Fusion Engineering and Design最新文献_第8页

First experimental results of HYDREX operation in hydrogen removal from helium for fusion applications

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-09 DOI: 10.1016/j.fusengdes.2025.114936

Vincenzo Narcisi , Dario Diamanti , Daniele Martelli , Alessia Santucci

{"title":"First experimental results of HYDREX operation in hydrogen removal from helium for fusion applications","authors":"Vincenzo Narcisi , Dario Diamanti , Daniele Martelli , Alessia Santucci","doi":"10.1016/j.fusengdes.2025.114936","DOIUrl":"10.1016/j.fusengdes.2025.114936","url":null,"abstract":"<div><div>The tritium removal from gaseous effluents represents a key issue for the deployment of future fusion power plants even more when tritium is present in the order of parts per million. A promising system derives from the fission experience, where oxidizing beds combined with Zeolite Molecular Sieve (ZMS) beds are adopted to purify helium coolant and cover gas. In this work, an integral helium purification process involving these technologies is studied in the Hydrogen Extraction (HYDREX) experimental facility assuming boundary conditions relevant for the Coolant Purification System of the EU-DEMO Helium Cooled Pebble Bed Breeding Blanket. The experimental campaign demonstrates the efficient purification performance allowing the removal of 96 % of the hydrogen. Then, a proper regeneration procedure is experimentally investigated providing a satisfactory restoring of the adsorption capability of the zeolite material. Some open aspects are individuated, mainly related to the uneven distribution of the flow through the ZMS bed causing an earlier saturation of the bed and a not completed regeneration of the zeolite material. Furthermore, a huge release of hydrogen in the first minutes of the regeneration is experienced due to the not completed oxidation. The results obtained in this work are relevant for the definition of further experimental investigations and as guidelines for the design of gas detritiation systems.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114936"},"PeriodicalIF":1.9,"publicationDate":"2025-03-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578546","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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

Manufacture study of ITER radial X-ray camera

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-09 DOI: 10.1016/j.fusengdes.2025.114895

Kaiyun Chen , Liqun Hu , Hong Yu , Hongrui Cao , Shi Li , Jizong Zhang , Xiuli Sheng , Jinlong Zhao , Luying Niu , Zijun Zhang , Yixiang Xing , Qiang Li , Lin Dong , Sheng Liu , Zhina Zhang

引用次数: 0

System level design of the Tangential visible and infrared viewing system for DTT

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-09 DOI: 10.1016/j.fusengdes.2025.114906

S. Vives , M.-H. Aumeunier , X. Courtois , L. Dubus , M. Alonzo , M. Iafrati

{"title":"System level design of the Tangential visible and infrared viewing system for DTT","authors":"S. Vives , M.-H. Aumeunier , X. Courtois , L. Dubus , M. Alonzo , M. Iafrati","doi":"10.1016/j.fusengdes.2025.114906","DOIUrl":"10.1016/j.fusengdes.2025.114906","url":null,"abstract":"<div><div>The Divertor Tokamak Test facility (DTT) is a superconducting tokamak under construction in Frascati (Italy). Its main goal is the study of strategies for the management of plasma exhaust in a reactor-grade tokamak plasmas, to support ITER operation and the design of DEMO. It will incorporate a visible and infrared viewing system dedicated to machine protection and plasma physics. This system, called Tangential Viewing System (TVS), consists of 6 Line-of-Sight (LoS) located in 3 sectors in equatorial ports. Each LoS provides a wide-angle view of 44° x 60°, with the first wall being the main area of surveillance.</div><div>This paper details the work on TVS during its initial concept development, focusing on defining requirements, verifying preliminary performance, and developing potential design solutions.</div><div>Each LoS is made of a Front Mirrors Unit collecting and transferring the light outside the vacuum vessel through a sapphire window. To optimize the performance in both channels, the visible and infrared beams are separated behind the window by a large dichroic. Then in each channel, an objective lenses creates a collimated beam which is propagated by an optical relay system up to the detector. In terms of the performance, the preliminary assessment of the spatial resolution and coverage is described. The spatial coverage of the outer and inner walls is evaluated to 97 % and 30 % respectively, which allows the first wall protection.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114906"},"PeriodicalIF":1.9,"publicationDate":"2025-03-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578547","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

Detection of absorbed neutrons through determination of rhenium content in tungsten with laser induced fast pulse discharge

