Acceder

Bibliografías temáticas / Tritium transport / Artículos de revistas

Artículos de revistas sobre el tema "Tritium transport"

Siga este enlace para ver otros tipos de publicaciones sobre el tema: Tritium transport.

Autor: Grafiati

Publicado: 14 de marzo de 2023

Crea una cita precisa en los estilos APA, MLA, Chicago, Harvard y otros

Elija tipo de fuente:

Consulte los 50 mejores artículos de revistas para su investigación sobre el tema "Tritium transport".

Junto a cada fuente en la lista de referencias hay un botón "Agregar a la bibliografía". Pulsa este botón, y generaremos automáticamente la referencia bibliográfica para la obra elegida en el estilo de cita que necesites: APA, MLA, Harvard, Vancouver, Chicago, etc.

También puede descargar el texto completo de la publicación académica en formato pdf y leer en línea su resumen siempre que esté disponible en los metadatos.

Explore artículos de revistas sobre una amplia variedad de disciplinas y organice su bibliografía correctamente.

1

Skelton, R., C. Nowak, X. W. Zhou y R. A. Karnesky. "Tritium segregation to vacancy-type basal dislocation loops in α-Zr from molecular dynamics simulations". Journal of Applied Physics 131, n.º 12 (28 de marzo de 2022): 125103. http://dx.doi.org/10.1063/5.0078048.

Texto completo

Resumen

Tritium interactions with irradiation-induced defects in α-Zr are important for understanding getter performance in tritium-producing burnable absorbed rods. Vacancy-type basal loops are prominent in α-Zr irradiated at high dose rates. As they generate substantial tensile strain fields, such loops can trap tritium atoms. For this reason, vacancy-type basal dislocation loops are potentially important for tritium transport, tritium solubility, and tritide precipitation. We perform molecular dynamics simulations of tritium distributions around vacancy-type basal dislocation loops of different sizes, across a temperature range of 700–1200 K. Tritium preferentially segregates to the dislocation core and, to a lesser extent, the stacking fault. Segregation energies are estimated by inverting the tritium concentration distributions by assuming that the Boltzmann distribution adequately describes partitioning between the bulk and core environments. Agreement between molecular dynamics calculated segregation energies and predictions from elasticity theory using the stress field obtained by spatially averaging the atomic virial stresses suggests that elastic interactions dominate the interaction between tritium and basal loops. We also find an attractive tritium–tritium interaction. This attractive interaction can increase the stability of tritium in the dislocation core, resulting in a higher relative tritium concentration as the overall tritium concentration of the system increases. This suggests that vacancy-type basal dislocation loops can increase tritium solubility in irradiated α-Zr and may serve as preferential sites for tritide precipitation.

Los estilos APA, Harvard, Vancouver, ISO, etc.

2

Zastrow), JET Team (prepared by K. D. "Trace tritium transport in JET". Nuclear Fusion 39, n.º 11Y (noviembre de 1999): 1891–96. http://dx.doi.org/10.1088/0029-5515/39/11y/331.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

3

Freund, Jana, Frederik Arbeiter, Ali Abou-Sena, Fabrizio Franza y Keitaro Kondo. "Tritium transport calculations for the IFMIF Tritium Release Test Module". Fusion Engineering and Design 89, n.º 7-8 (octubre de 2014): 1600–1604. http://dx.doi.org/10.1016/j.fusengdes.2014.06.003.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

4

Gusyev, M. A., M. Toews, U. Morgenstern, M. Stewart, P. White, C. Daughney y J. Hadfield. "Calibration of a transient transport model to tritium data in streams and simulation of groundwater ages in the western Lake Taupo catchment, New Zealand". Hydrology and Earth System Sciences 17, n.º 3 (19 de marzo de 2013): 1217–27. http://dx.doi.org/10.5194/hess-17-1217-2013.

