S. D. Lidzhigoriaev, D.A. Burmistrov, V. V. Gavrilov, I. M. Poznyak, A. V. Pushina, D. A. Toporkov
{"title":"Study of the Thermal Impact of Powerful Plasma Flows on the Surface of a Tungsten Target Using Infrared Pyrometry","authors":"S. D. Lidzhigoriaev, D.A. Burmistrov, V. V. Gavrilov, I. M. Poznyak, A. V. Pushina, D. A. Toporkov","doi":"10.1134/S1063778824130180","DOIUrl":"10.1134/S1063778824130180","url":null,"abstract":"<p>The research investigated the thermal effects of powerful (800–1000 J/cm<sup>2</sup>, 10–15 µs) hydrogen plasma flows on a tungsten target. Measurements were conducted using a developed fast infrared three-wavelength pyrometer within the material temperature range of 270–5800 K and a time resolution of 0.1 µs. It was demonstrated that the surface temperature of the irradiated target reached the boiling point of tungsten (≈5800 K) during the exposure. Using numerical methods, the thermal power absorbed by the target <i>q</i>(<i>t</i>) was determined. The energy density absorbed by the target (≈35 J/cm<sup>2</sup>) obtained by integrating <i>q</i>(<i>t</i>) coincides with the value measured by a thermocouple calorimeter.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S140 - S146"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108912","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Conditioning of the Tokamak Vacuum Chamber with Reactor Technologies","authors":"A. S. Voronov, G. G. Gladush, A. V. Rudov","doi":"10.1134/S1063778824130295","DOIUrl":"10.1134/S1063778824130295","url":null,"abstract":"<p>The article describes a method of conditioning the plasma-facing surfaces of a vacuum chamber. Efficient conditioning of surfaces is an important aspect for achieving maximum plasma parameters and minimizing the number of discharge failures. A simple method of conditioning is to heat the chamber to the required temperatures. For example, in order to remove water from the surface and desorb hydrogen and deuterium from carbon-containing structures, the chamber in tokamaks is heated to temperatures of 150–400°C. However, for the Tokamak with Reactor Technologies (TRT) with a superconducting electromagnetic system, this method of conditioning has certain limitations. In order to reduce the heat fluxes to the coils of the electromagnetic system, cooled screens are placed around the vacuum chamber and nozzles, which reduce the heat fluxes by 100 times; therefore, conditioning of the vacuum chamber of the TRT by means of a glow discharge becomes preferable. The modes of glow discharge in helium and hydrogen are investigated, and their optimal conditions are determined (<i>P</i> ~ 4 mTorr, <i>I</i> = 12 A). The process of chamber cleaning is most effective in the glow H<sub>2</sub> discharge at chamber surface temperatures <i>T</i> < 100°C, which can be confirmed by mass spectrometric and Auger measurements.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S173 - S180"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108959","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
L. B. Begrambekov, A. A. Airapetov, A. V. Grunin, S. S. Dovganyuk, Ya. A. Sadovsky
{"title":"Boron Carbide as a Protective Material for Plasma-Facing Elements of Plasma and Thermonuclear Facilities","authors":"L. B. Begrambekov, A. A. Airapetov, A. V. Grunin, S. S. Dovganyuk, Ya. A. Sadovsky","doi":"10.1134/S1063778824130027","DOIUrl":"10.1134/S1063778824130027","url":null,"abstract":"<p>The properties of boron carbide and its coating, which seem important for the plasma-facing material in thermonuclear facilities, are presented. The basic steps for boron carbide (B<sub>4</sub>C) coating using carborane (C<sub>2</sub>B<sub>10</sub>H<sub>12</sub>) as the initial material are reported. It has been shown that is not susceptible to “chemical sputtering.” The sputtering rate of B<sub>4</sub>C is 3–4 times and the emission of carbon atoms is 15–20 times less than that of graphite and changes slightly up to 1500 K. Trapping of hydrogen isotope ions into the B<sub>4</sub>C coating tends to saturation at irradiation doses of about 7 × 10<sup>23</sup> at/m<sup>2</sup>. A method for low-temperature “detritization” of the coating is proposed. Conditioning the coating by irradiating it with hydrogen ions with an energy of 50 eV left ≈8% of the introduced deuterium ions in it. The results of several cycles of thermal cycling of coatings are presented. In particular, a B<sub>4</sub>C coating with a thickness of 5 µm on tungsten up to 2000 K retained the composition B:C ≈ 3.8:1, melted in the range of 2500–3670 K, and changed the composition to B : C ≈ 1.2:1, but remained continuous, without peeling. The results of improvement of plasma parameters after deposition of a boron carbide coating on the first wall of the T-11M tokamak and in the PISCES-B facility are presented. The coating deposition rate reached 30 nm/s. The possibility of plasma-chemical conversion into gas and removal of boron carbide erosion products from facilities is reported.