污的原位测量

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-23 DOI: 10.1016/j.fusengdes.2025.115041

Dominic Batzler, Max Aker, James Robert Braun, Robin Größle, Philipp Haag, Marco Röllig, Dylan Ray Roodt, Marie-Christine Schäfer, Marius Schaufelberger

{"title":"In-situ measurement of tritium accumulation and decontamination of tungsten","authors":"Dominic Batzler, Max Aker, James Robert Braun, Robin Größle, Philipp Haag, Marco Röllig, Dylan Ray Roodt, Marie-Christine Schäfer, Marius Schaufelberger","doi":"10.1016/j.fusengdes.2025.115041","DOIUrl":"10.1016/j.fusengdes.2025.115041","url":null,"abstract":"<div><div>Tritium accumulation on surfaces, also known as the memory effect, has a wide range of implications for operating and maintaining fusion reactors, astroparticle physics experiments using tritium, and tritium analytics. At Tritium Laboratory Karlsruhe (TLK), the Tritium Activity Chamber Experiment (TRACE) was designed and built to investigate the tritium memory effect of a variety of materials. With TRACE, it is possible to expose samples to high-purity tritium at ambient temperature and measure their retained near-surface activity in-situ via beta-induced X-ray spectrometry (BIXS). Within this work, the relative memory effect of two tungsten samples — one pre-contaminated — after a cumulative exposure to tritium of 2100mbar<span><math><mi>⋅</mi></math></span>h was determined. The time evolutions of their activity prove the repeatability of the experiment. Attempts were made to decontaminate one of the samples in-situ. During continuous evacuation, merely 20% of its near-surface activity could be desorbed at a bake-out temperature of 200 °C.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115041"},"PeriodicalIF":1.9,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143860117","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Demonstration of curved magnetically guided liquid metal target using liquid Gallium for fusion neutron sources 用液态镓作聚变中子源的弯曲磁制导液态金属靶的演示

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-22 DOI: 10.1016/j.fusengdes.2025.115108

Eiji Hoashi, Takafumi Okita

{"title":"Demonstration of curved magnetically guided liquid metal target using liquid Gallium for fusion neutron sources","authors":"Eiji Hoashi, Takafumi Okita","doi":"10.1016/j.fusengdes.2025.115108","DOIUrl":"10.1016/j.fusengdes.2025.115108","url":null,"abstract":"<div><div>A high-speed liquid lithium (Li) jet with a free surface is being developed as a beam target for Fusion Neutron Sources. Li flows vertically along a concave flow channel with a free surface exposed to ion beam and its internal pressure increases due to centrifugal force, creating a temperature margin up to the boiling point. We proposed a practical concept of magnetically guided liquid metal target (MGLT) with a curved shape for IFMIF, and our MGLT produces curved magnetic field in combination of a couple of radiation-proof resistive coils, yokes, ducts/nozzles, and high flux test module. For the demonstration of the curved MGLT, gallium (Ga) was used as working liquid metal alternative to Li, because Ga has low chemical reactivity and a low melting point. In this study, firstly, we optimized the shape and conditions of the MGLT system for the curved Ga jet through brief two-dimensional calculations of the magnetic field and the Ga flow line. Next, the experimental apparatus was constructed, and measurements of the magnetic field was conducted. Then, the Ga jet was observed using high speed video camera, and the deviation between the Ga flow line and the magnetic field line was evaluated from image analysis. The deviation in the experiment was larger than that in the calculation. This was attributed to the fact that the three dimensional effects, including the deformation of the cross-sectional shape of the Ga jet, cannot be simulated in this calculation. However, from the results, it was demonstrated that our MGLT system had the potential to curve the liquid metal jet. On the other hand, the deviation in the experiment could not be made as small as calculated, but it was possible to identify the challenges for practical application of the MGLT system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115108"},"PeriodicalIF":1.9,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854493","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Design and qualification of a ceramic insulating break for ITER In-Vessel Coils ITER容器内线圈陶瓷绝缘断口的设计与鉴定

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-22 DOI: 10.1016/j.fusengdes.2025.115112

Davide Macioce , Alexander Vostner , Cristina Jimenez Aguinaga , Xabier Gomez Mitxelena , Miguel Angel Lagos Gomez , Igor Rueda Salazar , Roberto San Martín Ruiz , Ignacio Aviles Santillana

引用次数: 0

RF modeling and design of feedthroughs for the ICH system of DTT 数字地面电视ICH系统的射频建模与馈线设计

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-22 DOI: 10.1016/j.fusengdes.2025.115101

S. Greco , S. Ceccuzzi , F. Mirizzi , G.L. Ravera

引用次数: 0

Temperature field calculation and cooling water design of the pyrobreaker in Quench protect system 失火保护系统中高温断路器的温度场计算及冷却水设计

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-22 DOI: 10.1016/j.fusengdes.2025.115109