Texto completo

Resumen

Abstract. Here we present a general approach of calibrating transient transport models to tritium concentrations in river waters developed for the MT3DMS/MODFLOW model of the western Lake Taupo catchment, New Zealand. Tritium has a known pulse-shaped input to groundwater systems due to the bomb tritium in the early 1960s and, with its radioactive half-life of 12.32 yr, allows for the determination of the groundwater age. In the transport model, the tritium input (measured in rainfall) passes through the groundwater system, and the simulated tritium concentrations are matched to the measured tritium concentrations in the river and stream outlets for the Waihaha, Whanganui, Whareroa, Kuratau and Omori catchments from 2000–2007. For the Kuratau River, tritium was also measured between 1960 and 1970, which allowed us to fine-tune the transport model for the simulated bomb-peak tritium concentrations. In order to incorporate small surface water features in detail, an 80 m uniform grid cell size was selected in the steady-state MODFLOW model for the model area of 1072 km2. The groundwater flow model was first calibrated to groundwater levels and stream baseflow observations. Then, the transient tritium transport MT3DMS model was matched to the measured tritium concentrations in streams and rivers, which are the natural discharge of the groundwater system. The tritium concentrations in the rivers and streams correspond to the residence time of the water in the groundwater system (groundwater age) and mixing of water with different age. The transport model output showed a good agreement with the measured tritium values. Finally, the tritium-calibrated MT3DMS model is applied to simulate groundwater ages, which are used to obtain groundwater age distributions with mean residence times (MRTs) in streams and rivers for the five catchments. The effect of regional and local hydrogeology on the simulated groundwater ages is investigated by demonstrating groundwater ages at five model cross-sections to better understand MRTs simulated with tritium-calibrated MT3DMS and lumped parameter models.

Los estilos APA, Harvard, Vancouver, ISO, etc.

5

Gusyev, M. A., M. Toews, U. Morgenstern, M. Stewart, C. Daughney y J. Hadfield. "Calibration of a transient transport model to tritium measurements in rivers and streams in the Western Lake Taupo catchment, New Zealand". Hydrology and Earth System Sciences Discussions 9, n.º 8 (24 de agosto de 2012): 9743–65. http://dx.doi.org/10.5194/hessd-9-9743-2012.

Texto completo

Resumen

Abstract. Here we present a general approach of calibrating transient transport models to tritium concentrations in river waters developed for the MT3DMS/MODFLOW model of the Western Lake Taupo catchment, New Zealand. Tritium is a time-dependent tracer with radioactive half-life of 12.32 yr. In the transport model, the tritium input (measured in rain) passes through the groundwater system, and the modelled tritium concentrations are compared to the measured tritium concentrations in the river outlets for the Waihaha, Whanganui, Whareroa, Kuratau and Omori river catchments from 2000–2007. For the Kuratau River, tritium was also measured between 1960 and 1970, which allowed us to fine-tune the transport model. In order to incorporate all surface flows from rivers to small streams, an 80 m uniform grid cell size was selected in the steady-state MODFLOW model for the model area of 1072 km2. The groundwater flow model was first calibrated to groundwater levels and stream flow observations. Then, the transport model was calibrated to the measured tritium concentrations in the river waters. The MT3DMS model results show good agreement with the measured tritium values in all five river catchments. Finally, the calibrated MT3DMS model is applied to simulate groundwater ages that are used to construct groundwater age distributions for the river catchments.

Los estilos APA, Harvard, Vancouver, ISO, etc.