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-09 DOI: 10.1016/j.fusengdes.2025.114943

B.D. Stankov , I. Traparić , M. Gavrilović Božović , M. Ivković

{"title":"Detection of absorbed neutrons through determination of rhenium content in tungsten with laser induced fast pulse discharge","authors":"B.D. Stankov , I. Traparić , M. Gavrilović Božović , M. Ivković","doi":"10.1016/j.fusengdes.2025.114943","DOIUrl":"10.1016/j.fusengdes.2025.114943","url":null,"abstract":"<div><div>The diagnostics of the first wall of future fusion reactors provides a major source of information about the state of the machine and the expected lifetime of the first wall components. As the absorption of neutrons can cause induced radioactivity of the first wall tiles and produce significant structural changes to material, it is of the essence to monitor the amount of absorbed neutrons. One possibility to monitor them is via nuclear transmutation reaction where tungsten absorbs neutron and creates rhenium core. Therefore by assessing the amount of rhenium present in the material, information about neutron irradiation conditions can be deduced. Hence in this work, in order to assess the concentration of rhenium, Laser Induced Breakdown Spectroscopy (LIBS) combined with Fast Pulse Discharge (FPD) was used. The main achievement of this work is the amplification of line intensity and signal to noise ratio compared to the classical LIBS setup at reduced pressure which enables detection of <em>Re</em> in samples with less than 0.1% at of <em>Re</em>. With synergistic use of LIBS and FPD, ie. Laser Induced Fast Pulse Discharge (LIFPD), significantly enhanced Limit Of Detection (LOD) is obtained compared to the previously reported results. This result is of particular importance since only small amounts of rhenium are expected to be found in the first wall tiles, therefore making this approach suitable for this type of diagnostics.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114943"},"PeriodicalIF":1.9,"publicationDate":"2025-03-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578551","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

Transient electrical behavior of DEMO toroidal field coils system in normal operation and fault conditions

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-09 DOI: 10.1016/j.fusengdes.2025.114941

G. Messina , P. Zito , M. Manganelli , S. Valenti , L. Morici , V. Corato , A. Ferro

{"title":"Transient electrical behavior of DEMO toroidal field coils system in normal operation and fault conditions","authors":"G. Messina , P. Zito , M. Manganelli , S. Valenti , L. Morici , V. Corato , A. Ferro","doi":"10.1016/j.fusengdes.2025.114941","DOIUrl":"10.1016/j.fusengdes.2025.114941","url":null,"abstract":"<div><div>This study examines the transient electrical behavior of the DEMO Toroidal Field Coils (TFC) system under normal operation and fault conditions. The DEMO superconducting magnet system comprises a Central Solenoid, Poloidal Field coils, and d-shaped Toroidal Field Coils, the latter all connected in series. Fast Discharge Units (FDUs) are integrated to protect the system by quickly dissipating stored magnetic energy during a quench. Simulations were conducted using MATLAB/Simulink and ANSYS/Simplorer, incorporating the TFC inductance matrix, power cable connection impedances, and stray parameters of discharge resistors. The results highlight the significant voltage peaks that occur during fast discharges, which can stress the insulation of TFCs and associated components. Various fault scenarios, including ground faults and short circuits, were analyzed to determine their impact on peak transient voltages. The findings highlight the importance of a consistent quench protection system and the accurate design of the insulation level coordination to ensure the safety and reliability of superconducting magnets. The simulations showed consistent results across both platforms, validating the models used. Future work will aim to refine the models and explore additional fault scenarios to further enhance system performance and reliability. This comprehensive fault analysis provides critical insights for the design and safety of the DEMO TFC system, ensuring its reliable operation under diverse conditions.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114941"},"PeriodicalIF":1.9,"publicationDate":"2025-03-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578550","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

Breeding Blanket Remote Maintenance Concepts in EU DEMO: From vertical extraction to horizontal accommodation in cask

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-08 DOI: 10.1016/j.fusengdes.2025.114902