Zhenhan Li , Hua Li , Jifei Ye , Qianglin Xu , Xiaohua Bao , Ge Gao

{"title":"Temperature field calculation and cooling water design of the pyrobreaker in Quench protect system","authors":"Zhenhan Li , Hua Li , Jifei Ye , Qianglin Xu , Xiaohua Bao , Ge Gao","doi":"10.1016/j.fusengdes.2025.115109","DOIUrl":"10.1016/j.fusengdes.2025.115109","url":null,"abstract":"<div><div>The pyrobreaker, which serves as a backup protection switch in the Quench Protection System (QPS), is critical to maintaining the safe operation of superconducting fusion devices. However, the thermal energy generated by sustained current flow rises dramatically with current levels, which could harm the pyrobreaker and increasing the risk of QPS failure. Therefore, a reliable cooling water system is essential for ensuring the long-term reliability and stability of both the pyrobreaker and the overall system. First, the paper presents the overall structure and operational principles of the pyrobreaker in the QPS and then provides a detailed description of the cooling water system design. Second, the temperature of the cooling water system is calculated and analyzed theoretically by a numerical simulation model. Three, a 100kA test system platform was built to verify the feasibility and effectiveness of the cooling water system design. The results show that the cooling system effectively meets the temperature control requirements under 100 kA working conditions. This paper provides considerable theoretical support and a practical reference for ensuring QPS reliability and long-term stability in superconducting fusion systems.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115109"},"PeriodicalIF":1.9,"publicationDate":"2025-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854495","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Neutron emission from water activation: Experiments and modeling under fusion-relevant conditions at the KATANA facility 水活化的中子发射：在KATANA设施核聚变相关条件下的实验和建模

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-21 DOI: 10.1016/j.fusengdes.2025.115052

Julijan Peric, Domen Kotnik, Luka Snoj, Vladimir Radulović

{"title":"Neutron emission from water activation: Experiments and modeling under fusion-relevant conditions at the KATANA facility","authors":"Julijan Peric, Domen Kotnik, Luka Snoj, Vladimir Radulović","doi":"10.1016/j.fusengdes.2025.115052","DOIUrl":"10.1016/j.fusengdes.2025.115052","url":null,"abstract":"<div><div>Jožef Stefan Institute’s water activation experiment, called KATANA, was developed to procure benchmark quality experiments on the water activation process. This paper presents the optimization process of the neutron detector holder to achieve the neutron flux measurement system with the highest detection efficiency. Water is activated by the nuclear reactions on oxygen isotopes. The active oxygen and nitrogen isotopes then decay, emitting gamma rays and neutrons with different energies. The reaction <sup>17</sup>O(n,p)<sup>17</sup>N is responsible for the emission of high-energy neutrons. In future fusion plants such as ITER, the neutron flux in the water cooling system will be high, with an estimated flux of approx <span><math><mrow><mi>Φ</mi><mo>≈</mo><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>13</mn></mrow></msup></mrow></math></span> n/cm<span><math><msup><mrow></mrow><mrow><mn>2</mn></mrow></msup></math></span>s. Therefore, adequate shielding must be considered. The design and implementation of neutron flux measurement system at the KATANA water activation facility represents a significant step towards a better understanding of water activation processes. Despite the challenges associated with water activation experiments, the first test measurements of neutron emission during the water activation process have yielded promising results. The following results will be presented: the measured half-life for the decay of <sup>17</sup>N, activity of <sup>17</sup>N as a function of reactor power and water flow rate. The initial results indicate the possibility of using such a facility for the measurements of the integral cross section for the <sup>17</sup>O(n,p)<sup>17</sup>N reaction.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115052"},"PeriodicalIF":1.9,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143851664","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on brazing technology of graphite/OFC/CuCrZr joints with CuSnTi fillers applying for carbon-based plasma-facing components 石墨/OFC/CuCrZr（含铜硒钛填料）接头的钎焊技术研究，适用于碳基等离子体面层组件

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-21 DOI: 10.1016/j.fusengdes.2025.115106

Xianke Yang , Lei Yin , Pengfei Zi , Le Han , Qianqian Lin , Chongfeng Zhong , Damao Yao