6

Zeng, Qin, Wei Shi, Xiande Wang y Hongli Chen. "Tritium transport analysis for tokamak exhaust processing system of tritium plant". Fusion Engineering and Design 159 (octubre de 2020): 111955. http://dx.doi.org/10.1016/j.fusengdes.2020.111955.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

7

Murphy Jr. (INVITED), C. E. "Modelling Tritium Transport in the Environment". Radiation Protection Dosimetry 16, n.º 1-2 (1 de septiembre de 1986): 51–58. http://dx.doi.org/10.1093/oxfordjournals.rpd.a079713.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

8

Heung, L. K. "Tritium Transport Vessel Using Depleted Uranium". Fusion Technology 28, n.º 3P2 (octubre de 1995): 1385–90. http://dx.doi.org/10.13182/fst95-a30605.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

9

Tam, S. W., J. P. Kopasz y C. E. Johnson. "Tritium transport and retention in SiC". Journal of Nuclear Materials 219 (marzo de 1995): 87–92. http://dx.doi.org/10.1016/0022-3115(94)00392-0.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

10

Ritter, P. D., T. J. Dolan y G. R. Longhurst. "Tritium environmental transport studies at TFTR". Journal of Fusion Energy 12, n.º 1-2 (junio de 1993): 145–48. http://dx.doi.org/10.1007/bf01059370.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

11

Moriyama, H., K. Iwasaki y Y. Ito. "Transport of tritium in liquid lithium". Journal of Nuclear Materials 191-194 (septiembre de 1992): 190–93. http://dx.doi.org/10.1016/s0022-3115(09)80031-7.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

12

Killough, G. G. y D. C. Kocher. "Global environmental transport models for tritium". International Journal of Applied Radiation and Isotopes 36, n.º 7 (julio de 1985): 600. http://dx.doi.org/10.1016/0020-708x(85)90200-5.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

13

Killough, G. G. y D. C. Kocher. "Global Environmental Transport Models for Tritium". Fusion Technology 8, n.º 2P2 (septiembre de 1985): 2569–74. http://dx.doi.org/10.13182/fst85-a24666.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

14

Lee, Sanghoon, Min-Soo Lee, Ju-Chan Lee, Woo-Seok Choi, Ki-Young Kim, Je-Eon Jeon, Ki-Seog Seo, Wataru Shu y Glugla Manfred. "Development of ITER tritium transport package". Fusion Engineering and Design 88, n.º 3 (marzo de 2013): 136–44. http://dx.doi.org/10.1016/j.fusengdes.2013.01.007.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

15

MORIYAMA, H. "Transport of tritium in liquid lithium". Journal of Nuclear Materials 191-194 (septiembre de 1992): 190–93. http://dx.doi.org/10.1016/0022-3115(92)90751-6.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

16

Stauffer, Philip H., Brent D. Newman, Kay H. Birdsell, Marvin O. Gard, Jeffrey M. Heikoop, Emily C. Kluk y Terry A. Miller. "Vadose Zone Transport of Tritium and Nitrate under Ponded Water Conditions". Geosciences 12, n.º 8 (28 de julio de 2022): 294. http://dx.doi.org/10.3390/geosciences12080294.

Texto completo

Resumen

Vadose zone transport of tritium and nitrate can be important considerations at radioactive waste sites, landfills, or areas with industrial impacts. These contaminants are of particular concern because they typically have a relatively higher mobility in the subsurface compared to other compounds. Here, we describe a semiarid site with tritium and nitrate contamination involving a manmade ponded water source above a thick unsaturated zone at Los Alamos National Laboratory in New Mexico, USA. This study demonstrates the value of vadose zone flow and transport modeling for the development of field investigation plans (i.e., identifying optimal borehole locations and depths for contaminant characterization), and how a combination of modeling with isotope and geochemical measurements can provide insight into how tritium and nitrate transport in the vadose zone in semiarid environments. Modeling results suggest that at this location, tritium transport is well predicted by classical multiphase theory. Our work expands the demonstrated usefulness of a standard tritium conceptual model to sites with ponded surface conditions and agrees with previous results where a standard model was able to explain the evolution of a tritium plume at an arid waste disposal site. In addition, depth-based analyses of δ18O and δ2H of pore waters helped confirm the extent of pond infiltration into the vadose zone, and the δ15N of nitrate showed that the contaminant release history of the site was different than originally assumed.

