Nuclear FusionPub Date : 2024-04-18DOI: 10.1088/1741-4326/ad4046
Guiding Wang, T. L. Rhodes, Q. Pratt, William A Peebles, Neal A Crocker, Rongjie Hong, M. E. Austin, M. V. Van Zeeland, Sterling P Smith
{"title":"Core electron temperature turbulence and transport during sawtooth oscillations in the DIII-D tokamak","authors":"Guiding Wang, T. L. Rhodes, Q. Pratt, William A Peebles, Neal A Crocker, Rongjie Hong, M. E. Austin, M. V. Van Zeeland, Sterling P Smith","doi":"10.1088/1741-4326/ad4046","DOIUrl":"https://doi.org/10.1088/1741-4326/ad4046","url":null,"abstract":"\u0000 Sawteeth are one of the concerning instabilities in ITER and future burning plasma experiments. Sawtooth dynamics and its interaction with broadband plasma turbulence has been a challenge for predictive simulations of core transport in future fusion devices. This study provides new observations of core turbulence behavior during sawtooth oscillations in DIII-D hydrogen L-mode neutral beam injection heated plasmas in an inner wall limited configuration. A strong correlation of electron temperature and density turbulence levels with the sawtooth oscillation phase has been observed at locations inside the Te inversion radius and/or safety factor q=1 magnetic surface. The Te turbulence amplitude in the core during the sawtooth ramp exhibits a critical Te gradient behavior inside but not near the Te inversion radius/q=1 magnetic surface. The most unstable mode calculated from the trapped gyro-landau fluid (TGLF) turbulence simulations reveal a change from low-k ion-type to low-k electron-type modes from pre- to post- sawtooth crash time periods.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 5","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140686878","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-18DOI: 10.1088/1741-4326/ad4047
K. McCarthy, I. García-Cortés, Arturo Alonso, Ana Arias-Camisón, E. Ascasíbar, A. Baciero, A. Cappa, Ricardo Carrasco, O. Chmyga, Teresa Estrada, Raul García, J. Hernández Sánchez, Francisco Javier Hernanz, O. Kozachok, Belén López-Miranda, F. Medina, Daniel Medina Roque, B. V. Van Milligen, Miguel Navarro, M. Ochando, J. D. de Pablos, N. Panadero, Ignacio Pastor, Jaime de la Riva Villen, Ma. Carmen Rodriguez Fernandez, D. Tafalla, V. Tribaldos
{"title":"Multi-pellet injection into the NBI-heated phase of TJ-II plasmas","authors":"K. McCarthy, I. García-Cortés, Arturo Alonso, Ana Arias-Camisón, E. Ascasíbar, A. Baciero, A. Cappa, Ricardo Carrasco, O. Chmyga, Teresa Estrada, Raul García, J. Hernández Sánchez, Francisco Javier Hernanz, O. Kozachok, Belén López-Miranda, F. Medina, Daniel Medina Roque, B. V. Van Milligen, Miguel Navarro, M. Ochando, J. D. de Pablos, N. Panadero, Ignacio Pastor, Jaime de la Riva Villen, Ma. Carmen Rodriguez Fernandez, D. Tafalla, V. Tribaldos","doi":"10.1088/1741-4326/ad4047","DOIUrl":"https://doi.org/10.1088/1741-4326/ad4047","url":null,"abstract":"\u0000 A pellet-induced enhanced confinement (PiEC) phase, with general characteristics similar to those reported for the stellarator W7-X, is observed after single pellet injection (>1019 H atoms) into the neutral beam injection heated phase of plasmas in the mid-sized heliac-type stellarator TJ-II. In addition to a step-like increase in density, plasma diamagnetic energy content rises significantly with respect to that of reference discharges, energy confinement time is similarly enhanced when compared to International Stellarator Scaling law predictions (H. Yamada et al., Nucl. Fusion 45 (2005) 1684) renormalized for TJ-II, and the triple product, ne · Ti · E, exhibits a clear bifurcation towards an improved confinement branch when compared to the branch product predicted by the same law. In this work, multiple pellets are injected in series into NBI-heated plasmas in the TJ-II and post-injection plasma performance is reported and discussed. For instance, a charge-exchange recombination spectroscopy diagnostic reveals significantly increased core ion temperatures after pellet injection compared to temperatures achieved in comparable reference plasmas, this pointing to increased ion energy content and improved ion energy confinement during a PiEC phase. It is also found that enhanced performance is independent of whether co- or counter-NBI heating beam is employed. Finally, record stored diamagnetic energy content and plasma beta values are achieved when the largest available pellets are employed. The results indicate that pellet injections extend the operational regime well beyond limits previously achieved in TJ-II without pellets.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 4","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140685975","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-18DOI: 10.1088/1741-4326/ad4048