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S60 - S69"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109083","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
I. M. Poznyak, I. A. Aliabev, V. L. Podkovyrov, V. A. Barsuk, V. Yu. Tsybenko, E. Z. Biryulin, E. D. Fedulaev, Z. I. Novoselova
{"title":"Behavior of Tungsten Coated with Boron Carbide Exposed to Intense Plasma Streams","authors":"I. M. Poznyak, I. A. Aliabev, V. L. Podkovyrov, V. A. Barsuk, V. Yu. Tsybenko, E. Z. Biryulin, E. D. Fedulaev, Z. I. Novoselova","doi":"10.1134/S106377882413009X","DOIUrl":"10.1134/S106377882413009X","url":null,"abstract":"<p>To date, the possibility of using a fully tungsten coating of the first wall is being discussed within the ITER project. As a result, the key objectives of the project may not be achieved. Tungsten coatings with boron carbide B<sub>4</sub>C having a thickness of no more than 50 µm are considered as one of the possible solutions. This paper describes the results of testing samples of tungsten coated with boron carbide under the action of an intense deuterium plasma stream at the QSPA-T plasma gun. The heat load on the samples reached <i>w</i><sub><i>e</i></sub> = 1.4 GW/m<sup>2</sup> at a pulse duration of 1 ms. During plasma experiments, brittle destruction of boron carbide due to material cracking is observed. This process is accompanied by chipping of the pieces of the coating. Surface swelling is observed for the sample obtained by detonation spraying. Subsequent plasma exposure leads to B<sub>4</sub>C destruction and erosion crater formation in places of swelling. Therefore, even at a lower thermal load (1.1 GW/m<sup>2</sup> instead of 1.4 GW/m<sup>2</sup>), the B<sub>4</sub>C layer deposited on tungsten by detonation spraying erodes more strongly than the B<sub>4</sub>C layer deposited by atmospheric plasma spraying.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S108 - S117"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109027","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
P. Yu. Piskarev, I. V. Mazul, A. N. Makhankov, M. S. Kolesnik, E. V. Okuneva, N. V. Litunovsky
{"title":"Plasma-Facing Components in the TRT Project: A Design, Materials, and Technologies","authors":"P. Yu. Piskarev, I. V. Mazul, A. N. Makhankov, M. S. Kolesnik, E. V. Okuneva, N. V. Litunovsky","doi":"10.1134/S1063778824130064","DOIUrl":"10.1134/S1063778824130064","url":null,"abstract":"<p>The paper discusses the main issues that are resolved when designing plasma-facing components in the TRT project—this is the clarification of the functionality of various components, their arrangement in the vacuum vessel and design, and choice of materials of a high-heat flux multilayer structure and technologies for creating such a structure. The choice of armour material is the key issue, since not only the engineering parameters of the components but also the plasma parameters depend on the decision. The design and materials of the advanced cooling heat-sink structure must ensure long-term and reliable operation of the component at peak heat flux in specified environmental conditions. At the same time, taking into account the complexity and duration of construction, commissioning, and achievement of project parameters for any large-scale tokamak such as the TRT, it is reasonable to use a stepwise approach to equipping the tokamak with plasma-facing components with different materials and designs.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S48 - S59"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109081","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. A. Pisarev, A. V. Vertkov, M. Yu. Zharkov, I. V. Mazul, P. Yu. Piskarev, G. M. Tarasyuk