Los estilos APA, Harvard, Vancouver, ISO, etc.

17

Castrovinci, F. M., G. Bongiovì, P. Chiovaro, P. A. Di Maio, F. Franza, A. Quartararo, G. A. Spagnuolo y E. Vallone. "On the modelling of tritium transport phenomena at fluid-structure interfaces". Journal of Physics: Conference Series 2177, n.º 1 (1 de abril de 2022): 012002. http://dx.doi.org/10.1088/1742-6596/2177/1/012002.

Texto completo

Resumen

Abstract One of the main functions of the DEMO Breeding Blanket (BB) system is to ensure the tritium breeding inside the reactor. Tritium is a beta emitter radioactive isotope, subjected to several processes that determine its permeation across materials and its leakage towards the environment, posing potential safety issues in terms of radiological hazard. Thus, the evaluation of tritium inventories inside components and tritium losses towards the environment plays a key role in the fulfilment of the pertinent BB safety requirements. In this regard, a research activity has been carried out, in close cooperation between the University of Palermo and the Karlsruhe Institute of Technology, focussing on the development of a multiphysical model that might realistically simulate 3D tritium transport phenomena across complex fluid-structure interfaces. Models, source terms and boundary conditions assumed for the analyses are herewith reported and critically discussed, together with the main results obtained.

Los estilos APA, Harvard, Vancouver, ISO, etc.

18

Murphy, Charles E. "Tritium Transport and Cycling in the Environment". Health Physics 65, n.º 6 (diciembre de 1993): 683–97. http://dx.doi.org/10.1097/00004032-199312000-00007.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

19

Seungwoo Paek, Min Soo Lee, Kwang-Rag Kim, Do-Hee Ahn, Kyu-Min Song y Soon-Hwan Sohn. "Development of 100-kCi Tritium Transport Vessel". IEEE Transactions on Plasma Science 38, n.º 3 (marzo de 2010): 278–83. http://dx.doi.org/10.1109/tps.2009.2037227.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

20

Zhao, Pinghui, Wanli Yang, Yuanjie Li, Zhihao Ge, Xingchen Nie y Zhongping Gao. "Tritium transport analysis for CFETR WCSB blanket". Fusion Engineering and Design 114 (enero de 2017): 26–32. http://dx.doi.org/10.1016/j.fusengdes.2016.11.009.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

21

Zastrow, K.-D., J. M. Adams, Yu Baranov, P. Belo, L. Bertalot, J. H. Brzozowski, C. D. Challis et al. "Tritium transport experiments on the JET tokamak". Plasma Physics and Controlled Fusion 46, n.º 12B (19 de noviembre de 2004): B255—B265. http://dx.doi.org/10.1088/0741-3335/46/12b/022.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

22

Tam, S. W. y V. Ambrose. "Tritium transport in lithium ceramics porous media". Journal of Nuclear Materials 191-194 (septiembre de 1992): 253–57. http://dx.doi.org/10.1016/s0022-3115(09)80045-7.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

23

Cho, S. "Analysis of tritium transport in irradiated beryllium". Fusion Engineering and Design 28, n.º 1-2 (2 de marzo de 1995): 265–70. http://dx.doi.org/10.1016/0920-3796(94)00087-n.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

24

Cho, Seungyon y Mohamed A. Abdou. "Analysis of tritium transport in irradiated beryllium". Fusion Engineering and Design 28 (marzo de 1995): 265–70. http://dx.doi.org/10.1016/0920-3796(95)90047-0.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

25

Pasler, Volker, Frederik Arbeiter, Christine Klein, Dmitry Klimenko, Georg Schlindwein y Axel von der Weth. "Development of a Component-Level Hydrogen Transport Model with OpenFOAM and Application to Tritium Transport Inside a DEMO HCPB Breeder". Applied Sciences 11, n.º 8 (13 de abril de 2021): 3481. http://dx.doi.org/10.3390/app11083481.

