Relevant bibliographies by topics / Tritium transport

Academic literature on the topic 'Tritium transport'

Author: Grafiati
Published: 14 March 2023

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Contents

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Tritium transport.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Tritium transport"

1

Skelton, R., C. Nowak, X. W. Zhou, and R. A. Karnesky. "Tritium segregation to vacancy-type basal dislocation loops in α-Zr from molecular dynamics simulations." Journal of Applied Physics 131, no. 12 (March 28, 2022): 125103. http://dx.doi.org/10.1063/5.0078048.

Full text
Abstract:
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.
APA, Harvard, Vancouver, ISO, and other styles
2

Zastrow), 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Freund, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Gusyev, 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.

Full text
Abstract:
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.
APA, Harvard, Vancouver, ISO, and other styles
5

Gusyev, 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.

Full text
Abstract:
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.
APA, Harvard, Vancouver, ISO, and other styles
6

Zeng, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Murphy 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Heung, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Tam, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Ritter, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Tritium transport"

1

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Tyre, Shelly J. "REMChlor model of tritium transport at the MADE site." Connect to this title online, 2008. http://etd.lib.clemson.edu/documents/1219852373/.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Sullivan, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

CANDIDO, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Röttele, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Garcia, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Stempien, 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.

Full text
Abstract:
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015.
Cataloged 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.
APA, Harvard, Vancouver, ISO, and other styles
8

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.

Full text
Abstract:
When different water resource components coexist in nature, they usually have an impact on each other. Studies of how they impact each other in terms of water quantities, flow dynamics, quality and contamination are therefore necessary to ensure an appropriate water and environmental management is conducted. A study in Middleburg comprised a literature review and field investigations at and around a cemetery, as part of a Water Research Commission project on impacts on the water resource from large-scale burials. A literature review conducted has enabled familiarisation with similar studies that have been conducted around the subject. Reliable methodologies have therefore been adopted from the published literature and applied on the current research. A seasonal wetland is located downgradient of the cemetery, between the cemetery and a stream that flows past the cemetery. In order to assess possible flow pathways of near-surface and groundwater from the cemetery to the stream, monthly monitoring of surface and groundwater quality and level fluctuations was carried out on the stream, as well as existing and newly installed boreholes at the cemetery. Water samples collected were analysed for inorganic constituents, tritium, and stable water isotopes. The tritium and stable water isotope results – revealed the comparative influence of rainfall and shallow groundwater contributions to streamflow, while groundwater provides base-flows as the stream levels recede. The depth to groundwater reduced with increasing rainfall, indicating direct recharge. The difference in concentrations of some inorganic parameters in the stream compared to the groundwater at the cemetery revealed the effect of natural attenuation in the vadose zone due to reduced conditions and the wetland acting as a filter to improve the water quality of the shallow interflow on reaching the stream. Since isotope data indicated to be a useful tool in studying water resource interactions, the methodology should form part of site investigations for cemetery development or on existing cemeteries to study the current impact and/or predict future impacts that the cemetery may have on the water resources. The methodology best applies in areas with multiple water resources, where there may be an interconnection between them. The isotope studies can also be used to estimate recharge and thus contaminant transport rate of the cemetery leachate.
Dissertation (MSc)--University of Pretoria, 2020.
Geology
MSc
Unrestricted
APA, Harvard, Vancouver, ISO, and other styles
9

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.

Full text
Abstract:
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, February, 2021
Cataloged 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
APA, Harvard, Vancouver, ISO, and other styles
10

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Books on the topic "Tritium transport"

1

Rodrigo, L. Tritium measurement and transport. Chalk River, Ont: Chalk River Laboratories, 1993.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
2

Group, 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.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
3

Cooper, Clay A. Tritium transport at the Rulison Site, a nuclear-stimulated low-permeability natural gas reservoir. [Reno, Nev.]: Desert Research Institute, 2007.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
4

Cooper, Clay A. Tritium transport at the Rulison Site, a nuclear-stimulated low-permeability natural gas reservoir. [Reno, Nev.]: Desert Research Institute, 2007.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
5

Irving, 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.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
6

Modelling the Environmental Transport of Tritium in the Vicinity of Long Term Atmospheric and Sub-Surface Sources (IAEA-Biomass). International Atomic Energy Agency, 2003.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
7

ITER safety task NID-5D: Operational tritium loss & accident investigation for heat transport & water detritiation systems. Mississauga, ON: Canadian Fusion Fuels Technology Project, 1995.