Lunan Liu, Xinjun Zhang, Chengming Qin, Y. Mao, Shuai Yuan, Wei Zhang, Hua Yang, Lei Wang, Yan Cheng, Kai Zhang
{"title":"Design and operations of a load-tolerant ICRH system in Experimental Advanced Superconducting Tokamak","authors":"Lunan Liu, Xinjun Zhang, Chengming Qin, Y. Mao, Shuai Yuan, Wei Zhang, Hua Yang, Lei Wang, Yan Cheng, Kai Zhang","doi":"10.1088/1741-4326/ad4048","DOIUrl":"https://doi.org/10.1088/1741-4326/ad4048","url":null,"abstract":"\u0000 Ion cyclotron resonance heating (ICRH) has been a dependable tool for sturdy plasma heating with high RF power of several megawatts. However, a sudden increase in the reflected power during ICRH heating experiments is a problem that should be solved for future fusion experimental devices. To solve this issue, the load tolerant matching network have been designed for ICRH system in EAST Tokamak. The matching network includes 3-stub tuner impedance matching system, conjugate-T structure, 30 Ω to 50 Ω transmission line and center grounded antenna strap. By keeping a low reflection ratio in the network for a wide range of resistance, this matching network could allow sturdy high-power operations without fast impedance matching in EAST tokamak. In our matching network, the two arms of a conjugate-T were designed to have λ/2 length difference which could mitigate current imbalance and antenna poloidal phasing out of control problem. And the T-point corresponds to the maximum point of standing wave voltage, which could greatly improve the input impedance of antenna.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 38","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140689266","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-17DOI: 10.1088/1741-4326/ad3fca
V. Zamkovska, S. Sabbagh, Matthew Tobin, J. Berkery, J. Riquezes, Young-Seok Park, Keith Erickson, Jalal Butt, J. Bak, Jayhyun Kim, Kyu-Dong Lee, Jinseok Ko, Si-Woo Yoon, C. Ham, Lucy Kogan
{"title":"DECAF Cross-device characterization of tokamak disruptions indicated by abnormalities in plasma vertical position and current","authors":"V. Zamkovska, S. Sabbagh, Matthew Tobin, J. Berkery, J. Riquezes, Young-Seok Park, Keith Erickson, Jalal Butt, J. Bak, Jayhyun Kim, Kyu-Dong Lee, Jinseok Ko, Si-Woo Yoon, C. Ham, Lucy Kogan","doi":"10.1088/1741-4326/ad3fca","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3fca","url":null,"abstract":"\u0000 Abnormal (deviating from target) variations in the plasma vertical position Z and current Ip (such as vertical displacements, transient Ip 'spikes' and quenches) constitute common elements of a disruption, a phenomenon that is to be mitigated, or ultimately avoided in future reactor-relevant tokamaks. While those abnormalities are generally recognized cross-shot and cross-device, details in terms of appearance (or not) and order of those abnormalities in disruption event chains is bound with the plasma state at the time of the chain initiation. Detection of those abnormalities is thus indicative not only of the onset of the plasma collapse itself, but also of the disruption driving cause that is promoted at the particular plasma state. Here, occurrence of disruptions, explored via detection of a Ip quench, and analysis of disruption event chains constituted by Ip and Z abnormalities, is reported for in total 7 full years of operation of 3 devices (KSTAR, MAST-U and NSTX-U) using the DECAFTM code expanded tools and capabilities. It is shown that the disruption occurrence depends not only on details of the plasma state, but also on (device-dependent) technical elements of the shot exit scenario. A year-to-year change in main disruption causes and a reduction of the disruptivity rate, bound with device and operation upgrades, are reported. Particular trigger instances of disruption event chains (and the full chains, when applicable) are shown to occupy different parts of the operation space diagrams, in accordance with prior expectation. Plasma elongation is identified as an important factor influencing details of the chains and its role will be further explored.