Texto completo

Resumen

This work continues the development of a numerical model to simulate transient tritium transport on the breeder zone (BZ) level for the EU helium-cooled pebble bed (HCPB) concept for DEMO. The basis of the model is the open-source field operation and manipulation framework, OpenFOAM. The key output quantities of the model are the tritium concentration in the purge gas and in the coolant and the tritium inventory inside the BZ structure. New model features are briefly summarized. As a first relevant application a simulation of tritium transport for a single pin out of the KIT HCPB design for DEMO is presented. A variety of scenarios investigates the impact of the permeation regime (diffusion-limited vs. surface-limited), of an additional hydrogen content of 300 Pa H2 in the purge gas, of the released species (HT vs. T2), and of the choice of species-specific rate constants (recombination constant of HT set twice as for H2 and T2). The results indicate that the released species plays a minor role for permeation. Both permeation and inventory show a considerable dependence on a possible hydrogen addition in the purge gas. An enhanced HT recombination constant reduces steel T inventories and, in the diffusion-limited case, also permeation significantly. Scenarios with 80 bar vs. 2 bar purge gas pressure indicate that purge gas volumetric flow is decisive for permeation.

Los estilos APA, Harvard, Vancouver, ISO, etc.

26

Vergari, Lorenzo, Michael Borrello y Raluca O. Scarlat. "Electrochemical Sensors and Techniques for Redox Potential and Tritium Transport in a Neutron-Irradiated Molten Flibe Salt Loop". ECS Meeting Abstracts MA2022-02, n.º 12 (9 de octubre de 2022): 765. http://dx.doi.org/10.1149/ma2022-0212765mtgabs.

Texto completo

Resumen

A consortium of the Massachusetts Institute of Technology, North Carolina State University, the University of California at Berkeley (UCB) and Oak Ridge National Laboratory have initiated a project to build a neutron-irradiated molten-salt forced-circulation loop at the MIT reactor. The loop will use FLiBe (Li2BeF4) salt and will duplicate thermal-hydraulics, chemical, and neutronics conditions in a salt reactor. The SALT Lab at UCB is responsible for the design and application of electrochemical sensors and techniques for redox measurement and tritium transport within the loop. The proposed experiments will investigate redox measurements and control in the loop, tritium retention and diffusion in graphite, and tritium transport in the salt. Redox measurements and control studies will be performed to quantify the corrosive effect of neutron activation reactions and the effect of redox control agents in the loop. Tritium studies are being developed to quantify tritium uptake capacity in graphite, identify tritium desorption mechanisms, and measure tritium solubility, diffusivity, and speciation in the melt. To support these experiments, a variety of electrochemical probes are under development at UCB, including different size, shape, and material of the electrodes. This talk will present the electrochemical probes under development and discuss the experiments that will be tested off-loop in the Be-gloveboxes of the SALT lab and then implemented in the loop.

Los estilos APA, Harvard, Vancouver, ISO, etc.

27

Ye, Ming, Clay Cooper, Jenny Chapman, David Gillespie y Yong Zhang. "A Geologically Based Markov Chain Model for Simulating Tritium Transport With Uncertain Conditions in a Nuclear-Stimulated Natural Gas Reservoir". SPE Reservoir Evaluation & Engineering 12, n.º 06 (2 de septiembre de 2009): 974–84. http://dx.doi.org/10.2118/114920-pa.

