Fusion Engineering and Design最新文献

{"title":"Verification of vacuum regeneration for cryogenic molecular sieve bed","authors":"Pil-Kap Jung,&nbsp;Hyun-Goo Kang,&nbsp;Min Ho Chang,&nbsp;Jea-Uk Lee,&nbsp;Dong-you Chung,&nbsp;Junyoung Hur","doi":"10.1016/j.fusengdes.2025.115410","DOIUrl":"10.1016/j.fusengdes.2025.115410","url":null,"abstract":"<div><div>Cryogenic adsorption, referred to as Cryogenic Molecular Sieve Bed (CMSB), is one of the technologies capable of purifying and recovering helium-3 produced in tritium storage systems. In typical adsorption process using temperature swing adsorption, the regeneration step to remove impurities adsorbed on the adsorption bed is performed by heating and purging with either a portion of the product gas or an inert gas. To enhance the recovery efficiency and purity of helium-3, vacuum regeneration can be employed as an alternative to gas purging. This study evaluated the applicability of the vacuum regeneration for CMSB in the helium-3 recovery system. The adsorption performance of the two regeneration methods, gas purging and vacuum regeneration, was compared experimentally. Vacuum regeneration was confirmed to be reliable and demonstrated comparable performance to the gas purging method.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115410"},"PeriodicalIF":2.0,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144911552","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}

{"title":"Three-dimensional fluid simulation for the effects of argon additive in a negative hydrogen ion source for fusion","authors":"Si-Yu Xing ,&nbsp;Shi-Bo Li ,&nbsp;Fei Gao ,&nbsp;Yu-Ru Zhang ,&nbsp;Miao Zhao ,&nbsp;Shao-Fei Geng ,&nbsp;Guang-Jiu Lei ,&nbsp;You-Nian Wang","doi":"10.1016/j.fusengdes.2025.115405","DOIUrl":"10.1016/j.fusengdes.2025.115405","url":null,"abstract":"<div><div>To enhance the volume generation of negative ions in ion source for China Fusion Engineering Test Reactor (CFETR) neutral beam injection systems, a three-dimensional fluid model is developed in this paper. The difference between pure hydrogen and H₂/Ar mixed discharges is explored under various discharge conditions and magnetic field configurations. The results show that the negative hydrogen ion density 5 cm above the plasma grid increases by up to 44 % when Ar is added at low pressure (0.3 Pa). However, the enhancement effect is weakened at high pressure (0.5 or 1 Pa). By introducing the magnetic shield, the negative hydrogen ion density 5 cm above the plasma grid in pure hydrogen discharges is increased by 142 %. Surprisingly, the combined effect of magnetic shield and Ar addition result in a 236 % increase in negative hydrogen ion density, which exceeded the sum of each of them (186 %). In addition, the negative hydrogen ion density first rises and then falls with increasing magnetic filter field strength, and the highest density is achieved at 0.15 T. It is also found that the addition of Ar has the best effect on the enhancement of negative ion density at 0.15 T.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115405"},"PeriodicalIF":2.0,"publicationDate":"2025-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907912","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}

