Дисертації з теми "Tritium transport"
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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 джерелаWalsh, Virginia M. "Geochemical Determination of the Fate and Transport of Injected Fresh Wastewater to a Deep Saline Aquifer." FIU Digital Commons, 2012. http://digitalcommons.fiu.edu/etd/692.
Повний текст джерелаBykov, Igor. "Experimental studies of materials migration in magnetic confinement fusion devices : Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces." Doctoral thesis, KTH, Fusionsplasmafysik, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-145045.
Повний текст джерелаQC 20140508
Flaspoehler, Timothy Michael. "FW-CADIS variance reduction in MAVRIC shielding analysis of the VHTR." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/45743.
Повний текст джерелаAmejdki-Chab, Nassira. "Effets des ions sur le transport neuronal de la dopamine et sur la liaison des inhibiteurs et des substrats au transporteur, étudiée à l'aide d'un marqueur spécifique, le [3H] GBR 12783." Rouen, 1991. http://www.theses.fr/1991ROUES042.
Повний текст джерелаLarbi, Bouthaina. "Caractérisation du transport diffusif dans les matériaux cimentaires : influence de la microstructure dans les mortiers." Phd thesis, Université Paris-Est, 2013. http://tel.archives-ouvertes.fr/tel-00966392.
Повний текст джерелаMorillon, Raphaël. "Modifications de perméabilité cellulaire à l'eau liées au développement, au stress hydrique, et aux mutations." Rouen, 1999. http://www.theses.fr/1999ROUES032.
Повний текст джерелаQuérou, Rodolphe. "Absorption et devenir du triticonazole dans la plante de blé après traitement de la semence." Université Joseph Fourier (Grenoble), 1995. http://www.theses.fr/1995GRE10176.
Повний текст джерелаZOTTA, VITO KONRAD. "Prediction and analysis of JET fusion performance based on reduced first principle transport models." Doctoral thesis, 2023. https://hdl.handle.net/11573/1666954.
Повний текст джерелаGoreham, Vincent. "Contaminant Migration Through Soil-Cement Materials." 2014. http://hdl.handle.net/10222/48593.
Повний текст джерелаDeol, Kirandeep. "Molecular cloning and functional characterization of a new Sucrose Transporter in hexaploid wheat (Triticum aestivum L.)." 2012. http://hdl.handle.net/1993/8128.
Повний текст джерелаBotha, C. E. J., and B. Matsiliza. "Reduction in transport in wheat (Triticum aestivum) is caused by sustained phloem feeding by the Russian wheat aphid (Diuraphis noxia)." 2004. http://eprints.ru.ac.za/290/1/botha2004t.pdf.
Повний текст джерелаBotha, C. E. J., and Babalwa Matsiliza. "Reduction in transport in wheat (Triticum aestivum) is caused by sustained phloem feeding by the Russian wheat aphid (Diuraphis noxia)." 2004. http://hdl.handle.net/10962/d1004498.
Повний текст джерелаSilva, Perez Viridiana. "Screening genetic variation for photosynthetic capacity and efficiency in wheat." Phd thesis, 2016. http://hdl.handle.net/1885/101732.
Повний текст джерела