Texto completo

Resumen

Summary Nuclear-stimulation technology, which used subsurface nuclear detonation to increase permeability of tight natural gas reservoirs, was evaluated in the late 1960s and early 1970s. The Rulison site, located in the Piceance basin, Colorado, is one of three sites in the US where the technology was tested. An increase in exploration and production for natural gas in the basin has led to a need to quantify the extent of radionuclide (mainly tritium) migration after the detonation and potential migration under likely production scenarios. To meet this need, a numerical model was developed to simulate gas flow and tritium transport toward a hypothetical production well. A crucial problem in the model development is that limited on-site data are too sparse to quantify uncertainty of subsurface properties. This problem is partly resolved by using indirect data and information, such as parameter measurements from a nearby site and geological information regarding lithofacies geometry. In particular, a geologically based Markov chain model was developed to simulate spatial distribution of the sandstone lithofacies. This paper presents an application of the numerical model for simulating tritium transport from the nuclear chimney toward the production well at a likely location producing at a rate typical for the basin. The results show that under the circumstances considered in this paper, tritium will not reach the production well with a confidence level of 95%. The results also show that the lithofacies structure is more critical in controlling tritium transport than parameters of the sandstone and hydraulically fractured sandstone. The parameters become important only when the connectivity of sandstone lenses exists to support tritium transport from the chimney to the production well. The developed modeling framework can be updated as additional subsurface data are collected. The framework can be used to support establishment of drilling restrictions that protect public health and the environment for different production well scenarios.

Los estilos APA, Harvard, Vancouver, ISO, etc.

28

Burn, C. R. y F. A. Michel. "Evidence for recent temperature-induced water migration into permafrost from the tritium content of ground ice near Mayo, Yukon Territory, Canada". Canadian Journal of Earth Sciences 25, n.º 6 (1 de junio de 1988): 909–15. http://dx.doi.org/10.1139/e88-087.

Texto completo

Resumen

Determinations of the tritium (3H) content of ground ice collected near Mayo, Yukon Territory, indicate that since the mid-1950s atmospheric water has infiltrated permafrost to depths of up to 50 cm. The rate of tritium infiltration into permafrost at two plots irrigated with tritiated water in 1983 suggests that tritium movement is principally due to temperature-induced mass transport rather than molecular diffusion.

Los estilos APA, Harvard, Vancouver, ISO, etc.

29

Li, Ruyan, Xiaoyu Wang, Long Zhang y Jun Wang. "Development of tritium dynamic transport analysis tool for tritium breeding blanket system using Modelica". Fusion Engineering and Design 161 (diciembre de 2020): 112023. http://dx.doi.org/10.1016/j.fusengdes.2020.112023.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

30

Gusyev, M. A., D. Abrams, M. W. Toews, U. Morgenstern y M. K. Stewart. "A comparison of particle-tracking and solute transport methods for simulation of tritium concentrations and groundwater transit times in river water". Hydrology and Earth System Sciences 18, n.º 8 (20 de agosto de 2014): 3109–19. http://dx.doi.org/10.5194/hess-18-3109-2014.

Texto completo

Resumen

Abstract. The purpose of this study is to simulate tritium concentrations and groundwater transit times in river water with particle-tracking (MODPATH) and compare them to solute transport (MT3DMS) simulations. Tritium measurements in river water are valuable for the calibration of particle-tracking and solute transport models as well as for understanding of watershed storage dynamics. In a previous study, we simulated tritium concentrations in river water of the western Lake Taupo catchment (WLTC) using a MODFLOW-MT3DMS model (Gusyev et al., 2013). The model was calibrated to measured tritium in river water at baseflows of the Waihaha, Whanganui, Whareroa, Kuratau, and Omori river catchments of the WLTC. Following from that work we now utilized the same MODFLOW model for the WLTC to calculate the pathways of groundwater particles (and their corresponding tritium concentrations) using steady-state particle tracking MODPATH model. In order to simulate baseflow tritium concentrations with MODPATH, transit time distributions (TTDs) are necessary to understand the lag time between the entry and discharge points of a tracer and are generated for the river networks of the five WLTC outflows. TTDs are used in the convolution integral with an input tritium concentration time series obtained from the precipitation measurements. The resulting MODPATH tritium concentrations yield a very good match to measured tritium concentrations and are similar to the MT3DMS-simulated tritium concentrations, with the greatest variation occurring around the bomb peak. MODPATH and MT3DMS also yield similar mean transit times (MTTs) of groundwater contribution to river baseflows, but the actual shape of the TTDs is strikingly different. While both distributions provide valuable information, the methodologies used to derive the TTDs are fundamentally different and hence must be interpreted differently. With the current MT3DMS model settings, only the methodology used with MODPATH provides the true TTD for use with the convolution integral.

