10 Matching Results

Search Results

Advanced search parameters have been applied.

Sorption Behavior of Strontium-85 Onto Colloids of Silica and Smectite

Description: Strontium-90 is one of the sizable radioactive contaminants found in DP Canyon at Los Alamos, New Mexico. Radioactive surveys found the {sup 90}Sr is present in surface and groundwater in DP Canyon and Los Alamos Canyon. Colloids may influence the transport of this radionuclide in surface water and groundwater environments in both canyons. In this study, we investigated the sorption/desorption behavior of Sr on colloids of smectite and silica. Laboratory batch sorption experiments were conducted using {sup 85}Sr as a surrogate to {sup 90}Sr. Groundwater, collected from DP Canyon and from Well J-13 at Yucca Mountain, Nevada, and deionized water were used in this study. Our results show that 92% to 100% of {sup 85}Sr was rapidly adsorbed onto smectite colloids in all three waters. The concentrations of Ca{sup 2+} significantly influence the adsorption of {sup 85}Sr onto silica colloids. Desorption of {sup 85}Sr from smectite colloids is much slower than the sorption process. Desorption of {sup 85}Sr from silica colloids was rapid in DP groundwater and slow using J-13 groundwater and deionized water.
Date: November 10, 1998
Creator: Lu, N.; Triay, I.R.; Mason, C.F.V. & Longmire, P.A.
Partner: UNT Libraries Government Documents Department

Use of Thermal Data to Estimate Infiltration in Pagany Wash Associated with the winter of 1997-1998 El Nino Precipitation, Yucca Mountain, Nevada

Description: Temperature and air-pressure monitoring in a vertical borehole located in Pagany Wash, a normally dry stream-carved channel northeast of Yucca Mountain, Nevada, indicated that the annual temperature wave was measurable to a depth of 11.1 m. Temperature depressions were measured at depths of 3.1, 6.1, 9.2, and 11.1 m below ground surface. The temperature depressions were interpreted to be the result of infiltration associated with the 1997-1998 El Nino precipitation. A pressure differential, of approximately 2 kiloPascals, between stations located 11.1 and 24.5 m below ground surface was interpreted to be the result of compressed air ahead of the wetting front. The pressure differences between stations indicated that the wetting front migrated deeper than 35.2 m and that the Yucca Mountain Tuff retarded the downward movement of the wetting front. An analytical method indicated that the infiltration flux through the Pagany Wash alluvium due to the 1997-1998 El Nino precipitation was approximately 940 mm. A one-dimensional numerical model indicated that the infiltration flux was approximately 1000 mm. Sensitivity analysis indicated that the potential temperature decrease due to conduction was minimal and that cooler surface temperatures could not account for the measured subsurface temperature depressions.
Date: January 20, 2000
Creator: LeCain, G.D.; lu, N. & Kurzmack, M.
Partner: UNT Libraries Government Documents Department

SPECTROSCOPIC INVESTIGATION OF THE FORMATION OF RADIOLYSIS BY-PRODUCTS BY 13/9 MEV LINEAR ACCELERATOR OF ELECTRONS (LAE) IN SALT SOLUTIONS.

Description: In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in concentrated saline solution are of particular importance because the radiolysis of saline solutions results in oxidizing chlorine-containing species, which may oxidize actinide species to higher oxidation states. If the brines are irradiated, the solutions containing radiolytic species such as hypochlorite, hypochlorous acid or hydrogen peroxide, their pH and Eh may be altered. The oxidation and complexation states of actinides, which might be present in the salt brine, will change thus influencing their speciation and consequently their mobility. Furthermore, radiolytically formed oxidizing species such as ClO- or H2O2 may enhance the corrosion of the canister material. Therefore, radiation effects on salt brines must be integrated into the database, which described the chemical processes near a disposal site. Investigations in that context usually focus on the radiation chemistry of solid NaCl however our focus is on the radiolytic products, which are formed when salt brines are irradiated by a 10 MeV linear accelerator of electrons (LAE). We attempt to quantify the irradiation-induced formation of typical radiolysis by-products such as the hypochlorite ion (OCl-) by using a 13/9 MeV LAE with doses between 120 KGy to 216 KGy while monitoring the pH of the brine solutions
Date: January 1, 2001
Creator: Paviet-Hartmann, P. (Patricia); Dziewinski, J. J. (Jacek J.); Marczak, Stanislaw; Lu, N. (Ningping) & Walthall, M. (Mark)
Partner: UNT Libraries Government Documents Department

Simulation of radiolysis in the near field of a nuclear repository and the spectrophotometric investigation of the formation of radiolysis by-products by applying high energy beam-like experiments

