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Статті в журналах з теми "Tritium transport"
Skelton, R., C. Nowak, X. W. Zhou та R. A. Karnesky. "Tritium segregation to vacancy-type basal dislocation loops in α-Zr from molecular dynamics simulations". Journal of Applied Physics 131, № 12 (28 березня 2022): 125103. http://dx.doi.org/10.1063/5.0078048.
Повний текст джерелаZastrow), JET Team (prepared by K. D. "Trace tritium transport in JET." Nuclear Fusion 39, no. 11Y (November 1999): 1891–96. http://dx.doi.org/10.1088/0029-5515/39/11y/331.
Повний текст джерелаFreund, Jana, Frederik Arbeiter, Ali Abou-Sena, Fabrizio Franza, and Keitaro Kondo. "Tritium transport calculations for the IFMIF Tritium Release Test Module." Fusion Engineering and Design 89, no. 7-8 (October 2014): 1600–1604. http://dx.doi.org/10.1016/j.fusengdes.2014.06.003.
Повний текст джерелаGusyev, M. A., M. Toews, U. Morgenstern, M. Stewart, P. White, C. Daughney, and 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, no. 3 (March 19, 2013): 1217–27. http://dx.doi.org/10.5194/hess-17-1217-2013.
Повний текст джерелаGusyev, M. A., M. Toews, U. Morgenstern, M. Stewart, C. Daughney, and 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, no. 8 (August 24, 2012): 9743–65. http://dx.doi.org/10.5194/hessd-9-9743-2012.
Повний текст джерелаZeng, Qin, Wei Shi, Xiande Wang, and Hongli Chen. "Tritium transport analysis for tokamak exhaust processing system of tritium plant." Fusion Engineering and Design 159 (October 2020): 111955. http://dx.doi.org/10.1016/j.fusengdes.2020.111955.
Повний текст джерелаMurphy Jr. (INVITED), C. E. "Modelling Tritium Transport in the Environment." Radiation Protection Dosimetry 16, no. 1-2 (September 1, 1986): 51–58. http://dx.doi.org/10.1093/oxfordjournals.rpd.a079713.
Повний текст джерелаHeung, L. K. "Tritium Transport Vessel Using Depleted Uranium." Fusion Technology 28, no. 3P2 (October 1995): 1385–90. http://dx.doi.org/10.13182/fst95-a30605.
Повний текст джерелаTam, S. W., J. P. Kopasz, and C. E. Johnson. "Tritium transport and retention in SiC." Journal of Nuclear Materials 219 (March 1995): 87–92. http://dx.doi.org/10.1016/0022-3115(94)00392-0.
Повний текст джерелаRitter, P. D., T. J. Dolan, and G. R. Longhurst. "Tritium environmental transport studies at TFTR." Journal of Fusion Energy 12, no. 1-2 (June 1993): 145–48. http://dx.doi.org/10.1007/bf01059370.
Повний текст джерелаДисертації з теми "Tritium transport"
Considine, Ellen J. "Tritium transport at the Cambric site at NTS." abstract and full text PDF (free order & download UNR users only), 2005. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1433408.
Повний текст джерелаTyre, Shelly J. "REMChlor model of tritium transport at the MADE site." Connect to this title online, 2008. http://etd.lib.clemson.edu/documents/1219852373/.
Повний текст джерелаSullivan, David Patrick. "Intracellular sterol transport and distribution in saccharomyces cerevisiae /." Access full-text from WCMC, 2009. http://proquest.umi.com/pqdweb?did=1692359491&sid=3&Fmt=2&clientId=8424&RQT=309&VName=PQD.
Повний текст джерелаCANDIDO, LUIGI. "Tritium transport modelling and experimental validation in liquid metal nuclear power plants." Doctoral thesis, Politecnico di Torino, 2022. https://hdl.handle.net/11583/2972875.
Повний текст джерелаRöttele, Carsten [Verfasser], and G. [Akademischer Betreuer] Drexlin. "Tritium suppression factor of the KATRIN transport section / Carsten Röttele ; Betreuer: G. Drexlin." Karlsruhe : KIT-Bibliothek, 2019. http://d-nb.info/1192373669/34.