Find full text
APA, Harvard, Vancouver, ISO, and other styles

Book chapters on the topic "Tritium transport"

1

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Matsuura, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Gvirtzman, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Kuppelwieser, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Misra, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Shimada, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

SMAIHI, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

"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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Warrick, Arthur W. "Solute and Contaminant Transport." In Soil Water Dynamics. Oxford University Press, 2003. http://dx.doi.org/10.1093/oso/9780195126051.003.0012.

Full text
Abstract:
We now look at the transport of materials in soil systems. Not only do water and liquids move, but so also do a variety of chemical and biological constituents. In this chapter, the emphasis will be on flow processes involving water that is carrying different types of solute. The solutes of interest can be harmful or they can be beneficial. The same chemical species could be desirable when contained within one region and undesirable if it escapes to another—such as from the root zone to the ground water. Both conservative and reactive tracers will be discussed. A conservative tracer is assumed to move freely with the soil water and is non-reactive, non-volatile, and non-absorbing. Of course, this is only an ideal case, and all materials carried with water will react in some way with the solid phase. The degree of interaction depends on the solute, the soil, and the flow regime. However, if there is little interaction, the solute can often be treated as a conservative tracer. Examples are tritium and, to a lesser degree, bromide. Other materials are only slightly soluble, readily react with the solid phase, or perhaps can change into alternative phases that are clearly non-conservative. In some cases, whether a solute can logically be considered as a conservative or non-conservative tracer depends on the time scale and where the process is occurring—for example, perhaps the reaction rates are low, and for a short time scale the process is conservative; alternatively, perhaps the reaction rate is driven by whether oxygen is available or whether a specific microbe or catalyst is present at a particular time and place. Most of the discussion is directed toward “miscible displacement” processes. For a miscible displacement process, the invading fluid mixes freely with the fluid that is being driven out. An example is the displacement of water of a concentration differing from that of the antecedent water. Miscible displacement of a low molecular weight alcohol with water is another example. Many problems of environmental concern are included, such as leaching of nitrates from the soil surface to the groundwater.
APA, Harvard, Vancouver, ISO, and other styles
10

Ingram, 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.

Full text
Abstract:
Humans cultivate more than 200 species of plants, but this chapter reviews responses of 5 important cereal crops to drought. These crops are maize (Zea mays L.), rice (Oryza sativa L.), wheat (Triticum aestivum and Triticum turgidum L. var. durum), sorghum (Sorghum bicolor [L.] Moench), and pearl millet (Pennisetum glaucum [L.] R. Br), which provide the majority of food in the world. In general, farmers cultivate millet in the most drought-prone environments and sorghum where a short growing season is the greatest constraint to production. Some sorghum cultivars set grain in as short as 50–60 days (Roncoli et al., 2001). Rice is grown under a wide range of environments, from tropical to temperate zones, from deep water-flooded zones to nonflooded uplands. Rice productivity is limited mostly by water (IRRI, 2002). Drought limits, to a varying extent, the productivity of all of these crops. Although water is likely the most important manageable limit to food production worldwide, we should recognize that water management cannot be isolated from nutrient, crop, and pest management. Life on earth depends on green plants, which capture solar energy and store chemical energy by the process of photosynthesis. Although plants use a small amount of water in the reactions of photosynthesis and retain small amounts of water in plant tissues, as much as 99% of the water that plants take up is lost through transpiration (i.e., gaseous water transport through the stomata of leaves). Stomata, which are small pores on leaf surfaces, must open to allow carbon dioxide to enter leaf tissues for photosynthesis and plant growth, but open stomata also allow water to escape. In addition to transpiration, there are several other avenues of water loss from a crop system. Water may exit the crop system by evaporation from the soil, transpiration of weeds, deep drainage beyond the root zone, lateral flow beneath the soil surface, or runoff. We can sum the daily additions and losses of water to form a water balance equation: . . . S = G + P + I − E − T − Tw − D − L − R [2.1] . . .
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Tritium transport"

1

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Zhang, 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.