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 40","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140691330","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"A two-layer single shell magnetized target for lessening the Nernst effect","authors":"Shijia Chen, Fuyuan Wu, Hua Zhang, Cangtao Zhou, Yan-Yun Ma, Rafael Ramis","doi":"10.1088/1741-4326/ad3fcc","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3fcc","url":null,"abstract":"\u0000 Fuel magnetization significantly lowers the required radial convergence enabling cylindrical implosions to become an promising approach for inertial confinement fusion (ICF). Nernst effect on the two-layer single shell magnetized target design applied to Z-pinch benefits from a gold layer that decreases fuel demagnetization and serves as a magnetothermal insulation layer, preventing magnetothermal losses. The resistive diffusion and Nernst advection of the magnetic field are considered in the radiation magnetohydrodynamic (RMHD) model, which alter the evolution of magnetic flux in the magnetized target and result in plasma demagnetization. The results demonstrate that targets with a wide range of parameters can achieve ignition condition under a 30 MA driven current. A two-layer single shell magnetized target for lessening the Nernst effect has the potential to achieve ignition condition. The fusion yield of the optimal target increases by 168% from 0.71 MJ to 1.90 MJ, compared to a one-layer single shell target.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 11","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140692547","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-17DOI: 10.1088/1741-4326/ad3fcd
L. Piron, C. Paz-Soldan, L. Pigatto, P. Zanca, Olivier Sauter, T. Pütterich, Paolo Bettini, M. Bonotto, Geoffrey Cunningham, Gianmaria De Tommasi, Nicolò Ferron, Matteo Gambrioli, Georgina Graham, Peter C de Vries, Y. Gribov, Q. Hu, K. Kirov, N. Logan, Morten Lennholm, Massimiliano Mattei, Marc Maraschek, Tomas Markovic, G. Manduchi, Piero Martin, A. Pironti, A. Polevoi, T. Ravensbergen, David Anthony Ryan, B. Sieglin, W. Suttrop, D. Terranova, M. Teschke, Daniel F. Valcarcel, Charles Vincent
{"title":"Error field detection and correction studies towards ITER operation","authors":"L. Piron, C. Paz-Soldan, L. Pigatto, P. Zanca, Olivier Sauter, T. Pütterich, Paolo Bettini, M. Bonotto, Geoffrey Cunningham, Gianmaria De Tommasi, Nicolò Ferron, Matteo Gambrioli, Georgina Graham, Peter C de Vries, Y. Gribov, Q. Hu, K. Kirov, N. Logan, Morten Lennholm, Massimiliano Mattei, Marc Maraschek, Tomas Markovic, G. Manduchi, Piero Martin, A. Pironti, A. Polevoi, T. Ravensbergen, David Anthony Ryan, B. Sieglin, W. Suttrop, D. Terranova, M. Teschke, Daniel F. Valcarcel, Charles Vincent","doi":"10.1088/1741-4326/ad3fcd","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3fcd","url":null,"abstract":"\u0000 In magnetic fusion devices, error field sources, spurious magnetic field perturbations, need to be identified and corrected for safe and stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out to test the portability of the novel non-disruptive method, designed and tested in DIII-D (Paz-Soldan C. et al, Nuclear Fusion 62 (2022) 126007), and to perform an assessment of model-based EF control strategies towards their applicability in ITER. In this paper, the lessons learned, the physical mechanism behind the magnetic island healing, which relies on enhanced viscous torque that acts against the static electro-magnetic torque, and the main control achievements are reported, together with the first design of the asynchronous EF correction current/density controller for ITER.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"119 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140693567","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-16DOI: 10.1088/1741-4326/ad3f2f
Donguk Kim, Sangjin Park, G. Choi, Y. W. Cho, Jisung Kang, Hyunsun Han, Jeff Candy, E. Belli, Y. Na, T. Hahm, C. Sung