Повний текст джерелаGarcia, Christina Amanda. "Vertical tritium transport from the shallow unsaturated zone to the atmosphere, Amargosa Desert Research Site, Nevada." abstract and full text PDF (free order & download UNR users only), 2007. http://0-gateway.proquest.com.innopac.library.unr.edu/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqdiss&rft_dat=xri:pqdiss:1446436.
Повний текст джерелаStempien, John D. (John Dennis). "Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR)." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/103727.
Повний текст джерелаCataloged from PDF version of thesis.
Includes bibliographical references (pages 294-305).
The Fluoride Salt-Cooled High-Temperature Reactor (FHR) is a pebble bed nuclear reactor concept fueled by tristructural isotropic (TRISO) fuel particles embedded in graphite spheres and cooled by a liquid fluoride salt known as "flibe" (7LiF-BeF2). A system of models was developed which enabled analyses of the performance of a prototypical pebble bed FHR (PB-FHR) with respect to tritium production and transport, corrosion, TRISO fuel performance, and materials stability during both normal and beyond design-basis accident (BDBA) conditions. A model of TRITium Diffusion EvolutioN and Transport (TRIDENT) was developed and benchmarked with experimental data. TRIDENT integrates the effects of the chemical redox potential, tritium mass transfer, tritium diffusion through pipe walls, and selective Cr attack by tritium fluoride. Systems for capturing tritium from the coolant were proposed and simulated with TRIDENT. A large nickel permeation window reduced the tritium release rate from 2410 to 800 Ci/EFPD. A large gas stripping system reduced tritium release rates from 2410 to 439 Ci/EFPD. A packed bed of graphite located between the reactor core and the heat exchanger reduced peak tritium release rates from 2410 to 7.5 Ci/EFPD. Increasing the Li-7 enrichment in flibe from 99.995 to 99.999 wt% reduced both the tritium production rate and the necessary sizes of tritium capture systems by a factor of 4. An existing TRISO fuel performance model called TIMCOAT was modified for use with PBFHRs. Low failure rates are predicted for modern uranium oxycarbide (UCO) TRISO fuels in a PBFHR environment. Post-irradiation examinations of surrogate TRISO particles determined that the outer pyrolytic carbon layer is susceptible to cracking if flibe were to freeze around the particles. Chemical thermodynamics calculations demonstrated that common constituents of concrete will not be stable in the event they contact liquid flibe. The chemical stability of fission products in reference to the coolant redox potential was determined in the event the TRISO UCO kernel is exposed to flibe during a BDBA. Noble gases (Kr and Xe) will escape the coolant. Cesium, strontium, and iodine are retained in the salt. All other important radionuclides are retained in the kernel or within the coolant system.
by John Dennis Stempien.
Ph. D.
Mahlangu, Sarah Ndazi. "Use of tritium and stable water isotopes to assess contaminant transport at a burial site in Middelburg, Mpumalanga." Diss., University of Pretoria, 2020. http://hdl.handle.net/2263/77840.
Повний текст джерелаDissertation (MSc)--University of Pretoria, 2020.
Geology
MSc
Unrestricted
Dolan, Kieran Patrick. "Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor." Thesis, Massachusetts Institute of Technology, 2021. https://hdl.handle.net/1721.1/131004.
Повний текст джерелаCataloged from the official PDF version of thesis.
Includes bibliographical references (pages 319-333).
Advanced reactor concepts which use a lithium- or beryllium-bearing primary salt coolant will require technical solutions to mitigate the environmental release of tritium. One such design is the Fluoride-Salt-Cooled High-Temperature Reactor (FHR), which combines a molten Flibe (2LiF-BeF₂) salt coolant and tri-structural isotropic coated-particle fuel to produce power or process heat. Compared to current water-cooled reactors, managing tritium release from a FHR is further complicated by the mobility of tritium at high temperatures and limited knowledge of interactions between tritium and nuclear graphite in the molten fluoride salt environment. The total activity, chemical forms, and retention mechanisms for tritium in nuclear graphite were studied through thermal desorption analysis of sample materials from three in-core Flibe salt irradiations (denoted FS-1, FS-2, and FS-3) at the MIT Reactor (MITR).
