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The Use of Radar Methods to Determine Moisture Content in the Vadose Zone

Description: Water content is a critical parameter affecting both liquid-phase and vapor-phase contaminant transport in the vadose zone. This means that accurate estimate of in situ water content must be obtained in order to design for the appropriate handling or remediation of a contaminated region of the vadose zone. Traditional methods of sampling the subsurface by drilling and/or direct sampling are very time consuming, limited in terms of spatial coverage, and have the associated risk of contacting and increasing the size of the contaminated area. One solution is to use geophysical methods which can provide a high-resolution, non-invasive means of sampling or imagin the subsurface.
Date: December 28, 2003
Creator: Knight, Rosemary
Partner: UNT Libraries Government Documents Department

Radionuclide Inventory and Distribution Program: the Galileo area

Description: The Galileo area is the first region of the Nevada Test Site to be surveyed by the Radionuclide Inventory and Distribution Program (RIDP). This report describes in detail the use of soil sampling and in situ spectrometry to estimate radionuclide activities at selected sampling locations; the descriptions of these methods will be used as a reference for future RIDP reports. The data collected at Galileo were analyzed by kriging and the polygons of influence method to estimate the total inventory and the distribution of six man-made radionuclides. The results of the different statistical methods agree fairly well, although the data did not give very good estimates of the variogram for kriging, and further study showed the results of kriging to be highly dependent on the variogram parameters. The results also showed that in situ spectrometry gives better estimates of radionuclide activity than soil sampling, which tends to miss highly radioactive particles associated with vegetation. 18 references, 28 figures, 11 tables.
Date: December 28, 1983
Creator: McArthur, R.D. & Kordas, J.F.
Partner: UNT Libraries Government Documents Department

Transport Test Problems for Hybrid Methods Development

Description: This report presents 9 test problems to guide testing and development of hybrid calculations for the ADVANTG code at ORNL. These test cases can be used for comparing different types of radiation transport calculations, as well as for guiding the development of variance reduction methods. Cases are drawn primarily from existing or previous calculations with a preference for cases which include experimental data, or otherwise have results with a high level of confidence, are non-sensitive, and represent problem sets of interest to NA-22.
Date: December 28, 2011
Creator: Shaver, Mark W.; Miller, Erin A.; Wittman, Richard S. & McDonald, Benjamin S.
Partner: UNT Libraries Government Documents Department

Responses to TSP Directive 92-2: Summary report

Description: This report describes problems, delays, and development of computer codes for use in the Hanford Environmental Dose Reconstruction Project.
Date: December 28, 1992
Partner: UNT Libraries Government Documents Department

(Radiological assessments of radionuclide releases)

Description: As a consequence of the Chernobyl accident, data have been obtained throughout the Northern Hemisphere on the concentrations of radionuclides in air, vegetation, soil, water, and foodstuffs that could be important means of human exposure. At the IAEA's invitation, the traveler reviewed recently published data and handbook summaries. The traveler evaluated the need for revising the default values recommended in Chapter 5, Terrestrial and Aquatic Food Chain Transport,'' of IAEA Safety Series No. 57. All attempts at revision were made to keep the mathematical complexity of the models to a minimum without substantial underestimation of dose to critical population subgroups. The traveler also served as chairman of the Multiple Pathways Working Group of the Coordinated Research Program on VAMP. This group has been established to test predictions of models assessing multiple exposure pathways potentially leading to human exposure to {sup 137}Cs. Testing is carried out for major components of assessment models that predict deposition, environmental transport, food chain bioaccumulation, and subsequent uptake and retention in the human body and dose due to exposure to external gamma radiation.
Date: December 28, 1990
Creator: Hoffman, F.O.
Partner: UNT Libraries Government Documents Department

The trend of contamination in the air, the Columbia River, rain, sanitary water, vegetation, and wastes, at the Hanford Works for the period July, August, September 1947

Description: This report summarizes the contamination observed at the Hanford Works and vicinity for the period July, August, and September, 1947. Daily or weekly trends for all sampling locations as included in previous reports are omitted except in those cases where a true trend can be established. Statistical analysis to determine significant values and differences is used whenever possible. The report is divided into the following topic sections: meteorological -- wind conditions; extent of beta contamination in air and radiation level in air; extent of contamination in the Columbia River; extent of beta contamination in rain; extent of alpha and beta contamination in sanitary water; extent of beta contamination on vegetation; and the extent of contamination in Hanford Wastes. An appraisal and review of all the results is considered in detail for each section.
Date: December 28, 1947
Creator: Singlevich, W.
Partner: UNT Libraries Government Documents Department

Responses to TSP Directive 92-2: Summary report

Description: This report describes problems, delays, and development of computer codes for use in the Hanford Environmental Dose Reconstruction Project.
Date: December 28, 1992
Partner: UNT Libraries Government Documents Department

Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)

Description: This document is the Health and Safety Plan (HASP) for the demonstration of IITRI`s EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85{degrees} to 95{degrees}C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area.
Date: December 28, 1994
Creator: Dev, H.
Partner: UNT Libraries Government Documents Department

Disruptive Event Biosphere Doser Conversion Factor Analysis

Description: The purpose of this report was to document the process leading to, and the results of, development of radionuclide-, exposure scenario-, and ash thickness-specific Biosphere Dose Conversion Factors (BDCFs) for the postulated postclosure extrusive igneous event (volcanic eruption) at Yucca Mountain. BDCF calculations were done for seventeen radionuclides. The selection of radionuclides included those that may be significant dose contributors during the compliance period of up to 10,000 years, as well as radionuclides of importance for up to 1 million years postclosure. The approach documented in this report takes into account human exposure during three different phases at the time of, and after, volcanic eruption. Calculations of disruptive event BDCFs used the GENII-S computer code in a series of probabilistic realizations to propagate the uncertainties of input parameters into the output. The pathway analysis included consideration of different exposure pathway's contribution to the BDCFs. BDCFs for volcanic eruption, when combined with the concentration of radioactivity deposited by eruption on the soil surface, allow calculation of potential radiation doses to the receptor of interest. Calculation of radioactivity deposition is outside the scope of this report and so is the transport of contaminated ash from the volcano to the location of the receptor. The integration of the biosphere modeling results (BDCFs) with the outcomes of the other component models is accomplished in the Total System Performance Assessment (TSPA), in which doses are calculated to the receptor of interest from radionuclides postulated to be released to the environment from the potential repository at Yucca Mountain.
Date: December 28, 2000
Creator: Wasiolek, M.
Partner: UNT Libraries Government Documents Department