{"title":"Design and analysis of the cryostat of the ITER magnet cold test bench","authors":"Qingzhou Yu ,&nbsp;Hao Xu ,&nbsp;Genmu Shi ,&nbsp;Shilin Chen ,&nbsp;Xinyuan Qian ,&nbsp;Qingxi Yang ,&nbsp;Thierry Schild ,&nbsp;Guillaume Vitupier ,&nbsp;Jose Lorenzo ,&nbsp;Mohit Jadon ,&nbsp;Hoyoung Kim ,&nbsp;Xiaoming Yu ,&nbsp;Zhaoxi Chen ,&nbsp;Dan Zhu ,&nbsp;Jin Chai ,&nbsp;Rui Hu","doi":"10.1016/j.fusengdes.2025.115404","DOIUrl":"10.1016/j.fusengdes.2025.115404","url":null,"abstract":"<div><div>ITER is constructing a Magnet Cold Test Bench (MCTB) to evaluate the discharge characteristics, quench protection, ground insulation, and leakage rates of all ITER toroidal field (TF) coils and the poloidal field 1 (PF1) coil, ensuring reliable operation when integrated into the ITER tokamak. The MCTB cryostat, the primary component of the bench, is designed for compatibility with TF and PF1 configurations, providing a thermally insulated and high-vacuum environment for the coils. This paper begins with an overview of the cryostat structure, encompassing its shells, multi-layer insulation (MLI), magnet supports, and pressure relief device (PRD). Next, thermal analyses are performed to quantify the thermal conduction from the magnet supports to the tested coil and radiation from the MLI. Results demonstrate that even when the liquid helium pipeline temperature of the cold plates rises to 30 K, the thermal conduction load on the coil via the supports remains well below the 400 W limit. Regarding radiation heat, when the number of MLI layers increases to 50, the total radiation heat on the coil for the TF and PF1 configurations is approximately 839 W and 799 W, respectively, both below the 1000 W threshold. Additionally, assessments of the cryostat shells’ structural responses under varying loading conditions reveal that a 10% safety margin in structural strength is maintained, and the buckling load multipliers exceed the corresponding critical thresholds even under the worst operational load, demonstrating the absence of plastic collapse and buckling instability. A simple sealing scheme is proposed to address the pre-tightening problem of large-diameter sealing between cryostat shells, incorporating an effective suppression solution for flange slippage during sealing. Finally, significant developments in the cryostat’s manufacturing and future production plans are reviewed. This paper can provide valuable technical guidance for the design of other magnet test platforms.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115404"},"PeriodicalIF":2.0,"publicationDate":"2025-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907914","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}

{"title":"Benchmarking of spherical tokamak power plant design in PROCESS and SARAS","authors":"Christopher Ashe ,&nbsp;P.N. Maya ,&nbsp;Stuart I. Muldrew ,&nbsp;Shishir Deshpande","doi":"10.1016/j.fusengdes.2025.115359","DOIUrl":"10.1016/j.fusengdes.2025.115359","url":null,"abstract":"<div><div>Uncertainty in systems codes can be analyzed based on the assumptions in the models used, and their combinations of input parameters before optimization. In this paper we compare the PROCESS and SARAS codes across a range of spherical tokamak designs that have been identified as possible pilot plant and commercial designs on the Indian-DEMO programme. Overall both codes produce partially similar results though differences in the calculation and treatment of the edge safety factor lead to discrepancies in the calculation of other key parameters with differences of <span><math><mrow><mo>≈</mo><mo>±</mo><mspace></mspace><mn>20</mn><mtext>%</mtext></mrow></math></span>. Mainly with plasma current, <span><math><mi>β</mi></math></span> components and subsequently confinement time calculations. Bootstrap current fraction calculations were shown to be unreliable and out of the regime of future power plants, highlighting the need for new surrogate models closer to power plant conditions . Using Monte Carlo based uncertainty quantification focusing on the epistemic uncertainty of the inboard toroidal field coil leg we see reasonable agreement in stress quantification between the two codes. The pessimistic uncertainty assumption still shows room for performance recovery in a reduced toroidal field strength scenario.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115359"},"PeriodicalIF":2.0,"publicationDate":"2025-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907911","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}

{"title":"Extraction of tensile properties of metallic alloys by small punch test: benchmarking inverse finite element method versus empirical correlations","authors":"Alexander Bakaev ,&nbsp;Dmitry Terentyev ,&nbsp;Chih-Cheng Chang ,&nbsp;Thomas Melkior","doi":"10.1016/j.fusengdes.2025.115395","DOIUrl":"10.1016/j.fusengdes.2025.115395","url":null,"abstract":"<div><div>The miniaturized specimens of three metallic alloys (bainitic reactor pressure vessel steel, ferritic-martensitic steel Eurofer97 and fcc CuCrZr alloy) important for nuclear and fusion applications are subjected to the small punch tests (SPTs) at room and elevated (300°C) temperatures. The baseline plasticity metric, such as yield stress, is extracted from the SPT results by means of various empirical and FEM-assisted correlations and inverse finite element method (IFEM) simulations. Further strain hardening data (up to 10 % plastic strain) is also extracted from the SPT results by the IFEM. Later on, the accuracy of the derived yield stress and strain hardening behavior is compared with the reference results of the uniaxial tensile tests.</div><div>For both studied temperatures the IFEM calculations were proven to show the best overall accuracy for the extraction of the yield stress for all the studied materials. As a simplified alternative, the FEM-assisted single-value empirical correlation based on the method from the European EN standard can be recommended for the extraction of the yield stress from RPV steels. The extraction of strain hardening behavior up to 5 % plastic strain from SPTs at both test temperatures was found to be consistently feasible only for softer alloys such as CuCrZr.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115395"},"PeriodicalIF":2.0,"publicationDate":"2025-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907909","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}