Description: In the event of inundation of a nuclear waste repository located in a geological salt formation, chloride brines in contact with nuclear waste will be exposed to different kind of radiation depending on waste-form conditions. Ionizing radiations, however, have the ability to significantly affect the groundwater chemistry of the brines through the formation of free radicals, ionic- and molecular species; among them the typical byproducts of a-radiolysis: hypochlorite (OC1-) and hypochlorous acid (HOCl). In the absence of effects which arc supposed to dominate the redox conditions in the repository (corrosion of metals, microbial activity) the presence of OC1- is known to increase the redox potential of the brines and further to influence the stability of actinide waste-forms by accelerating their dissolution arid - most importantly - to oxidize actinides to their higlier oxidation states, whicli are gcncrally the most soluble ones. We are presenting a new approach to determine the radiation-induced formation rates of hypochlorite and hypochlorous acid as a first step to assess long-term steady-state repository conditions. To ovt:rcome the serious constraints of conventional radiocheinical work with GBq activity levels, we are simulating a-irradiation of chloride brines by the adaptation of ion-beam-line experiments. Therefore, we irradiate liquid chloride brine targets with 5 MeV protons, and 5 MeV helium ions. The irradiation-induced formation rates of OCX- and HOC1 were determined by UV-Vis spectrophotometry. To give an example, the measured G values for the HOCl formation in 3.7 M MgC12.6H20, pW 4.42, irradiated by 5 MeV protons was determined to be 0.0374 {+-} 0.0022, and 0.0536 {+-} 49 by irradiating with 5 MeV helium. The distinguished ltnowledge about the radiation-induced production of oxo-chloride species is the first step towards the assumption of their steady-state concentrations in the irradiation field of the repository.
Date: January 1, 2002
Creator: Hartmann, T. (Thomas); Paviet-Hartmann, P. (Patricia); Wetteland, C. J. (Christopher, J.); Lu, N. (Ningping); Ware, S. D. (Stuart D.) & Sage, S. (Sondra)
Partner: UNT Libraries Government Documents Department

A complete remediation process for a uranium-contaminated site and application to other sites

Description: During the summer of 1996 the authors were able to test, at the pilot scale, the concept of leaching uranium (U) from contaminated soils. The results of this pilot scale operation showed that the system they previously had developed at the laboratory scale is applicable at the pilot scale. The paper discusses these results, together with laboratory scale results using soil from the Fernald Environmental Management Project (FEMP), Ohio. These FEMP results show how, with suitable adaptations, the process is widely applicable to other sites. The purpose of this paper is to describe results that demonstrate remediation of uranium-contaminated soils may be accomplished through a leach scheme using sodium bicarbonate.
Date: December 31, 1998
Creator: Mason, C.F.V.; Lu, N.; Kitten, H.D.; Williams, M. & Turney, W.R.J.R.
Partner: UNT Libraries Government Documents Department

Strontium-85 and plutonium-239 sorption in rock samples from the Semipalatinsk Test Site, Kazakhstan

Description: The adsorption and desorption of strontium and plutonium were studied as a function of rock type and simulated ground waters from the Semipalatinsk Test Site (STS). Seven different rock types were obtained from the Balapan Region of the STS and were subjected to x-ray diffraction analyses. Two different ground waters were simulated using data supplied by the National Nuclear Center. The results indicate the sorption of strontium is strongly dependent on the minerals present in the rock species and on the total ionic strength of the ground water whereas, in all cases, plutonium was strongly irreversibly sorbed.
Date: March 1, 1999
Creator: Mason, C.F.V.; Lu, N.; Marusak, N.L.; Scheber, B.; Chipera, S.; Daukeyev, D. et al.
Partner: UNT Libraries Government Documents Department

Spectroscopic Investigation of the Formation of Radiolysis By-Products By 13/9 MeV Linear Accelerator of Electrons (LAE) in Salt Solutions

Description: In the near-field chemistry of a salt repository, the radiolytically-induced redox reactions in concentrated saline solution are of particular importance because the radiolysis of saline solutions results in oxidizing chlorine-containing species, which may oxidize actinide species to higher oxidation states. If the brines are irradiated, the solutions containing radiolytic species such as hypochlorite, hypochlorous acid or hydrogen peroxide, their pH and Eh may be altered. The oxidation and complexation states of actinides, which might be present in the salt brine, will change thus influencing their speciation and consequently their mobility. Furthermore, radiolytically formed oxidizing species such as ClO- or H2O2 may enhance the corrosion of the canister material. Therefore, radiation effects on salt brines must be integrated into the database, which described the chemical processes near a disposal site. Investigations in that context usually focus on the radiation chemistry of solid NaCl however our focus is on the radiolytic products, which are formed when salt brines are irradiated by a 10 MeV linear accelerator of electrons (LAE). We attempt to quantify the irradiation-induced formation of typical radiolysis by-products such as the hypochlorite ion (OCl-) by using a 13/9 MeV LAE with doses between 120 KGy to 216 KGy while monitoring the pH of the brine solutions.
Date: February 26, 2002
Creator: Paviet-Hartmann, P.; Dziewinski, J.; Hartmann, T.; Marczak, S.; Lu, N.; Walthall, M. et al.
Partner: UNT Libraries Government Documents Department

Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993); Volume 1

Description: Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: {open_quotes}wet{close_quotes} with a mean flux of 10 mm/yr, and {open_quotes}dry{close_quotes} with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a {open_quotes}hot repository{close_quotes}) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone.
Date: April 1, 1994
Creator: Wilson, M.L.; Gauthier, J.H.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E. et al.
Partner: UNT Libraries Government Documents Department

Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993); Volume 2

Description: Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: {open_quotes}wet{close_quotes} with a mean flux of 10 mm/yr, and {open_quotes}dry{close_quotes} with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a {open_quotes}hot repository{close_quotes}) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone.
Date: April 1, 1994
Creator: Wilson, M.L.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E.; Eaton, R.R. et al.
Partner: UNT Libraries Government Documents Department