{"title":"Flowing Liquid Lithium as a Plasma Facing Material","authors":"A. A. Pisarev, A. V. Vertkov, M. Yu. Zharkov, I. V. Mazul, P. Yu. Piskarev, G. M. Tarasyuk","doi":"10.1134/S1063778824130052","DOIUrl":"10.1134/S1063778824130052","url":null,"abstract":"<p>The paper provides a brief overview of research activity related to the use of the flowing liquid lithium as a plasma facing material of the limiter and divertor in tokamaks. A substantiation for a system with liquid lithium, possible variants of such systems, demonstration of positive test results, prospects for using in other tokamaks, related research, and open questions are considered.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S26 - S36"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108068","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
O. I. Obrezkov, Yu. V. Martynenko, M. Yu. Nagel, O. L. Shutev, S. L. Shevchuk, Yu. I. Rukina, V. E. Misnikov, S. N. Kochetov, M. A. Bazhin, D. I. Minaev, A. B. Mishenko, T. V. Churina
{"title":"Methods and Results of Electrochemical Investigation of the Relief of Films Deposited by Magnetron Sputtering","authors":"O. I. Obrezkov, Yu. V. Martynenko, M. Yu. Nagel, O. L. Shutev, S. L. Shevchuk, Yu. I. Rukina, V. E. Misnikov, S. N. Kochetov, M. A. Bazhin, D. I. Minaev, A. B. Mishenko, T. V. Churina","doi":"10.1134/S1063778824130192","DOIUrl":"10.1134/S1063778824130192","url":null,"abstract":"<p>Sputtering modes strongly affect the properties of the deposited films, which are important not only in thermonuclear installations but also in numerous applications. A method is proposed for comparing the development of the relief of coatings deposited in different modes by measuring the characteristics of a double electric layer in an electrochemical cell, taking into account nonlinear effects. The influence of magnetron sputtering and deposition parameters (gas pressure, thickness, presence of a diaphragm that hinders pumping) on the relief of the coating is under investigation. The following parameters were measured: capacitance and impedance of the double electric layer, energy transfer efficiency, specific surface area.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S241 - S251"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109186","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
E. P. Velikhov, M. V. Kovalchuk, I. O. Anashkin, V. F. Andreev, G. M. Asadulin, E. R. Akhmedov, A. Yu. Balashov, R. A. Begishev, A. M. Belov, I. S. Belbas, E. N. Bondarchuk, A. A. Borshchegovsky, V. A. Vershkov, A. V. Gorbunov, A. V. Gorshkov, S. A. Grashin, A. V. Gromova, D. E. Dias Mikhailova, M. M. Dremin, A. S. Drozd, A. F. Dubinitsky, I. A. Zemtsov, V. I. Ilgisonis, I. S. Ilyin, A. V. Karpov, A. G. Kachkin, N. A. Kirneva, D. A. Kislov, V. A. Kochin, V. A. Krupin, L. K. Kuznetsova, I. V. Levin, P. D. Lisovoy, A. V. Lutchenko, Yu. V. Matveev, M. V. Mashunkin, A. B. Mineev, A. L. Modyaev, N. A. Mustafin, T. B. Myalton, A. R. Nemets, A. V. Nikolaev, V. N. Novikov, G. E. Notkin, M. R. Nurgaliev, I. S. Obraztsov, D. S. Panfilov, I. S. Pimenov, K. A. Rogozin, I. N. Roy, A. N. Romannikov, D. V. Ryzhakov, P. V. Savrukhin, D. V. Sarychev, D. S. Sergeev, V. V. Smirnov, N. A. Soloviev, A. V. Stepin, A. V. Sushkov, D. Yu. Sychugov, K. N. Tarasyan, V. I. Tepikin, Yu. I. Tolpegina, D. L. Ulasevich, E. N. Khayrutdinov, A. P. Khvostenko, P. P. Khvostenko, A. I. Chudesnov, A. N. Chudnovskij, D. A. Shelukhin, E. A. Shestakov, the T-15MD tokamak team
{"title":"First Experimental Results on the T-15MD Tokamak","authors":"E. P. Velikhov, M. V. Kovalchuk, I. O. Anashkin, V. F. Andreev, G. M. Asadulin, E. R. Akhmedov, A. Yu. Balashov, R. A. Begishev, A. M. Belov, I. S. Belbas, E. N. Bondarchuk, A. A. Borshchegovsky, V. A. Vershkov, A. V. Gorbunov, A. V. Gorshkov, S. A. Grashin, A. V. Gromova, D. E. Dias Mikhailova, M. M. Dremin, A. S. Drozd, A. F. Dubinitsky, I. A. Zemtsov, V. I. Ilgisonis, I. S. Ilyin, A. V. Karpov, A. G. Kachkin, N. A. Kirneva, D. A. Kislov, V. A. Kochin, V. A. Krupin, L. K. Kuznetsova, I. V. Levin, P. D. Lisovoy, A. V. Lutchenko, Yu. V. Matveev, M. V. Mashunkin, A. B. Mineev, A. L. Modyaev, N. A. Mustafin, T. B. Myalton, A. R. Nemets, A. V. Nikolaev, V. N. Novikov, G. E. Notkin, M. R. Nurgaliev, I. S. Obraztsov, D. S. Panfilov, I. S. Pimenov, K. A. Rogozin, I. N. Roy, A. N. Romannikov, D. V. Ryzhakov, P. V. Savrukhin, D. V. Sarychev, D. S. Sergeev, V. V. Smirnov, N. A. Soloviev, A. V. Stepin, A. V. Sushkov, D. Yu. Sychugov, K. N. Tarasyan, V. I. Tepikin, Yu. I. Tolpegina, D. L. Ulasevich, E. N. Khayrutdinov, A. P. Khvostenko, P. P. Khvostenko, A. I. Chudesnov, A. N. Chudnovskij, D. A. Shelukhin, E. A. Shestakov, the T-15MD tokamak team","doi":"10.1134/S1063778824130283","DOIUrl":"10.1134/S1063778824130283","url":null,"abstract":"<p>The article presents the results of the first experiments on the T-15MD tokamak. Plasma discharges with current up to 250 kA, discharge duration up to 2 s, and plasma electron temperature up to 3 keV have been obtained in the experiments.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S1 - S9"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108826","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