{"title":"Research on brazing technology of graphite/OFC/CuCrZr joints with CuSnTi fillers applying for carbon-based plasma-facing components","authors":"Xianke Yang , Lei Yin , Pengfei Zi , Le Han , Qianqian Lin , Chongfeng Zhong , Damao Yao","doi":"10.1016/j.fusengdes.2025.115106","DOIUrl":"10.1016/j.fusengdes.2025.115106","url":null,"abstract":"<div><div>Plasma-facing components (PFCs), which consist of plasma-facing materials, heat sink materials, and support materials, are designed to withstand plasma shock directly and heat load during tokamak device operation; therefore, the bonding of graphite (plasma-facing material) with CuCrZr (heat sink material) is a critical technology for manufacture of PFCs. In this paper, oxygen-free copper (OFC) and CuSnTi foil were employed as the stress-relieving layer and brazing filler respectively, and graphite/CuSnTi/OFC/CuSnTi/CuCrZr brazing joints were fabricated under various brazing process parameters. The distribution of reaction products and joint-formatting mechanism were analyzed by scanning electron microscope (SEM), energy disperse spectroscopy (EDS) and X-ray diffractometer (XRD), and optimal brazing process parameters were determined by microstructure and mechanical property test results. The brazing joints exhibited a shear strength of 24 MPa when brazed at 1213 K with holding time of 15 min, and the mock-up fabricated using the CuSnTi filler endured 7 MW m<sup>−2</sup> for 1000 thermal fatigue cycles of 15 s heating and 15 s cooling in high heat flux (HHF) tests, which verified the feasibility of its application under high thermal load conditions. The OFC layer within the joint can effectively relieve the thermal stress under high thermal load conditions. Moreover, the bonding of graphite, OFC and CuCrZr was realized in a one-step brazing process, thereby simplifying the manufacturing process while ensuring both mechanical properties and heat removal ability. This advanced brazing technology provides technological support for the fabrication of carbon-based PFCs in experimental tokamak devices.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115106"},"PeriodicalIF":1.9,"publicationDate":"2025-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143854494","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Coil energization tests in JT-60SA integrated commissioning JT-60SA综合调试线圈通电试验

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-19 DOI: 10.1016/j.fusengdes.2025.115091

Kunihito Yamauchi , Shoichi Hatakeyama , Jun Okano , Yoshikazu Ohmori , Tsunehisa Terakado , Katsuhiro Shimada , Giampaolo Frello , Luca Novello

{"title":"Coil energization tests in JT-60SA integrated commissioning","authors":"Kunihito Yamauchi , Shoichi Hatakeyama , Jun Okano , Yoshikazu Ohmori , Tsunehisa Terakado , Katsuhiro Shimada , Giampaolo Frello , Luca Novello","doi":"10.1016/j.fusengdes.2025.115091","DOIUrl":"10.1016/j.fusengdes.2025.115091","url":null,"abstract":"<div><div>In 2023, all the coil Power Supply (PS) components of JT-60SA were tested with the corresponding superconducting coils in the integrated commissioning. Initially, the individual coil energization test was carried out to confirm the performance of each coil PS component. Subsequently, the integrated coil energization test was performed step by step progressively increasing the number of superconductive coils in simultaneous operation. As a result, it was confirmed that, in the tested operation range of Operation-1 phase in 2023, set at the rated current of 25.7 kA for toroidal field coils and +/–5 kA for poloidal field coils considering the validated electrical insulating performance of the coils, all the PS components could be operated as expected. Following the successful completion of the integrated commissioning, the first plasma of JT-60SA was successfully achieved and then the plasma experiment phase started. In this paper, the highlighted results of coil energization tests in JT-60SA integrated commissioning and the achievements were reported.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115091"},"PeriodicalIF":1.9,"publicationDate":"2025-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143847753","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Vibration testing of mechanical resilience of bolometer sensors and sensor holders under ITER-relevant conditions 热辐射计传感器和传感器支架在iter相关条件下的机械弹性振动试验

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-18 DOI: 10.1016/j.fusengdes.2025.115042

H. Meister , L.C. Ingesson , N. Marques , A. Pataki , U. Walach

{"title":"Vibration testing of mechanical resilience of bolometer sensors and sensor holders under ITER-relevant conditions","authors":"H. Meister , L.C. Ingesson , N. Marques , A. Pataki , U. Walach","doi":"10.1016/j.fusengdes.2025.115042","DOIUrl":"10.1016/j.fusengdes.2025.115042","url":null,"abstract":"<div><div>The ITER bolometer diagnostic will provide the measurement of the total radiation emitted from the plasma, a part of the overall energy balance. Up to 550 sensor channels will be installed in ITER in 71 cameras of various sizes and types. The sensor holder is the component inside those cameras to provide attachment and signal connections to the sensor itself. A design of a sensor holder has been proposed previously based on ceramic front and back plates with wire bonded contacts to the sensor and welded signal cables. This concept can provide the reliable electrical connections required for ITER at temperatures up to 350  <!-->kHz) have been deduced based on load definitions from ITER describing the floor response spectra for typical seismic events as well as the ones expected during disruptions due to electro-magnetically induced forces in bolometer cameras and port structures within which they are mounted. A particular focus has been placed on testing whether it is beneficial to cover the bond wires with a ceramic paste to protect them against fatigue breaks due to vibrations. The tests demonstrated that the chosen sensor assembly is well capable of withstanding all applied loads without failures and thus demonstrating its structural integrity during the expected operations. Within the limited number of load cycles no need to apply the ceramic paste could be identified.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115042"},"PeriodicalIF":1.9,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143843260","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0