Gonçalo Teixeira, Alberto Vale

{"title":"Breeding Blanket Remote Maintenance Concepts in EU DEMO: From vertical extraction to horizontal accommodation in cask","authors":"Gonçalo Teixeira, Alberto Vale","doi":"10.1016/j.fusengdes.2025.114902","DOIUrl":"10.1016/j.fusengdes.2025.114902","url":null,"abstract":"<div><div>During the lifetime of a magnetic confinement nuclear fusion reactor, the replacement and decommissioning of Breeding Blankets (BB) are anticipated operations that occur in the upper-level containment cell of a reactor building, such as EU DEMO. Such operations are not feasible by in-situ human interaction. Remote Handling (RH) is the leading solution in the nuclear industry for addressing these operations. The BB is a structure with approximately 13 metres in length and weights between 100 and 120 tons. The BB is assumed to be extracted vertically and transported horizontally by casks to the Active Maintenance Facility. The BB is divided into 5 different segments for maintenance purposes: 2 inboard and 3 outboard segments. Both inboard and outboard segments pose different handling and rotation challenges. Three design concepts for handling/rotating (H/R) BB segments are proposed in this study. The concepts rely on variations of the Medium Payload Manipulation Stillage (MPMS), a system responsible for securing and H/R the BB segments. The concepts are: (I) Crane Support Concept (heavily relies on a crane to perform the rotation of BB segments), (II) Lifting Platform Support Concept (only relies on the MPMS itself to perform the rotation of the BB segments), and (III) Sliding Platform Support Concept (only relies on the MPMS itself to perform the rotation of the BB segments but provides additional support and makes use of gravity to its advantage). A comparative analysis highlighting the concept’s advantages and disadvantages is presented. The analysis and conclusions presented in this paper are derived from the assessed system requirements, possible risks concerning the CAD model designs, expected sequence of operations performed by the MPMS and the dimensions of the systems depicted in the CAD models.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114902"},"PeriodicalIF":1.9,"publicationDate":"2025-03-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578548","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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

Transient multiphysics modeling of the electromagnetic loads on the first wall during plasma disruptions

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-08 DOI: 10.1016/j.fusengdes.2025.114929

Sunday C. Aduloju, Sergey Smolentsev, Paul Humrickhouse

{"title":"Transient multiphysics modeling of the electromagnetic loads on the first wall during plasma disruptions","authors":"Sunday C. Aduloju, Sergey Smolentsev, Paul Humrickhouse","doi":"10.1016/j.fusengdes.2025.114929","DOIUrl":"10.1016/j.fusengdes.2025.114929","url":null,"abstract":"<div><div>A transient three-dimensional multiphysics finite element model that relies on coupling electromagnetic and solid-mechanics modules was developed for modeling the effect of electromagnetic (EM) loads on the in-vessel components during plasma midplane disruptions. The T-Ω formulation is employed within the finite element framework to numerically solve the Maxwell's governing equations of the electromagnetic problem, for the induced current density (<span><math><mi>J</mi></math></span>), and magnetic flux density (<span><math><mi>B</mi></math></span>) on the in-vessel components. The <span><math><mrow><mi>J</mi><mo>×</mo><mi>B</mi></mrow></math></span> forces are fed into the transient large strain kinematics within solid mechanics module through a one-way coupled interface for computation of stress and displacement distributions on the first wall (FW). The effects of the continuity of the FW on <span><math><mrow><mi>J</mi><mo>×</mo><mi>B</mi></mrow></math></span> forces and consequently stress state are studied. The current densities are higher at the edges of the non-continuous FW and at the midplane of the continuous FW. The current quench produces forces that both pull away and push the non-continuous FW to the plasma while the current quench causes the continuous FW to be pushed towards the plasma only. The maximum stress on the non-continuous FW and the continuous FW are 93 MPa and 52 MPa. The factor of safety (FOS) calculated for non-continuous and continuous FWs under the EM loads are about 5 and 10 respectively. Both walls will withstand the EM loads without failure, but the continuous blanket FW has higher structural integrity for the EM loads. Preliminary studies of the EM loads on the inboard blanket are consistent with the FW results and earlier works.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114929"},"PeriodicalIF":1.9,"publicationDate":"2025-03-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143578549","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

A risk analysis for Helium Cooling System (HCS) of HCCP-TBS

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-06 DOI: 10.1016/j.fusengdes.2025.114921

Daniel Moya Alonso , Youngmin Lee , Enric Bargalló Font , Chang Shuk Kim , Myungho Kim , Changwook Shin , Seok-Kwon Son , Mu-Young Ahn , Martín Gorriarán Vicario , Javier Leboreiro Iriarte

