Journal of Fusion Energy最新文献_第3页

Gamma Ray Diagnostics in Large Helical Device 大型螺旋装置中的伽马射线诊断

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-17 DOI: 10.1007/s10894-026-00557-z

Kunihiro Ogawa, Siriyaporn Sangaroon, Hideaki Matsuura, Makoto I. Kobayashi, S. Yoshihashi, Mitsutaka Isobe

引用次数: 0

ICSI Contributions Regarding Barriers Against Hydrogen Isotope Permeation Through Stainless Steel and EUROFER97 in DEMO Applications 在演示应用中，ICSI对氢同位素通过不锈钢和EUROFER97渗透的屏障的贡献

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-17 DOI: 10.1007/s10894-026-00560-4

Alina Niculescu, Maria Craciun, George Ana, Gheorghe Bulubasa

{"title":"ICSI Contributions Regarding Barriers Against Hydrogen Isotope Permeation Through Stainless Steel and EUROFER97 in DEMO Applications","authors":"Alina Niculescu, Maria Craciun, George Ana, Gheorghe Bulubasa","doi":"10.1007/s10894-026-00560-4","DOIUrl":"10.1007/s10894-026-00560-4","url":null,"abstract":"<div>\u0000 \u0000 One of the essential requirements for the future fusion power plants is the tritium self-sufficiency. Still, during transport from the breeding blanket towards the extraction system, a fraction of tritium permeates through the piping and containment walls, and it might escape into the outer environment. To reduce the amount of permeated tritium in the coolant, the obvious solution is coating of the tritium exposed surfaces with anti-permeation barriers. Stainless steels and EUROFER97 are the main materials for DEMO systems construction. While EUROFER97 is a reduced activation martensitic steel specially designed for the construction of fusion reactor blankets which will be exposed to neutron irradiation, stainless steels like 316(L) are used for constructing the other components and systems. Hydrogen isotopes in various gas mixtures are permanently circulated through the reactor systems as they are the fuel which drive it. This paper is a detailed analysis of different technologies and materials conceived for creating efficient barriers against hydrogen permeation through stainless steel and EUROFER97. This literature review presents some investigation of important aspects regarding the development of stable hydrogen permeation barriers in order to prevent adsorption in structural materials and permeation of hydrogen isotopes. These barriers will help avoid the corrosion and embrittlement effects, and also, they will prevent the migration of tritium towards other systems and environment which poses radiation protection issues.\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-02-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00560-4.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147340029","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Parity Transition of MHD Instabilities in LHD Experiments LHD实验中MHD不稳定性的宇称跃迁

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-11 DOI: 10.1007/s10894-026-00558-y

Yuki Takemura, Kiyomasa Watanabe

引用次数: 0

Conception and Manufacturing of Four Diodes for Tritium Detection 四种氚检测二极管的构想与制造

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-07 DOI: 10.1007/s10894-026-00550-6

Paul Eyméoud, Stéphane Biondo, Mihai Lazar, Nadia Grillet, Wilfried Vervisch, Vanessa Vervisch, Dominique Bérard

{"title":"Conception and Manufacturing of Four Diodes for Tritium Detection","authors":"Paul Eyméoud, Stéphane Biondo, Mihai Lazar, Nadia Grillet, Wilfried Vervisch, Vanessa Vervisch, Dominique Bérard","doi":"10.1007/s10894-026-00550-6","DOIUrl":"10.1007/s10894-026-00550-6","url":null,"abstract":"<div>\u0000 \u0000 Tritium dosimetry constitutes a major nuclear safety issue for fusion reactors. Among the numerous tritium detection techniques, beta-voltaic detection is a simple and real-time approach, consisting in using a diode to collect the beta particles resulting from tritium decay and convert it in an electrical signal. Particularly, the use of a wide bandgap semiconductor, such as silicon carbide (4 H-SiC), for the diode conception, allows to increase its electrical conversion efficiency. In this context, we have designed four different SiC-based diode structures to perform tritium beta-voltaic detection: two PIN diodes, a Metal-Insulator-Semiconductor (MIS) diode, and a Junction Barrier Schottky (JBS) diode. From Monte-Carlo and finite elements simulations, we have optimized, for each diode, several structural parameters in order to maximize the electrical response, such as p + layer thickness and doping concentration, distance between ohmic contacts, n- doping concentration. The four optimized diodes have then been manufactured in cleanroom, and are now ready for experimental tests.\u0000 </div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147338026","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Study of Leakage Electromagnetic Field Monitoring with a Wide Frequency Range on Safety Management in a Magnetic Fusion Facility 宽频率泄漏电磁场监测在磁融合设施安全管理中的应用研究

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-07 DOI: 10.1007/s10894-026-00553-3