{"title":"Investigation of fast ion effects on core turbulence in FIRE mode plasmas","authors":"Donguk Kim, Sangjin Park, G. Choi, Y. W. Cho, Jisung Kang, Hyunsun Han, Jeff Candy, E. Belli, Y. Na, T. Hahm, C. Sung","doi":"10.1088/1741-4326/ad3f2f","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3f2f","url":null,"abstract":"\u0000 Further investigation of fast ion effects on turbulence and transport in the FIRE mode discharge [H. Han et al, Nature\u0000 609 269–275 (2022)] was performed in this work as a continuation of a previous study [D. Kim et al Nucl. Fusion\u0000 63 124001 (2023)] that showed that the dominant turbulence suppression mechanism by fast ions is the dilution effect in the FIRE mode discharge. The current study includes (i) the impact of the fast ion relevant mode observed in the simulation of thermal energy flux, (ii) dilution effects by fast ions compared to dilution effects by other species, and (iii) fast ion effects on electron-scale turbulence. First, nonlinear gyrokinetic simulation results show that turbulence is significantly suppressed even without the fast ion relevant mode, indicating that the impact of this mode on thermal transport is not significant in this discharge. Second, further analysis on the dilution effects shows the three following results: Turbulence is not completely suppressed by the reduced main ion density fraction effect due to impurities; the reduction in energy flux can be limited by a certain impurity mode that is destabilized by a high impurity density gradient from adjusting the main ion density gradient; electrons can contribute to turbulence suppression through the main ion density gradient change, although this effect is less significant compared to other species. Third, we observe that two fast ion effects can influence the linear growth rate of the electron-scale turbulence mode. The growth rate decreases by an increase in β*(≡(-8π/B2)dp/dr) and increases by dilution effects, suggesting that fast ion effects on electron-scale turbulence can differ depending on the operation scenario, such as the fast ion fraction. The comprehensive analysis performed in this study can enhance our understanding of fast ion physics, required for burning plasma operation in the future.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"357 2‐3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140698279","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-16DOI: 10.1088/1741-4326/ad3f2d
F. Kin, S. Inagaki, K. Nagasaki, M. Luo, K. Itoh, K. Shinohara, A. Terakado, T. Minami, S. Kado, Shinji Kobayashi, S. Ohshima, T. Bando, N. Oyama, M. Yoshida
{"title":"Observation of avalanche-like transport in Heliotron J and JT-60U plasmas","authors":"F. Kin, S. Inagaki, K. Nagasaki, M. Luo, K. Itoh, K. Shinohara, A. Terakado, T. Minami, S. Kado, Shinji Kobayashi, S. Ohshima, T. Bando, N. Oyama, M. Yoshida","doi":"10.1088/1741-4326/ad3f2d","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3f2d","url":null,"abstract":"\u0000 The avalanche type of transport can induce a long-radial transport and thus can contribute to the global profile formation. In this study, we observed the heat perturbations exhibiting avalanche-like transport in the stellarator/heliotron device, Heliotron J, and the tokamak device, JT-60U. We found that the electron heat propagation in Heliotron J is mainly generated from the heating source region. The relatively high value of the Hurst exponent, which is a signature of avalanches, depends on the total heating power. On the other hand, the electron and ion heat avalanches measured in JT-60U tend to spread from the local peak of the temperature gradient and are not influenced by the heating source profiles. The contrasting features of avalanches in stellarator/heliotrons and tokamaks potentially imply the difference in the temperature profile formation, such as the presence of stiffness.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"106 10","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140695168","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-16DOI: 10.1088/1741-4326/ad3f30
A. Wingen, R. S. Wilcox, B. C. Lyons, L. Baylor, N. Ferraro
{"title":"Prediction of pellet mass thresholds for ELM triggering in low-collisionality, ITER-like discharges","authors":"A. Wingen, R. S. Wilcox, B. C. Lyons, L. Baylor, N. Ferraro","doi":"10.1088/1741-4326/ad3f30","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3f30","url":null,"abstract":"\u0000 In ITER, pellets are calculated to require more than 8 times the mass than currently planned to reliably trigger ELMs. Unmitigated heat flux impulses from edge-localized modes (ELMs) are intolerable in ITER at full power and current. Therefore, ITER operation relies on multiple approaches to control ELM heat fluxes. One method is pellet ELM pacing to instigate small rapid ELMs with low heat flux. Predicting the performance of pellet pacing is critical for ITER, which is expected to operate in a regime with a low-collisionality, peeling-limited pedestal. However, to trigger ELMs the local pressure increase in the expanding pellet cloud pushes the equilibrium over the ballooning stability limit. In this work, linear and nonlinear M3D-C1 simulations are used to predict pellet mass thresholds in DIII-D discharges and ITER scenarios with peeling-limited pedestals. It is found that the distance of the equilibrium's operational point from the ballooning branch of the pedestal stability boundary strongly changes thresholds. Linear M3D-C1 simulations find a strong dependence of the pellet mass threshold on the poloidal injection location for ITER's 15 MA, Q=10 scenario. The required pellet mass at the planned injection locations is 8 to 17 times larger than currently considered. However, such linear simulations do not include pellet ablation physics or time evolution of density and temperature. A new scheme of 2D nonlinear simulations, coupled with linear stability analysis at various steps throughout the nonlinear time evolution, was developed to include such physics and improve on the linear results. These new nonlinear-to-linear simulations confirm previous findings. This result suggests that pellet ELM triggering in ITER could require pellets much larger than those currently planned, which makes ELM-pacing operationally challenging. On the other hand, fueling pellets injected from the high-field side will likely not unintentionally trigger ELMs in an otherwise ELM-stable plasma.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"56 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140695582","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Nuclear FusionPub Date : 2024-04-16DOI: 10.1088/1741-4326/ad3f2e
M. Kobayashi, Sachiko Yoshihashi, Kunihiro Ogawa, Mitsutaka Isobe, Tsukasa Aso, Masanori Hara, S. Sangaroon, S. Tamaki, I. Murata, S. Toyama, M. Miwa, S. Matsuyama, Masaki Osakabe
{"title":"Simultaneous measurements for fast neutron flux and tritium production rate using pulse shape discrimination and single crystal CVD diamond detector","authors":"M. Kobayashi, Sachiko Yoshihashi, Kunihiro Ogawa, Mitsutaka Isobe, Tsukasa Aso, Masanori Hara, S. Sangaroon, S. Tamaki, I. Murata, S. Toyama, M. Miwa, S. Matsuyama, Masaki Osakabe","doi":"10.1088/1741-4326/ad3f2e","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3f2e","url":null,"abstract":"\u0000 This paper presents the development of a simultaneous measurement method for fast neutron energy spectra and tritium production rates within mixed radiation fields using a single crystal Chemical Vapor Deposition (CVD) diamond detector (SDD) combined with a lithium fluoride (LiF) foil. The method involves the separation of pulses with rectangular shapes and the determination of the depth position within the single crystal diamond (SCD) struck by fast neutrons or nuclear reaction products including recoil tritons from the LiF foil based on pulse width, extracting pulse events occurred at the specific bulk region and the surface region of the SCD. Subsequently, unfolding techniques were employed to analyse the energy deposition spectrum of pulses at the specific bulk region which are induced only by fast neutrons, allowing the deduction of the fast neutron energy spectrum. To evaluate the tritium production rate, the energy deposition spectrum of pulses from events occurring at the SCD surface facing the LiF foil was analysed. By estimating the energy deposition spectrum solely induced by fast neutrons striking the SCD surface and subtracting it from the energy deposition spectrum of events at the SCD surface, the contribution of energetic ions, such as recoil tritons generated by the 6Li(n,α)3H reaction in the LiF foil, was determined. The fast neutron flux and tritium production rate obtained through this study were consistent with particle transport calculations, demonstrating the successful development of a method suitable for performance testing of fusion reactor blankets.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"71 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140695438","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}