V. Yu. Sergeev, V. G. Skokov, B. V. Kuteev, V. M. Timokhin
{"title":"Closed Lithium Cycle Concept in the DEMO-FNS Tokamak with a Sectioned Divertor","authors":"V. Yu. Sergeev, V. G. Skokov, B. V. Kuteev, V. M. Timokhin","doi":"10.1134/S1063778824130106","DOIUrl":"10.1134/S1063778824130106","url":null,"abstract":"<p>The organization of the plasma–wall interaction remains an urgent problem for long-term operation of a tokamak with an intense thermonuclear fusion reaction. The concept of a lithium cycle and the design of a sectioned divertor for the Demonstration Fusion Neutron Source (DEMO-FNS) tokamak are proposed. The parameters are estimated, and requirements for the components of the lithium cycle are formulated. Technical solutions for the lithium cycle flow rate ≅10 g/s are selected. It is estimated that 0.1-µm liquid lithium layer on the surface of the first wall can protect its solid coating. On the basis of a simple model, it is shown that, at a wall temperature of 200–300°C, a thickness of 0.1 µm can be achieved in ≅1 min. The film can reach quasi-stationary values of 13–15 µm in 3–4 h. Above 340°C, the film does not form because of the increase in the thermal evaporation of lithium. The wall temperature of 700°C of the divertor section with the lithium pool is chosen so that lithium deuteride and lithium tritide do not form in it. They can form in the liquid metal lithium protective layer of the wall at temperatures less than 300°C. In order to significantly reduce the explosion and fire hazard when working with hot liquid lithium, it is proposed to increase the size of the DEMO-FNS divertor section with the lithium pool by 2 to 3 times, which may allow the transition from water to helium coolant.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S37 - S47"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109080","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
P. A. Sdvizhenskii, A. B. Kukushkin, M. G. Levashova, V. E. Zhogolev, V. M. Leonov, V. S. Lisitsa, S. V. Konovalov
{"title":"Assessment of Multiplet Splitting and Line Radiation Imprisonment Effects during Discharge Quenching by Intense Argon Injection in ITER","authors":"P. A. Sdvizhenskii, A. B. Kukushkin, M. G. Levashova, V. E. Zhogolev, V. M. Leonov, V. S. Lisitsa, S. V. Konovalov","doi":"10.1134/S1063778824130209","DOIUrl":"10.1134/S1063778824130209","url":null,"abstract":"<p>One of the conditions of safe operation for the experimental tokamak reactor ITER is the possibility of mitigating disruption instability by massive injection of inert gases, in particular, of argon and neon. Here we present the results of assessing the influence of multiplet splitting and line radiation imprisonment during the discharge quenching by intense argon injection in ITER. In this paper, the fine structure of energy levels and the noncoronal collisional-radiative kinetics for the radiating excited state are used. For the radiation of two argon ions, Ar<sup>+15</sup> and Ar<sup>+3</sup>, which have spectral lines of high intensity and could be used for plasma diagnostics, it is shown that the optical thickness for the ionic strongest lines has no significant effect on the total power losses of plasma radiation in the considered quenching scenario (massive argon injection in the 15 MA, <i>Q</i> ~ 10 basic scenario in ITER, carried out at the quasi-stationary stage of the discharge, flat-top of the current). The most significant effect appears to be the multiplet splitting of atomic levels, which provides an increase in the radiative losses, e.g., by a factor of ~2 for low-ionized atoms at low temperatures, because the resolution of the fine structure of atomic levels for Δ<i>n</i> = 0 transitions leads to a contribution of lower excitation energy than that in the model of multiplet-average radiative transitions.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S233 - S240"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109185","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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