Masahiro Tanaka, Jianqing Wang, Tatsuhiko Uda

{"title":"Study of Leakage Electromagnetic Field Monitoring with a Wide Frequency Range on Safety Management in a Magnetic Fusion Facility","authors":"Masahiro Tanaka, Jianqing Wang, Tatsuhiko Uda","doi":"10.1007/s10894-026-00553-3","DOIUrl":"10.1007/s10894-026-00553-3","url":null,"abstract":"<div>With respect to considerations of nuclear fusion systems, since the electromagnetic field in the wide frequency range from the static magnetic field to extremely high frequency was utilized for the plasma confinement, heating at the magnetic confinement fusion facilities, not only ionizing radiation but also non-ionizing radiation should be investigated and discussed in terms of occupational protection as one of the issues in fusion facilities. To clarify the behavior of non-ionizing radiation, leakage from electric and magnetic fields has been observed at the Large Helical Device (LHD), because a strong magnetic field generated by large superconducting magnet coils for plasma confinement, in addition to high-frequency and high-power oscillators for ion cyclotron range of frequencies (ICRF) and electron cyclotron resonance heating (ECRH) for plasma heating, are used. In the LHD experiments, magnetic field leakage has been observed at extremely low frequencies (ELFs) around a power supply system for superconducting magnet coils. The magnetic field outside the experimental hall and the intensity of electric field leakage from the oscillators for ICRF and ECRH are significantly below the International Commission on Non-Ionizing Radiation Protection (ICNIRP) guidelines and radio frequency exposure protection standards in Japan (RCR-STD38). The ICNIRP and RCR-STD38 provide guidelines for limiting exposure to electric and magnetic fields to protect against established adverse health effects. The guidelines for safety management to protect the working people in fusion facilities should be made clearer with respect to occupational protection from non-ionizing radiation.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00553-3.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337616","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Comments on the Paper “Fundamental Scaling of Adiabatic Compression of Field Reversed Configuration Thermonuclear Fusion Plasmas” 对“场反转组态热核聚变等离子体绝热压缩的基本尺度”一文的评论

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-07 DOI: 10.1007/s10894-026-00554-2

K. Lackner, R. Burhenn, S. Fietz, A. v. Müller, J. Ball

{"title":"Comments on the Paper “Fundamental Scaling of Adiabatic Compression of Field Reversed Configuration Thermonuclear Fusion Plasmas”","authors":"K. Lackner, R. Burhenn, S. Fietz, A. v. Müller, J. Ball","doi":"10.1007/s10894-026-00554-2","DOIUrl":"10.1007/s10894-026-00554-2","url":null,"abstract":"<div>In a recent paper Kirtley and Milroy [D. Kirtley, R. Milroy, J. of Fusion Energy (2023) 42:30] discuss the Helion concept for a pulsed reactor, in which two supersonic field-reversed configurations (FRCs) merge and the resulting plasmoid is adiabatically compressed to fusion conditions. Using D-He3 as fuel this would allow for efficient electromagnetic energy conversion during the subsequent expansion phase. Essential for their very promising projections of energy gain is the assumed large temperature ratio between ions and electrons ((:{T}_{i}/{T}_{e}approx:10)) resulting initially from the supersonic plasmoid collision and the following adiabatic compression. For reactor-relevant conditions, however, the collisional ion to electron power transfer exceeds the fusion power by more than an order of magnitude at (:{T}_{i})=100 keV (and by over two orders at (:{T}_{i})=40 keV). Even if this exchange does not change total pressure, it rapidly erodes (:{T}_{i}/{T}_{e}gg:1) and causes the time-integrated fusion energy yield to fall well below values inferred from the initial, non-equilibrated state. While this does not preclude a D-He3 FRC reactor our analysis implies much tighter requirements on plasma lifetime, anomalous losses, and direct-conversion efficiency than suggested in D. Kirtley, R. Milroy, J. of Fusion Energy (2023) 42:30.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00554-2.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147337549","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Neutron Producing Reactions in Implosion and Direct Heating Experiments of Inertial Confinement Fusion 惯性约束聚变内爆和直接加热实验中的产中子反应

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-02-03 DOI: 10.1007/s10894-025-00547-7

A. Youssef, R. Kodama

{"title":"Neutron Producing Reactions in Implosion and Direct Heating Experiments of Inertial Confinement Fusion","authors":"A. Youssef, R. Kodama","doi":"10.1007/s10894-025-00547-7","DOIUrl":"10.1007/s10894-025-00547-7","url":null,"abstract":"<div>Neutron production is the critical factor in judging the success of fusion in implosion and direct heating pathways for implementing inertial confinement fusion (ICF) using CD and CD2 targets. Therefore, identifying the source of the emitted neutrons is the most important factor in determining whether nuclear fusion has been achieved efficiently or not. Thermonuclear and beam fusions of the D(d, n)3He reaction were thought to be the only neutron-producing reactions in the ICF pathway. This work, through in-depth analysis of experimental measurements and simulations using the 3D Monte Carlo code MCUNED, demonstrates that several neutron-producing interactions contribute to the overall neutron yield. The 12C(d, n)13N, and D(12c, n)13N stripping reactions participate in the neutron production with much higher neutron yield compared to the D(d, n)3He fusion reaction. Deuteron Break-up, photodissociation, electro-disintegration and photonuclear reactions can contribute to the total neutron production. The relative contribution of each reaction compared to the D(d, n)3He reaction was determined. Based on the above, considering the D(d, n)3He fusion reaction as the only source of neutrons will lead to incorrect results.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147336783","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Visualization of fusion plasmas 融合等离子体的可视化