Tritium desorption rates as a function of temperature were observed in distinct peak structures which are indicative of distinct trapping sites in graphite. The tritium content measurements led to estimations of overall retention in nuclear graphite of 19.6±1.9% from FS-1, 34±10% from FS-2, and 27.1±1.9% from FS-3 relative to the total calculated tritium generation in each experiment. Thermal desorption measurements of the MITR samples were consistent with previously proposed mechanisms for retention of gaseous hydrogen in graphite based on the chemical form of desorbed tritium, the activation energy of the desorption process, and the effect of excess H₂ on the desorption rate as a function of temperature. Therefore, a methodology based on gaseous retention mechanisms was proposed and developed to model the uptake of tritium into graphite from Flibe in a FHR.
A tritium retention model based on a bulk-diffusivity in graphite was developed as well as a model based on differential transport in graphite pores and grains. Using a system-level tritium transport model, the overall retention on graphite pebbles in a FHR was calculated to be 20.3% and 26.3% of the equilibrium generation rate for the bulk-diffusivity and pore and grain methods, respectively. In each case, modeling the transport and trapping of tritium inside graphite significantly reduced the retention rates compared to a retention process solely limited by mass transport in Flibe. According to the results of a sensitivity analysis, the level of tritium retention in core graphite has the largest uncertainty in the FHR tritium distribution because of relatively high standard deviations in literature measurements of tritium solubility and diffusivity in graphite.
Tritium management technology options were then examined in the system-level transport model based on permeation barrier coatings and tritium extraction systems. Permeation barrier coatings of a specified performance level applied to Flibe-facing surfaces were found to be more effective than exterior-surface coatings, while extraction systems with design constraints were able to significantly reduce overall tritium releases. A combination of the interior-surface barriers and extraction systems applied to various regions of the plant was shown to reduce tritium release into the FHR reactor building to levels below that of current light water reactors.
by Kieran Patrick Dolan.
Ph. D.
Ph.D. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering
Kosmider, Andreas [Verfasser], and G. [Akademischer Betreuer] Drexlin. "Tritium Retention Techniques in the KATRIN Transport Section and Commissioning of its DPS2-F Cryostat / Andreas Kosmider. Betreuer: G. Drexlin." Karlsruhe : KIT-Bibliothek, 2012. http://d-nb.info/102472963X/34.
Повний текст джерелаКниги з теми "Tritium transport"
Rodrigo, L. Tritium measurement and transport. Chalk River, Ont: Chalk River Laboratories, 1993.
Знайти повний текст джерелаGroup, Biosphere Modelling and Assessment Programme (International Atomic Energy Agency) Tritium Working. Modelling the environmental transport of tritium in the vicinity of long term atmospheric and sub-surface sources: Report of the Tritium Working Group of the Biosphere Modelling and Assessment (BIOMASS) Programme, theme 3. Vienna, Austria: International Atomic Energy Agency, 2003.
Знайти повний текст джерелаCooper, Clay A. Tritium transport at the Rulison Site, a nuclear-stimulated low-permeability natural gas reservoir. [Reno, Nev.]: Desert Research Institute, 2007.
Знайти повний текст джерелаCooper, Clay A. Tritium transport at the Rulison Site, a nuclear-stimulated low-permeability natural gas reservoir. [Reno, Nev.]: Desert Research Institute, 2007.
Знайти повний текст джерелаIrving, Rebecca E. L. Three-dimensional flow and transport modelling of tritium in the Twin Lake aquifer, Chalk River, Ontario. Ottawa: National Library of Canada = Bibliothèque nationale du Canada, 1993.
Знайти повний текст джерелаModelling the Environmental Transport of Tritium in the Vicinity of Long Term Atmospheric and Sub-Surface Sources (IAEA-Biomass). International Atomic Energy Agency, 2003.
Знайти повний текст джерелаITER safety task NID-5D: Operational tritium loss & accident investigation for heat transport & water detritiation systems. Mississauga, ON: Canadian Fusion Fuels Technology Project, 1995.