Los estilos APA, Harvard, Vancouver, ISO, etc.

31

Naoe, S., Y. Torikai, R. D. Penzhorn, K. Akaishi, K. Watanabe y M. Matsuyama. "Transport of Tritium in SS316 at Moderate Temperatures". Fusion Science and Technology 54, n.º 2 (agosto de 2008): 515–18. http://dx.doi.org/10.13182/fst08-1.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

32

Bonheure, Georges, Jan Mlynar, A. Murari, C. Giroud, P. Belo, L. Bertalot y S. Popovichev. "A novel method for trace tritium transport studies". Nuclear Fusion 49, n.º 8 (22 de julio de 2009): 085025. http://dx.doi.org/10.1088/0029-5515/49/8/085025.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

33

Scott, S. D., D. R. Ernst, M. Murakami, H. Adler, M. G. Bell, R. Bell, R. V. Budny et al. "Isotopic scaling of transport in deuterium-tritium plasmas". Physica Scripta 51, n.º 3 (1 de marzo de 1995): 394–401. http://dx.doi.org/10.1088/0031-8949/51/3/021.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

34

Gormezano, C., Y. F. Baranov, C. D. Challis, I. Coffey, G. A. Cottrell, A. C. Ekedahl, C. M. Greenfield et al. "Internal Transport Barriers in JET Deuterium-Tritium Plasmas". Physical Review Letters 80, n.º 25 (22 de junio de 1998): 5544–47. http://dx.doi.org/10.1103/physrevlett.80.5544.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

35

Raffray, A. R., Z. R. Gorbis y M. A. Abdou. "Rate-Controlling Tritium Transport Mechanisms in Solid Breeders". Fusion Technology 19, n.º 3P2B (mayo de 1991): 1525–31. http://dx.doi.org/10.13182/fst91-a29558.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

36

Billone, M. C. "Thermal and tritium transport in Li2O and Li2ZrO3". Journal of Nuclear Materials 233-237 (octubre de 1996): 1462–66. http://dx.doi.org/10.1016/s0022-3115(96)00254-1.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

37

Kopasz, J. P., C. A. Seils y C. E. Johnson. "Spatial tritium transport in single-crystal lithium aluminate". Journal of Nuclear Materials 212-215 (septiembre de 1994): 912–16. http://dx.doi.org/10.1016/0022-3115(94)90968-7.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

38

Wu, Xiao, Shanbin Shi, Sheng Zhang, David Arcilesi, Richard Christensen, Piyush Sabharwall y Xiaodong Sun. "Mass transport analysis for tritium removal in FHRs". Annals of Nuclear Energy 121 (noviembre de 2018): 250–59. http://dx.doi.org/10.1016/j.anucene.2018.07.026.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

39

Pan, Lei, Hongli Chen y Qin Zeng. "Tritium transport analysis of HCPB blanket for CFETR". Fusion Engineering and Design 113 (diciembre de 2016): 82–86. http://dx.doi.org/10.1016/j.fusengdes.2016.10.013.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

40

Naoe, S. "Transport of Tritium in SS316 at Moderate Temperatures". Fusion Science and Technology 54, n.º 2 (agosto de 2008): 515–18. http://dx.doi.org/10.13182/fst54-515.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