{"title":"A risk analysis for Helium Cooling System (HCS) of HCCP-TBS","authors":"Daniel Moya Alonso , Youngmin Lee , Enric Bargalló Font , Chang Shuk Kim , Myungho Kim , Changwook Shin , Seok-Kwon Son , Mu-Young Ahn , Martín Gorriarán Vicario , Javier Leboreiro Iriarte","doi":"10.1016/j.fusengdes.2025.114921","DOIUrl":"10.1016/j.fusengdes.2025.114921","url":null,"abstract":"<div><div>Climate change is a reality. Every day, the effects of it are visible and one of the main challenges is to achieve carbon neutrality by 2050. With this goal, one increasing technology in clean energy generation is nuclear fusion. Nuclear fusion needs unique working conditions, such as: extremely elevated temperatures, strong electromagnetic fields, and ultra-high vacuum conditions. But another challenging milestone should be taken into account: breeding tritium. Tritium quantity is naturally scarce on Earth and has to be generated, which is costly and currently very limited. One of the missions for the later stages of ITER operation is to demonstrate the feasibility of producing tritium from lithium within the vacuum vessel, making breeding blankets a key component of ITER.</div><div>Given its relevance, there are several proposals to breed tritium, from using helium or water as a coolant, or liquid types like lithium-lead (LiPb) alloy or solid types such as lithiated ceramic pebbles as breeder. One of the proposals being currently developed, is the Helium Cooled Ceramic Pebble (HCCP), where lithiated ceramic pebbles are used as breeder and helium, as coolant. HCCP is designed to test tritium breeding, recovery, and withstand reactor loads. A key function is heating removal, with the Helium Cooling System (HCS) essential for ITER's safety and availability.</div><div>This paper describes the Reliability, Availability, Maintainability and Inspectability (RAMI) analysis and preliminary risk assessment (HAZOP) performed, together with the proposed design, operation and maintenance suggestions needed to achieve the mail goal: a reliable and safe operation for HCCP-HCS.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114921"},"PeriodicalIF":1.9,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143552887","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

Preliminary fault analysis of EFCC system in the Divertor Tokamak Test (DTT) facility

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-06 DOI: 10.1016/j.fusengdes.2025.114915

Antonio Iaiunese , Raffaele Albanese , Andrea Gaetano Chiariello , Pasquale Zumbolo , Raffaele Martone

引用次数: 0

Development of transport calculation for unstructured mesh geometry in cosRMC

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-06 DOI: 10.1016/j.fusengdes.2025.114933

Zhenyu Wang, Shichang Liu, Yixue Chen

{"title":"Development of transport calculation for unstructured mesh geometry in cosRMC","authors":"Zhenyu Wang, Shichang Liu, Yixue Chen","doi":"10.1016/j.fusengdes.2025.114933","DOIUrl":"10.1016/j.fusengdes.2025.114933","url":null,"abstract":"<div><div>The traditional constructive solid geometry (CSG) modeling approach fails to meet the requirements of complex geometric transport, fusion neutronics analysis, multi-physics coupling calculations, and large-scale nuclear radiation effect simulations. To tackle these challenges, this study developed unstructured mesh (UM) transport and statistical functionalities in the Monte Carlo particle transport code, cosRMC, based on the MOAB and libMesh libraries. These functionalities allow for accurate particle positioning and tracking within UM elements, and the transport process is accelerated through a neighbor element acceleration technique. The track-length estimator is then used for tally results. To verify the computational accuracy and efficiency of the UM feature, three test cases were constructed and analyzed: a box case, a fuel rod case, and a tokamak case. The computational results demonstrate that the <em>k<sub>eff</sub></em> values calculated by UM-cosRMC geometry transport function align well with those from traditional CSG and DAGMC geometries, and the UM tally results are consistent with those of UM-MCNP calculations. In terms of computational efficiency, after employing the neighbor mesh acceleration technique, the speed of UM geometry calculations improved significantly. The UM geometry calculation efficiency based on the libMesh library is higher than that based on the MOAB library, with the former taking 1.18 to 10.42 times longer than CSG geometry calculations and 0.37 to 0.96 times that of DAGMC geometry. Compared to UM-MCNP calculation efficiency, UM-cosRMC shows a distinct advantage, reducing computation time by >70 % with the same mesh. Additionally, this study analyzed the computational efficiency of UM transport based on both libraries, and the results indicate that the libMesh-based UM calculations outperform in terms of UM reading speed, memory usage, and transport computation speed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114933"},"PeriodicalIF":1.9,"publicationDate":"2025-03-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143562750","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