Знайти повний текст джерелаЧастини книг з теми "Tritium transport"
Eriksson, Erik. "The Atmospheric Transport of Tritium." In Isotope Techniques in the Hydrologic Cycle, 56–57. Washington, D. C.: American Geophysical Union, 2013. http://dx.doi.org/10.1029/gm011p0056.
Повний текст джерелаMatsuura, Hideaki, and Masabumi Nishikawa. "Evaluation Method of Tritium Breeding Ratio Using Neutron Transport Equation." In Tritium: Fuel of Fusion Reactors, 257–72. Tokyo: Springer Japan, 2016. http://dx.doi.org/10.1007/978-4-431-56460-7_12.
Повний текст джерелаGvirtzman, H., and M. Magaritz. "Water and Anion Transport in the Unsaturated Zone Traced by Environmental Tritium." In Inorganic Contaminants in the Vadose Zone, 190–98. Berlin, Heidelberg: Springer Berlin Heidelberg, 1989. http://dx.doi.org/10.1007/978-3-642-74451-8_13.
Повний текст джерелаKuppelwieser, H., and U. Feller. "Influence of fusicoccin and xylem wall adsorption on cation transport into maturing wheat (Triticum aestivum) ears." In Plant Nutrition — Physiology and Applications, 117–20. Dordrecht: Springer Netherlands, 1990. http://dx.doi.org/10.1007/978-94-009-0585-6_19.
Повний текст джерелаMisra, A. N., S. M. Sahu, F. Dilnawaz, P. Mohapatra, M. Misra, N. K. Ramaswamy, and T. S. Desai. "Photosynthetic Pigment-Protein Content, Electron Transport Activity and Thermo-Luminescence Properties of Chloroplasts Along the Developmental Gradient in Greening Wheat (Triticum aestivum L.) Leaves." In Photosynthesis: Mechanisms and Effects, 3179–82. Dordrecht: Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-3953-3_745.
Повний текст джерелаShimada, Masashi. "Tritium Transport in Fusion Reactor Materials." In Comprehensive Nuclear Materials, 251–73. Elsevier, 2020. http://dx.doi.org/10.1016/b978-0-12-803581-8.11754-0.
Повний текст джерелаSMAIHI, M., D. PETIT, J. P. BOILOT, F. M. BOTTER, J. MOUGIN, and M. J. BONCOEUR. "TRANSPORT PROPERTIES AND TRITIUM RELEASE OF SOL-GEL LITHIUM ORTHOSILICATE CERAMICS." In Fusion Technology 1990, 817–21. Elsevier, 1991. http://dx.doi.org/10.1016/b978-0-444-88508-1.50148-1.
Повний текст джерела"Alternate VHTR/HTE interface for mitigating tritium transport and structure creep." In Nuclear Science, 433–44. OECD, 2010. http://dx.doi.org/10.1787/9789264087156-48-en.
Повний текст джерелаWarrick, Arthur W. "Solute and Contaminant Transport." In Soil Water Dynamics. Oxford University Press, 2003. http://dx.doi.org/10.1093/oso/9780195126051.003.0012.
Повний текст джерелаIngram, Keith T. "Drought-Related Characteristics of Important Cereal Crops." In Monitoring and Predicting Agricultural Drought. Oxford University Press, 2005. http://dx.doi.org/10.1093/oso/9780195162349.003.0008.
Повний текст джерелаТези доповідей конференцій з теми "Tritium transport"
Paek, S., M. Lee, K. R. Kim, D. H. Ahn, K. M. Song, and S. H. Shon. "Development of 100kCi tritium transport vessel." In 2009 23rd IEEE/NPSS Symposium on Fusion Engineering - SOFE. IEEE, 2009. http://dx.doi.org/10.1109/fusion.2009.5226402.
Повний текст джерелаZhang, Baorui, Zhaoyang Xia, and Zhiwei Zhou. "Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65076.
Повний текст джерелаLee, Sanghoon, Min-Soo Lee, Ju-Chan Lee, Woo-Seok Choi, and Ki-Seog Seo. "Development of Tritium Transport Package for ITER Supply." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57851.