41

Franza, Fabrizio, Lorenzo Virgillio Boccaccini, David Demange, Andrea Ciampichetti y Massimo Zucchetti. "Tritium Transport Issues for Helium-Cooled Breeding Blankets". IEEE Transactions on Plasma Science 42, n.º 7 (julio de 2014): 1951–57. http://dx.doi.org/10.1109/tps.2014.2329573.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

42

Candido, Luigi, Marco Utili, Iuri Nicolotti y Massimo Zucchetti. "Tritium transport in HCLL and WCLL DEMO blankets". Fusion Engineering and Design 109-111 (noviembre de 2016): 248–54. http://dx.doi.org/10.1016/j.fusengdes.2016.03.017.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

43

Kopasz, J. P., S. W. Tam y C. E. Johnson. "Enhanced tritium transport and release by solids modification". Journal of Nuclear Materials 179-181 (marzo de 1991): 816–19. http://dx.doi.org/10.1016/0022-3115(91)90213-q.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

44

TAM, S. "Tritium transport in lithium ceramics porous media*1". Journal of Nuclear Materials 191-194 (septiembre de 1992): 253–57. http://dx.doi.org/10.1016/0022-3115(92)90765-d.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

45

Ying, Alice, Hongjie Zhang, Brad Merrill, Mu-Young Ahn y Seungyon Cho. "Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation: A MATLAB/Simulink, COMSOL integrated dynamic tritium transport model for HCCR TBS". Fusion Engineering and Design 136 (noviembre de 2018): 1153–60. http://dx.doi.org/10.1016/j.fusengdes.2018.04.093.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

46

Li, Jun Heng, Rong Hua Huang y Hao Ran Cao. "Static Neutronics Analyses of Hellium-Cooled Solid Breeder Blanket". Advanced Materials Research 953-954 (junio de 2014): 631–34. http://dx.doi.org/10.4028/www.scientific.net/amr.953-954.631.

Texto completo

Resumen

A Monte Carlo N-particle transport code was used to study physics of the helium-cooled solid-breeder tritium breeding blanket in the Chinese Fusion Engineering Thermal Reactor （CFETR）for various volume ratio of the neutron multiplier and tritium breeder and various thickness of the first wall. A sandwich-type of Be and loading model is used to analyze the compact of volume ratio and the thickness of the first wall for the tritium breeding rate. The results of different volume ratio models show that the tritium breeding ratio would reach 1.51 for volume ratio from 2 to 5.And the results of the different first wall thickness show that the upper limit of the thickness should be 33mm to keep the tritium self-sustain.

Los estilos APA, Harvard, Vancouver, ISO, etc.

47

Chaparro, M. Carme y Maarten W. Saaltink. "Tritium transport in non-saturated concrete under temperature fluctuations". Journal of Environmental Radioactivity 251-252 (octubre de 2022): 106969. http://dx.doi.org/10.1016/j.jenvrad.2022.106969.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

48

Alberghi, Ciro, Luigi Candido, Marco Utili y Massimo Zucchetti. "Development of new analytical tools for tritium transport modelling". Fusion Engineering and Design 177 (abril de 2022): 113083. http://dx.doi.org/10.1016/j.fusengdes.2022.113083.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

49

Longhurst, Glen R. y James Ambrosek. "Verification and Validation of the Tritium Transport Code TMAP7". Fusion Science and Technology 48, n.º 1 (agosto de 2005): 468–71. http://dx.doi.org/10.13182/fst05-a967.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

50

Pattison, M. J., S. Smolentsev, R. Munipalli y M. A. Abdou. "Tritium Transport in Poloidal Flows of a DCLL Blanket". Fusion Science and Technology 60, n.º 2 (agosto de 2011): 809–13. http://dx.doi.org/10.13182/fst10-309.

Texto completo

Los estilos APA, Harvard, Vancouver, ISO, etc.

Ofrecemos descuentos en todos los planes premium para autores cuyas obras están incluidas en selecciones literarias temáticas. ¡Contáctenos para obtener un código promocional único!