{"title":"W/Ta cold spray coatings as an armour layer for first wall steel components","authors":"Katja Hunger ,&nbsp;Rudolf Neu ,&nbsp;Hans Maier ,&nbsp;Bernd Böswirth ,&nbsp;Henri Greuner ,&nbsp;Jan Kondas ,&nbsp;Johann Riesch","doi":"10.1016/j.fusengdes.2025.115400","DOIUrl":"10.1016/j.fusengdes.2025.115400","url":null,"abstract":"<div><div>Cold spray could provide a simple and cost-effective method for coating large areas of plasma facing components regardless of their shape. Low local power deposition and the possibility to perform the process under ambient pressure are favorable features of this technology. In initial cold spray coating tests with pure tungsten, no pore-free coatings could be achieved, but trials with a mixture of W and Ta showed rather good results, resulting in dense coatings with a thickness of up to 2 mm on steel with a W content of up 70 %. In this contribution the initial high heat flux tests were expanded towards systematic studies of the coating behaviour under slow transient loads of up to 20 MW/m² and surface temperatures up to 1200 °C. As a result, it could be shown that the coatings survive cyclic loading up to surface temperatures of 1000 °C even under the highest heat loads of 20 MW/m² without any damage or surface modification.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115400"},"PeriodicalIF":2.0,"publicationDate":"2025-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144902932","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}

{"title":"Experimental assessment of palladium-silver membrane for isotope separation, rebalancing and protium removal","authors":"Vincenzo Narcisi,&nbsp;Linda Sansosti,&nbsp;Alessia Santucci","doi":"10.1016/j.fusengdes.2025.115406","DOIUrl":"10.1016/j.fusengdes.2025.115406","url":null,"abstract":"<div><div>The isotope separation, isotope rebalancing, and protium removal are critical functionalities for the fuel cycle of a fusion machine. Nowadays, cryogenic distillation and thermal cycling temperature swing absorption are considered the reference technologies for these tasks, but they are both characterized by high tritium inventory. In the past, the palladium-silver membranes were considered as an option with reduced inventory although some challenges were identified, mainly related to the efficiency of the separation process. This work aims at experimentally investigate the capabilities of this technology for the above-mentioned functionalities in the improved HyFraMe facility at ENEA Frascati laboratories. To do this, the Pd-Ag membrane is preliminary characterized with pure protium and pure deuterium and the permeability and the breakthrough curves are obtained for both the isotopes. After that, the isotope separation tests are performed with different protium-deuterium mixtures. The isotope separation remains a challenging task for the palladium-silver membrane, mainly due to the low efficiency of the process. On the contrary, looking at the isotope rebalancing and protium removal functions, the results obtained in the present campaign are in line with the requirements of a typical fusion machine. Both the functions can be fulfilled with a single and compact permeator which allow to reduce tritium inventory, encumbrances and energy consumption.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115406"},"PeriodicalIF":2.0,"publicationDate":"2025-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144907910","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}

{"title":"Heating of SPIDER drivers during nominal operations: Calorimetry and numerical estimation","authors":"S. Denizeau ,&nbsp;D. López Bruna ,&nbsp;P. Agostinetti ,&nbsp;G. Berton ,&nbsp;A. La Rosa ,&nbsp;M. Pavei","doi":"10.1016/j.fusengdes.2025.115391","DOIUrl":"10.1016/j.fusengdes.2025.115391","url":null,"abstract":"<div><div>SPIDER, the ion source prototype for ITER Neutral Beam Injectors, is under development at the Neutral Beam Test Facility (NBTF) in Padua, Italy. A first experimental campaign took place between 2018 and 2021. This paper focuses on the heating of SPIDER drivers during operations, primarily caused by RF power dissipation through eddy currents in passive structure elements. Specifically, it examines short pulses with low RF power (about 20 to 50 kW per driver) of the 2018–2021 campaign. It aims at validating the results of a 3D electromagnetic model that simulates RF coupling with plasma, by providing a realistic evaluation of driver temperature and incident power. A calorimetric study allows to estimate the share of RF power absorbed by the driver passive elements. In line with existing literature, results show that around 50% of the RF power is typically lost, with 90% of this loss occurring in the Faraday Shield Lateral Wall (FSLW). The second part of this study describes a self-consistent set of simulations to assess driver heating. Aforementioned electromagnetic code calculates the spatial distribution of power on the FSLW, and ANSYS Fluent models of the Faraday Shield cooling circuits are coupled with a thermal steady-state model that accounts for radiation, plasma heating and backstreaming ions (BSI). Three load cases are considered: low RF power without BSI (typical of 2018–2021 campaign), full target power, and a “worst-case scenario” with maximum RF power on the Faraday Shield. The temperature at which the mechanical properties of electrodeposited copper degrade is never exceeded. The electromagnetic code assumes constant electrical conductivity on the FSLW — that of copper at 50 °C. Thermal simulations support this hypothesis at low power but predict important variations of temperature — and therefore conductivity — at target conditions, locally modifying the RF coupling.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115391"},"PeriodicalIF":2.0,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144886839","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}