Повний текст джерелаBlanton, Paul S., and T. Kurt Houghtaling. "Onsite Packaging and Transport of Tritium Waste." In ASME/JSME 2004 Pressure Vessels and Piping Conference. ASMEDC, 2004. http://dx.doi.org/10.1115/pvp2004-2776.
Повний текст джерелаQin, Hao, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, and Guanghui Su. "Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81728.
Повний текст джерелаCastro, P., M. Velarde, J. Ardao, J. M. Perlado, and L. Sedano. "Tritium extraction system pipe break environmental impact by atmospheric modelling of tritium forms transport." In 2013 IEEE 25th Symposium on Fusion Engineering (SOFE). IEEE, 2013. http://dx.doi.org/10.1109/sofe.2013.6635497.
Повний текст джерелаTerron, S., C. Moreno, L. A. Sedano, F. Gabriel, and A. Abanades. "Tritium transport finite element modeling tools for breeding blanket design." In 2009 23rd IEEE/NPSS Symposium on Fusion Engineering - SOFE. IEEE, 2009. http://dx.doi.org/10.1109/fusion.2009.5226403.
Повний текст джерелаZhou, Ziling, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, and Bin Shan. "Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91275.
Повний текст джерелаZhang, Sheng, Xiao Wu, and Xiaodong Sun. "Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16379.
Повний текст джерелаZhou, Ziling, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, and Qunchao Fan. "Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-63539.
Повний текст джерелаЗвіти організацій з теми "Tritium transport"
Pan, P. Y., and L. D. Rigdon. Tritium oxidation in atmospheric transport. Office of Scientific and Technical Information (OSTI), September 1996. http://dx.doi.org/10.2172/369675.
Повний текст джерелаViner, B. MODELING TRITIUM TRANSPORT, DEPOSITION AND RE-EMISSION. Office of Scientific and Technical Information (OSTI), April 2012. http://dx.doi.org/10.2172/1037767.
Повний текст джерелаMurakami, M., D. B. Batchelor, and C. E. Bush. ICRF heating and transport of deuterium-tritium plasmas in TFTR. Office of Scientific and Technical Information (OSTI), December 1994. http://dx.doi.org/10.2172/113956.
Повний текст джерелаRogers, J. H., G. Schilling, J. E. Stevens, G. Taylor, J. R. Wilson, M. G. Bell, R. V. Budny, N. L. Bretz, D. Darrow, and E. Fredrickson. ICRF heating and transport of deuterium-tritium plasmas in TFTR. Office of Scientific and Technical Information (OSTI), February 1995. http://dx.doi.org/10.2172/10115936.
Повний текст джерелаChapman, J., K. Pohlmann, and R. Andricevic. Exposure assessment of groundwater transport of tritium from the Shoal Site. Office of Scientific and Technical Information (OSTI), April 1995. http://dx.doi.org/10.2172/110786.
Повний текст джерелаDunn, D. L., and W. H. Carlton. Surface water transport of tritium to the Savannah River, 1992--1993. Office of Scientific and Technical Information (OSTI), November 1994. http://dx.doi.org/10.2172/10195015.
Повний текст джерелаMartin, R., and N. M. Ghoniem. Modelling of tritium transport in a pin-type solid breeder blanket. Office of Scientific and Technical Information (OSTI), February 1986. http://dx.doi.org/10.2172/5610340.
Повний текст джерелаMurphy, C. E. Jr. The transport, dispersion, and cycling of tritium in the environment. [Contains Bibliography]. Office of Scientific and Technical Information (OSTI), January 1990. http://dx.doi.org/10.2172/6324878.
Повний текст джерелаChang H. Oh and Eung S. Kim. Heat Exchanger Design Options and Tritium Transport Study for the VHTR System. Office of Scientific and Technical Information (OSTI), September 2008. http://dx.doi.org/10.2172/940414.
Повний текст джерелаPohlmann, K., and R. Andricevic. Scoping calculations for groundwater transport of tritium from the Gnome Site, New Mexico. Office of Scientific and Technical Information (OSTI), August 1994. http://dx.doi.org/10.2172/45596.
Повний текст джерела