Nuclear Materials and Energy最新文献_第2页

Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-03-01 DOI: 10.1016/j.nme.2025.101899

Q. Tichit , M.H. Aumeunier , Y. Corre , R. Dejarnac , L. Dubus , J. Gaspar , J. Gerardin , A. Grosjean , J.P. Gunn , A. Juven , K. Krieger , A. Podolník , E. Tsitrone

{"title":"Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak","authors":"Q. Tichit , M.H. Aumeunier , Y. Corre , R. Dejarnac , L. Dubus , J. Gaspar , J. Gerardin , A. Grosjean , J.P. Gunn , A. Juven , K. Krieger , A. Podolník , E. Tsitrone","doi":"10.1016/j.nme.2025.101899","DOIUrl":"10.1016/j.nme.2025.101899","url":null,"abstract":"<div><div>The heat load deposited in the toroidal gaps between two tungsten monoblocks remains an open problem to prepare safe and powerful experiments in ITER. An experiment has been carried out on the WEST tokamak aiming to study the power deposition on the toroidal surfaces with various monoblock and heat loading configurations. The very high spatial resolution (0.1 mm/px) infrared camera of WEST has been used to monitor the temperature distribution on the blocks. Few actively cooled ITER-like plasma facing units have been misaligned in the vertical and poloidal direction to maximize the heat loading and temperature on specific block areas. This paper shows the experimental results obtained during high power plasma experiment (4.5 MW injected power) performed with the outer strike line located precisely in the toroidal gap. The experimental IR images exhibit complex pattern with strong signal into the gap (greater than measured on the top surface) and shifted hot spot on the poloidal chamfer of the downstream component featuring poloidal misalignment (where optical hot spot are expected). Thermal and photonic modelling have been used to mimic the infrared thermal scene an try to provide a better understanding of the heat loading on the toroidal edge and on the optical hot spots. The importance of specular reflection is highlighted in the two cases because the reflective facets of the block facing each other.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101899"},"PeriodicalIF":2.3,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143520753","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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High-dose neutron irradiation of beryllium and titanium beryllide: Summary and outlook 铍和铍化钛的高剂量中子辐照：总结与展望

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-03-01 DOI: 10.1016/j.nme.2025.101910

Vladimir Chakin , Rolf Rolli , Hans-Christian Schneider , Ramil Gaisin , Pavel Vladimirov , Michael Klimenkov , Michael Duerrschnabel , Nikolai Zimber , Michael Rieth , Bronislava Gorr , Francisco A. Hernández , Dirk Radloff , Alexander Fedorov , Milan Zmitko , Masaru Nakamichi , Sergey Udartsev

{"title":"High-dose neutron irradiation of beryllium and titanium beryllide: Summary and outlook","authors":"Vladimir Chakin , Rolf Rolli , Hans-Christian Schneider , Ramil Gaisin , Pavel Vladimirov , Michael Klimenkov , Michael Duerrschnabel , Nikolai Zimber , Michael Rieth , Bronislava Gorr , Francisco A. Hernández , Dirk Radloff , Alexander Fedorov , Milan Zmitko , Masaru Nakamichi , Sergey Udartsev","doi":"10.1016/j.nme.2025.101910","DOIUrl":"10.1016/j.nme.2025.101910","url":null,"abstract":"<div><div>The irradiation experiment conducted in the HFR material testing reactor, under conditions simulating the operating environment of the DEMO breeding blanket, along with subsequent post-irradiation examinations (PIEs) of irradiated beryllium-based materials—such as pure beryllium and titanium beryllide—enabled a comparative analysis of their radiation resistance for potential use as neutron multipliers. The PIEs clearly demonstrated the superiority of titanium beryllide over beryllium, particularly in terms of reduced swelling, lower tritium retention, and enhanced mechanical properties at elevated temperatures. As a result, titanium beryllide blocks have been proposed to replace beryllium pebbles in the Helium-Cooled Pebble Bed (HCPB) DEMO breeding blanket design. A production technology for fabricating titanium beryllide blocks was successfully developed, and further advancements in this technology, along with research on full-scale blocks, have been outlined.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101910"},"PeriodicalIF":2.3,"publicationDate":"2025-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143526815","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Atomic determination of the energetics and configurations of N-Cr/Cr-N-C-O and N-Cr/Ni-vacancy complexes in austenitic Fe alloys

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-21 DOI: 10.1016/j.nme.2025.101909

Guofeng Li , Pengbo Zhang , Haichuan Ji , Mingliang Wei , Tingting Zou , Yichao Wang