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-01-20 DOI: 10.1007/s10894-026-00549-z

Hiroaki Ohtani, Nobuaki Ohno, Yuichi Tamura, Akira Kageyama, Seiji Ishiguro, Tetsuya Sato, Shintaro Kawahara, Mamoru Shoji, Kunihiro Ogawa, Kunqi Hu, Koji Koyamada

{"title":"Visualization of fusion plasmas","authors":"Hiroaki Ohtani, Nobuaki Ohno, Yuichi Tamura, Akira Kageyama, Seiji Ishiguro, Tetsuya Sato, Shintaro Kawahara, Mamoru Shoji, Kunihiro Ogawa, Kunqi Hu, Koji Koyamada","doi":"10.1007/s10894-026-00549-z","DOIUrl":"10.1007/s10894-026-00549-z","url":null,"abstract":"<div>This paper discusses the importance and advancements of visualization technology in fusion science research. First, visualization is an essential process for analyzing experimental and simulation data, aiding in the understanding of complex phenomena such as plasma. It emphasizes that, instead of conventional two-dimensional graphs, virtual reality (VR) technology enables researchers to observe data in three dimensions. This approach leads to a more intuitive understanding of complex phenomena. Additionally, VR technology provides an environment where multiple researchers can simultaneously discuss and analyze plasma physics, making it highly useful for research. Furthermore, VR plays a crucial role in effectively communicating research findings to the general public in an accurate and accessible manner. At the National Institute for Fusion Science, a VR visualization system has been established to efficiently analyze large-scale simulation data using CAVE-type VR devices. The latest technology, such as head-mounted displays (HMDs), has also been introduced. The applications of visualization technology are not limited to fusion science but are expected to expand into other fields as well, making it a promising area of ongoing development. This paper presents key visualization research achievements conducted at the National Institute for Fusion Science. We are also developing new capabilities to display both CAD and simulation data on HMDs as we port the VR software originally designed for large CAVE-type systems. These developments will also be described.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-01-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-026-00549-z.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146027102","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Neutron Camera in Large Helical Device 大型螺旋装置中的中子照相机

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-01-20 DOI: 10.1007/s10894-026-00548-0

Kunihiro Ogawa, Siriyaporn Sangaroon, Takashi Kobuchi, Mitsutaka Isobe

引用次数: 0

Machine Learning Based Efficiency Calculator (MaLBEC) for Nuclear Fusion Diagnostics 基于机器学习的核聚变诊断效率计算器（MaLBEC）

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2026-01-07 DOI: 10.1007/s10894-025-00546-8

Kimberley Lennon, Chantal Shand, Gemma Wilson, Robin Smith

{"title":"Machine Learning Based Efficiency Calculator (MaLBEC) for Nuclear Fusion Diagnostics","authors":"Kimberley Lennon, Chantal Shand, Gemma Wilson, Robin Smith","doi":"10.1007/s10894-025-00546-8","DOIUrl":"10.1007/s10894-025-00546-8","url":null,"abstract":"<div>Diagnostics are critical for commercial and research fusion machines, since measuring and understanding plasma features is important to sustaining fusion reactions. The neutron flux (and therefore fusion power) can be indirectly calculated using neutron activation analyses, where potentially large numbers of activation foils are placed in the neutron flux, and delayed gammas from key reactions are measured via gamma spectrometry. In gamma spectrometry, absolute efficiency forms part of the activity calculation, and equals to the ratio of the total number of photons detected to the number emitted by a radioactive sample. Hence, it is imperative that they are calculated efficiently and accurately. This paper presents a novel digital efficiency calculation algorithm, the Machine Learning Based Efficiency Calculator (MaLBEC), that uses state-of-the-art supervised machine learning techniques to calculate efficiency values of a given sample, from only four inputs. In this paper, the performance of the MaLBEC is demonstrated with a fusion sample and compares the values to a traditional efficiency calculation method, Monte Carlo N-Particle (MCNP). The efficiencies from the MaLBEC were within an average 5% of the ones produced by MCNP, but with an exceptional reduction in computation time of 99.96%. When the efficiency values from both methods were used in the activity calculation, the MaLBEC was within 3% of the MCNP results.</div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"45 1","pages":""},"PeriodicalIF":2.1,"publicationDate":"2026-01-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00546-8.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145930418","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0