Full text
Abstract:
Abstract China Fusion Engineering Test Reactor (CFETR) is aimed to meet the technical gaps between International Thermonuclear Experimental Reactor (ITER) and future fusion DEMO reactors, tritium self-sufficiency must be guaranteed for the operation of fusion reactors. Helium Cooled Ceramic Breeder (HCCB) blanket is one of the promising candidate blanket schemes for CFETR. Tritium generated in Li4SiO4 pebble bed is carried out by purge gas, it is crucial to study the tritium behavior in the blanket from the tritium fuel cycle point of view. In this paper, the effective diffusivity of tritium in purge gas is conducted based on Discrete Element Method (DEM) and Computational Fluid Dynamics (CFD) coupled simulation considering the influence of the pebble bed structure. The flow characters analysis of purge gas is carried out by CFD simulation as well, which includes velocity field distribution, pressure field distribution and pressure drop. Based on the macro parameters conducted above, the tritium transport process in blanket including tritium permeation into coolant, tritium inventory in blanket and tritium carried out by purge gas is simulated based on a 2D model set up in COMSOL Multiphysics, the results can be the reference for the design of Tritium Extraction System (TES) and Coolant Purification System (CPS).
APA, Harvard, Vancouver, ISO, and other styles
3

Lee, 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.

Full text
Abstract:
For tritium supply to the fusion reactor of ITER (The Way to New Energy) [1], tritium need to be transported from tritium production sites, mainly the CANDU type reactor sites to the tritium plant building of ITER. Korea Atomic Energy Research Institute (KAERI) was commissioned the work of developing the transport package for tritium by ITER Organization and the first stage of the development has been just finished. The developed package was designed to carry 70 g of tritium and classified as a type B(U) package, which should comply with the requirements stipulated in IAEA Safety Standard Series [2]. The package is composed of a storage vessel, a containment vessel, an overpack and an aluminum liner which is a unique feature of the package. The aluminum liner between the storage vessel and the containment vessel is for containment control under the repetitive use of the package. The package has enough pressure resistance for 5 year in-site storage and the structural and thermal integrity under the hypothetical accident conditions has been demonstrated through a series of analyses.
APA, Harvard, Vancouver, ISO, and other styles
4

Blanton, 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.

Full text
Abstract:
Radioactive material packagings designed for out-of-commerce shipments are not necessarily subject to the same regulatory requirements as packagings designed for in-commerce service. For example, DOE Order 460.1B permits application of the notion of Equivalent Safety to out-of-commerce shipping within DOE sites. Equivalent safety can be viewed as a reduction in 10 CFR 71 design conditions without a corresponding loss of public health and safety. This paper presents a packaging design identified as the Tritium Spent Melt Overpack (SMO) that successfully utilized equivalent safety at the Savannah River Site (SRS). Because the spent melt materials are highly radioactive, the container must be loaded and closed remotely. The SMO design is a based on twenty-foot long eighteen-inch diameter pipe, with one end closed by welded plate and the open end closed by a latching plug that incorporates bore seals. The SMO receives a single sixteen-inch diameter by 16-foot long crucible partly filled with the waste product from the tritium extraction process. The loaded overpack is moved from the SRS Tritium Extraction Facility inside a heavily shielded cask. Upon arrival at a waste silo designed to receive the overpack, it is removed from the shielding cask by remote means and placed in the long-term storage silo. This paper provides an overview of the SMO overpack design and its operation.
APA, Harvard, Vancouver, ISO, and other styles
5

Qin, 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.

Full text
Abstract:
Tritium control is one of the most critical issues for the development of Molten Salt Reactor (MSR). The point kinetic model has been added into the TAPAS (Tritium trAnsPort chAracteristicS code) to research the dynamic responses of tritium transport characteristics during transients. Two typical transient accident conditions for Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) are simulated, including unprotected reactivity insertion (URIA) and unprotected overcooling (UOC). The distributions of the key variables in the primary loop and variations with time are obtained including TF, T2 and Cr2+. Numerical results show that during transients, tritium has quite different transport characteristics compared with steady state, ranging from tritium production and speciation, absorption by graphite, Cr corrosion and deposition to tritium permeation. The results are discussed in comparison with earlier findings in detail. This study may provide a valuable reference for the tritium control in MSR.
APA, Harvard, Vancouver, ISO, and other styles
6

Castro, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Terron, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Zhou, 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.