{"title":"Evaluation of microstructural and mechanical properties of ARAA plates with various thicknesses","authors":"Sungyu Kim,&nbsp;Hyoseong Gwon,&nbsp;Yi-Hyun Park","doi":"10.1016/j.fusengdes.2025.115396","DOIUrl":"10.1016/j.fusengdes.2025.115396","url":null,"abstract":"<div><div>The Advanced Reduced-Activation Alloy (ARAA), developed in Korea as a reduced-activation ferritic/martensitic (RAFM) steel, is designed for structural applications in fusion reactor breeding blankets, where materials are subjected to elevated temperatures and intense neutron irradiation. Given the diverse geometries and thicknesses of structural components, ensuring consistent mechanical reliability across different plate dimensions is critical. This study investigated the microstructural and mechanical properties of ARAA plates with thicknesses of 20, 36, and 62 mm, all fabricated under identical normalizing and tempering conditions. Optical microscopy and EBSD analyses revealed fine, non-elongated prior austenite grains (PAGs) without localized coarsening across all thickness positions and directions. Despite experiencing the lowest thickness reduction, the 62 mm plate retained a refined grain structure throughout the thickness, similar to the 20 mm plate, which underwent the highest deformation. Tensile and impact tests showed consistent strength, ductility, and toughness in all directions, including the short transverse, with no evidence of anisotropy or degradation related to thickness. These results demonstrate that the current ARAA fabrication process enables stable grain morphology and uniform mechanical performance across a thickness range of 20–62 mm, supporting the reliable use of ARAA in fusion blanket structures subjected to multidirectional loading, thermal gradients, and irradiation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115396"},"PeriodicalIF":2.0,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144879534","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}

{"title":"Experimental research on the adsorbent performance in neutral beam injector cryopump","authors":"Qianxu Wang ,&nbsp;Yuanlai Xie ,&nbsp;Fang Wang ,&nbsp;Yufan Li","doi":"10.1016/j.fusengdes.2025.115398","DOIUrl":"10.1016/j.fusengdes.2025.115398","url":null,"abstract":"<div><div>To enhance the performance of the neutral beam injector (NBI) cryopump, experimental research was conducted on cryogenic adsorbent materials to select the ones with better performance. In the paper, three types of activated carbon materials prepared by different processes were selected and named as No 1, No 2 and No 3, respectively. Through structural analysis and cryogenic adsorption performance experiments, the internal structural characteristics of the activated carbon materials were analyzed, meanwhile their performance was evaluated. The results indicate that No 1 has hierarchical pore structures combining micropores and mesopores, its adsorption isotherm belongs to Type IV and accompanied by capillary condensation phenomena. At the pressure of 1E-3 Pa, its hydrogen pumping speed can reach 1.07E4 L/s. No 2 and No 3 are mainly composed of micropores, their adsorption isotherms belong to type I. At the pressure of 1E-3 Pa, the hydrogen pumping speed of No.3 can reach 1.05E4 L/s. In addition, the hydrogen pumping speed of the activated carbon materials under mixed gas intake conditions was analyzed, meanwhile the effect of the cryogenic adsorption planes temperature on their pumping speed and adsorption capacity were also studied. The research results reveal the adsorption characteristics of activated carbon and can provide reference for the selection of adsorbent materials for NBI cryopumps.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115398"},"PeriodicalIF":2.0,"publicationDate":"2025-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144879535","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}