{"title":"Atomic determination of the energetics and configurations of N-Cr/Cr-N-C-O and N-Cr/Ni-vacancy complexes in austenitic Fe alloys","authors":"Guofeng Li , Pengbo Zhang , Haichuan Ji , Mingliang Wei , Tingting Zou , Yichao Wang","doi":"10.1016/j.nme.2025.101909","DOIUrl":"10.1016/j.nme.2025.101909","url":null,"abstract":"<div><div>The energetics and configurations of small N-Cr/Cr-N-C-O and N-Cr (Ni)-vacancy complexes in austenitic Fe alloys were investigated using a first-principles method. The interaction between N and Cr/vacancy is attractive (0.10/0.59 eV) while Ni/O repels N (−0.21/−0.46 eV). Energetically, interstitial N and Cr can form stable Cr<em><sub>m</sub></em>N<em><sub>n</sub></em> complexes, the binding energy of the clusters increases from 0.24 to 2.07 eV with the size (<em>m</em> = 2–16). The tetrahedral Cr<sub>4</sub>N<sub>4</sub> structure acts as a stable unit to form larger size by connecting N (point to point). The presence of Cr strengthens the stability of VN<em><sub>n</sub></em> clusters energetically while Ni weakens it, the Cr-VN<em><sub>n</sub></em> and VN<em><sub>n</sub></em> (<em>n</em> = 1,2) act as main complex defects. Furthermore, we determined the stabilities of serval Cr-N-O/Cr-N-C-O complexes and found that the synergistic interaction of Cr-N-C-O strongly stabilize the clusters and O impurities, then enhancing mechanical properties. Finally, we predicted the effect of Cr/Ni on N migration and effective diffusivity. These results deepen understanding for the synergistic interactions between interstitial N and alloying elements/vacancies in austenitic stainless steels.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101909"},"PeriodicalIF":2.3,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143488668","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Effect of Am addition on oxygen potential in (U0.55Pu0.3Am0.15)O2−x

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-20 DOI: 10.1016/j.nme.2025.101908

Keisuke Yokoyama , Masashi Watanabe , Akane Usui , Takayuki Seki , Takashi Onishi , Masato Kato

引用次数: 0

Towards improved neutral exhaust in the HSX stellarator

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-20 DOI: 10.1016/j.nme.2025.101874

Dieter Boeyaert , Kelly A. Garcia , Heinke Frerichs , Michael J. Gerard , Aaron Bader , Robert Davies , Benedikt Geiger , John Schmitt , Oliver Schmitz

引用次数: 0

Effects of 14 T high magnetic field on the formation and migration behavior of CLF-1 steel corrosion products

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-18 DOI: 10.1016/j.nme.2025.101906

Shu-Feng Zhang , Yi-Ming Lyu , Lei Peng , Shan-Liang Zheng

{"title":"Effects of 14 T high magnetic field on the formation and migration behavior of CLF-1 steel corrosion products","authors":"Shu-Feng Zhang , Yi-Ming Lyu , Lei Peng , Shan-Liang Zheng","doi":"10.1016/j.nme.2025.101906","DOIUrl":"10.1016/j.nme.2025.101906","url":null,"abstract":"<div><div>The CLF-1 steel, which is a main candidate material of cooling water pipes in fusion reactor blanket being developed in China, is not only corroded by water, but also operates in high magnetic fields. The effect of magnetic field on the corrosion process of CLF-1 steel should be considered. Currently, the corrosion of fusion reactor materials in high magnetic fields at scales of 10 T has not been studied due to the lack of suitable experimental conditions for high magnetic fields. To study the influence of high magnetic fields on the corrosion process of CLF-1 steel, corrosion experiment was carried out using a superconducting steady-state magnet in 1 wt% H<sub>2</sub>O<sub>2</sub> + 0.1 wt% NaCl solution for 2 h with the 14 T high magnetic field. A contrast experiment without the magnetic field was performed. The ANSYS software was used to simulate the distribution of magnetic flux around the sample in a 14 T magnetic field. The morphology of the samples was observed and the composition of corrosion products was analyzed. The number of corrosion pits on the sample surface increases significantly at 14 T magnetic field, and the surface corrosion products around the pits appear approximately circular in shape, while the corrosion products distributing in strip shape on sample corroded without the magnetic field. The simulations show that the maximum magnetic flux density is localized in the middle of the sample, where most of the corrosion pits are distributed. Possible reasons for the influence of the magnetic field on the corrosion process could be that the Lorentz force and magnetic gradient force induced change the motion of ions and paramagnetic substances (such as O<sub>2</sub>) respectively.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101906"},"PeriodicalIF":2.3,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143465042","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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Optimization and evaluation of a water-cooled target probe in linear plasma devices by computational fluid dynamics methods

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-18 DOI: 10.1016/j.nme.2025.101905

Tongzhen Li , Qian Xu , Xin Yang , Fang Ding , Guang-nan Luo , Haishan Zhou

{"title":"Optimization and evaluation of a water-cooled target probe in linear plasma devices by computational fluid dynamics methods","authors":"Tongzhen Li , Qian Xu , Xin Yang , Fang Ding , Guang-nan Luo , Haishan Zhou","doi":"10.1016/j.nme.2025.101905","DOIUrl":"10.1016/j.nme.2025.101905","url":null,"abstract":"<div><div>Effective cooling of the target probe under extreme plasma operational conditions is crucial for ensuring stable and reliable diagnostic measurements. In this study, we designed a water-cooled target probe specifically tailored for deployment in a linear plasma device (LPD). Computational Fluid Dynamics (CFD) methods were employed to evaluate and optimize the cooling performance of the target probe. CFD simulations included different probe base structures and inlet pipe types. The trade-offs between enhanced heat transfer and the associated pressure drop losses for different inlet pipe designs have been comprehensively considered. Simulation results indicated that at a Gaussian heat load of 10 MW/m<sup>2</sup>, which simulates a plasma discharge scenario in the LPD, the maximum temperature of the tungsten probe tip for the optimized target probe was reduced to approximately 723 ℃. Extending the thermal analysis to a future scenario where the target probe is subjected to three adjacent plasma beams, the temperature increase of the tungsten probe tips was not significant. This robust cooling performance highlights the potential of the target probe for application in advanced linear plasma devices that feature multiple or multichannel plasma sources.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101905"},"PeriodicalIF":2.3,"publicationDate":"2025-02-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143474696","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Effects of liquid metal embrittlement on an alumina forming martensitic steel

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-18 DOI: 10.1016/j.nme.2025.101907

Christopher Petersson , Peter Szakalos , Rachel Pettersson , Mats Lundberg

引用次数: 0

Modified sink strength model for dislocation in tungsten: Dependence on temperature and probability density distribution

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-16 DOI: 10.1016/j.nme.2025.101900

Hui-Zhi Ma, Yu-Hao Li, Yu-Ze Niu, Hong-Bo Zhou, Guang-Hong Lu

{"title":"Modified sink strength model for dislocation in tungsten: Dependence on temperature and probability density distribution","authors":"Hui-Zhi Ma, Yu-Hao Li, Yu-Ze Niu, Hong-Bo Zhou, Guang-Hong Lu","doi":"10.1016/j.nme.2025.101900","DOIUrl":"10.1016/j.nme.2025.101900","url":null,"abstract":"<div><div>Sink strength, as a fundamental parameter in mean-field approaches, describes the ability of sinks (e.g., dislocation lines) to capture migrating defects and is crucial for simulating the microstructure evolution of irradiation damage in nuclear materials. Here, taking body centered cubic tungsten (W) as an example, we systematically investigate the sink strength of dislocation lines using the object Kinetic Monte Carlo (OKMC) method. It is found that there are noteworthy discrepancies of sink strength between the traditional theoretical expression and OKMC simulations. This should be attributed to two factors, namely temperature and probability density distribution. The former can be derived from a master curve that has already been proposed for 1D to 3D diffusion–reaction kinetics, while the latter can be well described by a modified analytical expression of sink strength for dislocation lines. By incorporating these factors, the discrepancy between theoretical results and OKMC simulations is eliminated. Notably, the results of defect evolution in irradiated W, obtained using the modified sink strength expression, exhibit a greater consistency with experimental observations than those derived from the conventional model. These results provide a better insight into the sink strength model, and have broad implications for understanding and reproducing the microstructure evolution of irradiation defects in materials.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"42 ","pages":"Article 101900"},"PeriodicalIF":2.3,"publicationDate":"2025-02-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143446038","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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TALIF measurements of atomic deuterium in toroidal divertor simulator NAGDIS-T

IF 2.3 2区物理与天体物理

Nuclear Materials and Energy Pub Date : 2025-02-13 DOI: 10.1016/j.nme.2025.101898

Shin Kajita , Kota Hiraiwa , Hirohiko Tanaka , Ryuki Iwai , Mitsutoshi Aramaki , Ryo Yasuhara , Noriyasu Ohno

引用次数: 0