Full text
Abstract:
Abstract Tritium is an important nuclear fuel in fusion reactors and one of the dominant nuclides in the primary coolant in fission reactors. The storage, feeding, control, monitoring, and transport of tritium are important for practical engineering applications. Because of the high mobility of tritium in both fission and fusion nuclear systems and its effect on human body, tritium has received great attention worldwide. The retention and prevention of tritium permeation from primary loop to secondary loop is a common research interest in various reactors. Previous studies indicated that a surface oxide layer is an efficient method to reduce tritium permeation. In this paper, we summarize the effects of various oxide layers on the permeation of hydrogen isotopes in nuclear reactors. The permeation reduction factor for materials used in fusion reactors ranges from 1000 to 100000. The diffusion behavior of tritium in several materials with and without oxide layer is discussed in detail. The oxide layer is more important than intrinsic permeability to prevent tritium permeation. As tritium is the only radioactive source term in the secondary loop of high temperature gas-cooled reactors, we also reviewed the permeation of hydrogen isotopes in the heat exchanger, which is an important issue in nuclear hydrogen production. The present study provides a comprehensive overview of tritium permeation behavior and is expected to promote the development and design of tritium-permeation-proof materials in the future.
APA, Harvard, Vancouver, ISO, and other styles
9

Zhang, 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.

Full text
Abstract:
Abstract Fluoride salt-cooled High-temperature Reactor (FHR) is one of the advanced non-Light Water Reactor (non-LWR) designs, which adopts a low-pressure fluoride salt as the primary coolant, high working temperatures, coated-particle fuel, and a passive safety system for decay heat removal. However, tritium management is perceived as a critical issue for FHRs since tritium is a radiation hazard when inhaled or ingested and its production rate in FHRs is expected to be significantly higher compared to that in LWRs. To reduce FHR tritium release rates into the ambient, two tritium mitigation options, such as using Double-Wall Fluted-Tube Heat eXchangers (DWFT-HXs) with a tritium carrier or Single-Wall Fluted-Tube HXs (SWFT-HXs) with a tritium barrier, are therefore proposed for key HXs in FHRs, which potentially provide major pathways for tritium release due to their elevated temperatures and large surface areas. Tritium carriers investigated include gases, such as helium, and liquids, such as FLiBe, FLiNaK, and KF-ZrF4, while the tritium barrier investigated in this paper is silicon carbide (SiC) due to its low permeability for tritium. These proposed HX designs are then optimized, using a Non-dominated Sorting in Generic Algorithms (NSGA) optimization approach, for the Advanced High-Temperature Reactor (AHTR), one of the FHR designs with a large power output. A system-level mass transfer model is developed to evaluate the tritium transport in the two proposed design options for tritium mitigation in FHRs and quantitively analyze the tritium release/leakage rate from the reactor primary system. Our study shows that both the DWFT-HX design with helium as the tritium carrier and SWFT-HX design with SiC coating as the tritium barrier are able to reduce the total tritium leakage rate in FHRs to the same order of magnitude of the typical average tritium leakage rate in LWRs (1.9 Ci/day).
APA, Harvard, Vancouver, ISO, and other styles
10

Zhou, 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.

Full text
Abstract:
Abstract The very-high-temperature reactor (VHTR) has been included in the conception of the Generation IV nuclear energy system proposed by the United States Department of Energy Nuclear Energy Research Advisory Committee and the Generation IV International Forum. After the Fukushima accident, concern has grown regarding the safety of nuclear power plants. For its inherent safety, superior proliferation resistance, and high thermal efficiency, the VHTR and its prototype, the high-temperature gas-cooled reactor (HTGR), attracted worldwide interest. Tritium exists in the fuel element and graphite reflectors in the core, primary coolant, some liquid and solid wastes, and gaseous effluent of HTGRs. Due to its permeation behavior at high temperatures, tritium is the most important nuclide in the secondary loop of HTGRs. Considering the future application of HTGRs in hydrogen production, tritium will be non-negligible and could be difficult to separate from hydrogen. In addition, the interaction between tritium and graphite is expected to be very strong. The absorption, desorption, and diffusion of tritium at the interface between the primary coolant and graphite are of great interest. Experimental measurements of the diffusion coefficients of tritium and its isotopes do not agree well with theoretical predictions based on the consideration of isotope effects. In this paper, research progress on the permeation, absorption, desorption, and diffusion behaviors of tritium in HTGRs is summarized and discussed. The chemical form of tritium in the primary coolant, and its spectroscopic characteristics, internal structures, and transport behaviors are organized and analyzed. Basic properties related to tritium, such as isotope effect, nuclear spin, radioactivity, etc. are also discussed.
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Tritium transport"

1

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Viner, B. MODELING TRITIUM TRANSPORT, DEPOSITION AND RE-EMISSION. Office of Scientific and Technical Information (OSTI), April 2012. http://dx.doi.org/10.2172/1037767.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Murakami, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Rogers, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Chapman, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Dunn, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Martin, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Murphy, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Chang 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Pohlmann, 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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Tritium transport' for particular source types:
Journal articles Dissertations / Theses
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography