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A DECONTAMINATION PROCESS FOR METAL SCRAPS FROM THE DECOMMISSIONING OF TRR

Description: A decontamination facility including surface condition categorizing, blasting, chemical/electrochemical cleaning, very low radioactivity measuring, and melting, is being established at INER. The facility will go into operation by the end of 2004. The main purpose is to clean the dismantled metal wastes from the decommissioning of Taiwan Research Reactor (TRR). The pilot test shows that over 70% of low level metal waste can be decontaminated to very low activity and can be categorized as BRC (below regulatory concern) waste. All the chemical decontamination technologies applied are developed by INER. In order to reduce the secondary wastes, chemical reagents will be regenerated several times with a selective precipitation method. The exhausted chemical reagent will be solidified with INER's patented process. The total secondary waste is estimated about 0.1-0.3 wt.% of the original waste. This decontamination process is accessed to be economic and feasible.
Date: February 27, 2003
Creator: Wei, T.Y.; Gan, J.S.; Lin, K.M. & Chung, Z.J.
Partner: UNT Libraries Government Documents Department

CHANGING RELEASE CRITERIA FROM PAST TO PRESENT

Description: Beginning with the decommissioning of nuclear power plants the release, criteria for radioactive materials has gained importance significantly. After decommissioning and dismantling, most of the residues need not be treated as radioactive waste, since they contain only small amounts of radioactivity. The Karlsruhe Research Center already dismantled two research reactors completely (the Karlstein Super Heated Steam Reactor and the Niederaichbach Nuclear Power Plant), while several additional decommissioning projects are currently in progress. About 70 % of the total waste mass within each project can be released from the area of atomic regulations and licenses. At the Niederaichbach and Karlstein sites the release procedures and the release criteria were determined in the decommissioning license, where issues such as controlling and release values were fixed. Additionally, each step of the release process has to be coordinated with the regulator. Today the general release criteria are contained in the atomic act. Depending on the nature of the material to be released (e.g. building structures or metallic waste), and depending on the further use of the material, such as unrestricted reuse or waste disposal, release values for each nuclide are established. To prepare the release of materials, a release plan including the release measurement results is sent to the regulator, who has to officially approve the concept.
Date: February 27, 2003
Creator: Graf, A. & Valencia, L.
Partner: UNT Libraries Government Documents Department

ANL technical support program for DOE Environmental Restoration and Waste Management. Annual report, October 1991--September 1992

Description: A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods.
Date: May 1, 1993
Creator: Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L. et al.
Partner: UNT Libraries Government Documents Department

New heavy proton radioactivities

Description: The new proton radioactivities {sup 165,166,167}Ir, {sup 171}Au, and {sup 185}Bi have been observed, extending our knowledge of proton radioactivity up to and beyond the Z=82 closed shell. For Z=77 and 79, the transitions can be explained using simple shell-model arguments. The case of {sup 185}Bi represents the first example of proton radioactivity from an intruder state.
Date: August 1, 1995
Creator: Davids, C.N.; Woods, P.J. & Batchelder, J.C.
Partner: UNT Libraries Government Documents Department

Radiological status report for the EBWR containment building. Volume 1: Summary and analysis

Description: At the conclusion of the EBWR D and D process, ANL Health Physics conducted a release survey to determine the radiological status of the facility. The primary goal of the survey was to verify that residual activities on building surfaces met DOE and ANL guidelines for downposting of a Radiologically Contaminated Area to a Radiologically Controlled Area. The resultant area was to bear no contamination designation, with no requirements for radiological personnel monitoring or protective clothing. ANL Health Physics designed a survey procedure, using a graded approach considering the building history, the D and D process, and the intended future use. The survey followed the general guidance of NRC NUREG/CR-5849, but simplified and reduced in scope to match the release goal. The building interior surfaces were divided into 15 principal survey units and one special survey unit. Each of the principal survey units had to meet the controlled release guidelines. The procedure consisted of dual full floor scans for beta/gamma activity, sampling measurements of total and removable alpha and beta/gamma activities, and background gamma exposure surveys. In the 15 principal survey units, surface activities were measured at a total of 444 locations. With the exception of certain excluded contaminated areas and mechanical equipment, the building interior meets the limited release guidelines.
Date: February 1, 1996
Creator: Murdoch, B.T.
Partner: UNT Libraries Government Documents Department

An introduction to the ENDF formats

Description: The ENDF Evaluated Nuclear Data Formats are used all over the world to encode nuclear data evaluations for use in research and nuclear technology. This report is an introduction to the formats and how they are used in modern compilations of nuclear data.
Date: November 1, 1998
Partner: UNT Libraries Government Documents Department

Development of proposed free release criteria for Idaho National Engineering Laboratory lead

Description: The INEL Lead Management Project (LMP) performed an investigation of the origin of lead used as shielding at the INEL and developed radiological profile information that was then used to establish a baseline for the DOE ``no-rad-added`` standard. Primary findings of the investigation include the following: (a) Much of the lead at the INEL was obtained from a DOE lead bank; (b) Lead inventory at the DOE lead bank was derived primarily from recycled sources and was most likely in the form of pure lead; (c) Secondary lead (lead from recycled sources), available in today`s market, is expected to have radiological characteristics similar to those of the DOE lead bank; (d) Highly sensitive radiological testing of 20 samples of lead from secondary sources revealed the lead to be radiologically pristine. Beta-, gamma-, and alpha-emitting radionuclide concentrations were all found to be less than detectable, except for a very small quantity of lead-210 (an alpha emitter), which is a naturally occurring isotope of lead. Based on the pristine nature of lead, a proposed free release criterion for lead was developed based on a statistical null hypothesis approach. The free release criterion compares the natural background count of a clean lead standard with the natural background count of a sample. When the sample background count cannot be distinguished as different from the standard background count at the 95% confidence level, then the sample is considered radiologically clean.
Date: December 31, 1994
Creator: Losinski, S.J.
Partner: UNT Libraries Government Documents Department

Radiological conditions at Naen, Yugui, Lomiulal, Kabelle and Mellu Islands in the northern half of Rongelap Atoll

Description: The data presented in the following tables is the total available for each northern island; they include both the data from the 1978 Northern Marshall Island Radiological Survey (NMIRS) and trips to Rongelap Atoll from 1986 through 1989. In one table we present the number of vegetation samples collected in the 1978 NMIRS and from 1986 through 1989. Again the majority of the {sup 137}Cs data is from the 1986-1989 trips. We have not made additional analyses of {sup 239+240}Pu, {sup 241}Am and {sup 90}Sr because the concentrations are very low and these radionuclides contribute less than 5% of an already very small dose. In another table we show the number of soil samples collected at each island in 1978 and the number collected since 1986. Most of the data are from 1986 through 1989. The major exception is {sup 90}Sr where all of the data are from the 1978 NMIRS. We have done some additional Pu analyses of surface soils (0-5 cm depth) in the northern islands. A significant amount of new data for {sup 137}Cs and {sup 241}Am have been generated from the samples collected from 1986 through 1989. The data are presented in the form of summary tables, graphics, detailed appendices and aerial photographs of the islands with the sample locations marked. The identified sample locations from the 1978 NMIRS will be added later.
Date: March 1, 1996
Creator: Robison, W.L. & Conrado, C.L.
Partner: UNT Libraries Government Documents Department

Radioactive Waste Management information for 1994 and record-to-date

Description: This document, Radioactive Waste Management Information for 1994 and Record-To-Date, contains computerized radioactive waste data records from the Idaho National Engineering Laboratory (INEL). Data are compiled from information supplied by the US Department of Energy (DOE) contractors. Data listed are on airborne and liquid radioactive effluents and solid radioactive waste that is stored, disposed, and sent to the INEL for reduction. Data are summarized for the years 1952 through 1993. Data are detailed for the calendar year 1994.
Date: July 1, 1995
Creator: French, D.L.; Lisee, D.J. & Taylor, K.A.
Partner: UNT Libraries Government Documents Department

Argonne National Laboratory-East summary site environmental report for calendar year 2000.

Description: This booklet explains major portions of the ongoing environmental monitoring program conducted by Argonne National Laboratory-East in the calendar year 2000. The full Site Environmental Report, written by N.W. Golchert, R.G. Kolzow and L.P. Moos, can be obtained by contacting Argonne National Laboratory in Argonne, Illinois, 60439, or by going to the Web site (www.anl.gov). This booklet includes descriptions of the Argonne-East site, missions and programs; the status of compliance with environmental regulations; environmental protection and restoration activities; current projects; past, present and potential problems and the monitoring program for air, water and radioactivity in the area. ''The policy of Argonne National Laboratory is that its activities are to be conducted in such a manner that worker and public health and safety and protection of the environment are given the highest priority.'' The environmental surveillance program conducts regular monitoring for radiation, radioactive materials and nonradiological materials on the Argonne-East site and in the surrounding region. The detection of such releases to the environment is of great importance. If a release occurs, the monitoring program clearly identifies the substance, its magnitude and its origin. Programs and controls are set up to eliminate, contain or remove the substance from the environment. Argonne is able to determine the effectiveness of its own pollution control and remedial activities.
Date: January 14, 2002
Creator: Golchert, N. W. & Kolzow, R. G.
Partner: UNT Libraries Government Documents Department

An approach for dealing with large errors.

Description: Numerical functions or equivalent algorithms are commonly used to derive estimates for physical quantities that can be expressed in terms of more fundamental physical parameters. It is shown that in situations where large uncertainties (errors) are involved in these parameters, or where error amplification occurs through severe non-linearity of the functions, conventional deterministic techniques for calculating the derived quantities and estimating their errors can lead to erroneous results. Instead, it is necessary to resort to a probabilistic approach and thereby obtain estimates for mean values and variances of the derived quantities through Monte Carlo simulation in order to preserve the essential information without distortion. The correct choice for a probability distribution is suggested by the inherent nature of the random variable in question. Examples are given from the analysis of radioactivity decay, the shielding of penetrating radiation, and the derivation of nuclear reaction rates that are used in astrophysical calculations to model nucleosynthesis of the elements in stellar explosions. Subsequent analyses that use these derived quantities must also be carried out in a probabilistic manner to insure that the obtained results will reflect the underlying information properly.
Date: October 17, 2001
Creator: Smith, D. L.; Naberejnev, D. G. & Van Wormer, L. A.
Partner: UNT Libraries Government Documents Department

Gamma analysis of environmental samples from the Marshall Islands

Description: Radiological studies of the fate of nuclear test related debris in the Marshall Islands conducted by members of the Lawrence Livermore National Laboratory generate large number of environmental samples. For more than 20 years, the Low-Level Gamma Spectroscopy Facility has been used to perform the analysis of gamma emitting radionuclides. A brief description of the facility, calibration, counting and analysis procedures is given.
Date: September 1, 1995
Creator: Brunk, J.L.
Partner: UNT Libraries Government Documents Department

A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites

Description: The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for {alpha}, {beta} and {gamma} emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for {gamma} and {alpha}/{beta} monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in {alpha}/{beta} liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure {sup 241}Am produced from {sup 241}Pu by {beta} decay. Because {sup 241}Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., {sup 137}Cs).
Date: May 26, 1995
Creator: Rego, J. H.; Smith, D. K. & Friensehner, A. V.
Partner: UNT Libraries Government Documents Department

Environmental Report 1994, Volume No. 1

Description: Lawrence Livermore National Laboratory (LLNL), a U.S. Department of Energy (DOE) facility operated by the University of California, serves as a national resource of scientific, technical, and engineering capability. The Laboratory`s mission focuses on nuclear weapons and national security, and over the years has been broadened to include areas such as strategic defense, energy, the environment, biomedicine, technology transfer, the economy, and education. The Laboratory carries out this multifaceted mission in compliance with local, state, and federal environmental regulatory requirements. It does so with the support of the Environmental Protection Department, which is responsible for environmental monitoring and analysis, hazardous waste management, environmental restoration, and ensuring compliance with environmental laws and regulations. LLNL comprises two sites: the Livermore site and Site 300. The Livermore site occupies an area of 3.28 square kilometers on the eastern edge of Livermore, California. Site 300, LLNL`s experimental testing site, is located 24 kilometers to the east in the Altamont Hills, and occupies an area of 30.3 square kilometers. Environmental monitoring activities are conducted at both sites as well as in surrounding areas. This summary provides an overview of LLNL`s environmental activities in 1994, including radiological and nonradiological sampling and surveillance monitoring, remediation, assessment of radiological releases and doses, and determination of the impact of LLNL operations on the environment and public health.
Date: September 1, 1995
Creator: Rath, K.S.; Harrach, R.J.; Gallegos, G.M. & Failor, R.A.
Partner: UNT Libraries Government Documents Department

Soil-Related Input Parameters for the Biosphere Model

Description: This report presents one of the analyses that support the Environmental Radiation Model for Yucca Mountain Nevada (ERMYN). The ''Biosphere Model Report'' (BSC 2004 [DIRS 169460]) describes the details of the conceptual model as well as the mathematical model and the required input parameters. The biosphere model is one of a series of process models supporting the postclosure Total System Performance Assessment (TSPA) for the Yucca Mountain repository. A schematic representation of the documentation flow for the Biosphere input to TSPA is presented in Figure 1-1. This figure shows the evolutionary relationships among the products (i.e., analysis and model reports) developed for biosphere modeling, and the biosphere abstraction products for TSPA, as identified in the ''Technical Work Plan for Biosphere Modeling and Expert Support'' (TWP) (BSC 2004 [DIRS 169573]). This figure is included to provide an understanding of how this analysis report contributes to biosphere modeling in support of the license application, and is not intended to imply that access to the listed documents is required to understand the contents of this report. This report, ''Soil-Related Input Parameters for the Biosphere Model'', is one of the five analysis reports that develop input parameters for use in the ERMYN model. This report is the source documentation for the six biosphere parameters identified in Table 1-1. The purpose of this analysis was to develop the biosphere model parameters associated with the accumulation and depletion of radionuclides in the soil. These parameters support the calculation of radionuclide concentrations in soil from on-going irrigation or ash deposition and, as a direct consequence, radionuclide concentration in other environmental media that are affected by radionuclide concentrations in soil. The analysis was performed in accordance with the TWP (BSC 2004 [DIRS 169573]) where the governing procedure was defined as AP-SIII.9Q, ''Scientific Analyses''. This analysis revises the previous ...
Date: September 9, 2004
Creator: Smith, A. J.
Partner: UNT Libraries Government Documents Department

Population exposure dose reconstruction for the Urals Region

Description: This presentation describes the first preliminary results of an ongoing joint Russian-US pilot feasibility study. Many people participated in workshops to determine what Russian and United States scientists could do together in the area of dose reconstruction in the Urals population. Most of the results presented here came from a joint work shop in St. Petersburg, Russia (11-13 July 1995). The Russians at the workshop represented the Urals Research Center for Radiation Medicine (URCRM), the Mayak Industrial Association, and Branch One of the Moscow Biophysics Institute. The US Collaborators were Dr. Anspaugh of LLNL, Dr. Nippier of PNL, and Dr. Bouville of the National Cancer Institute. The objective of the first year of collaboration was to look at the source term and levels of radiation contamination, the historical data available, and the results of previous work carried out by Russian scientists, and to determine a conceptual model for dose reconstruction.
Date: June 1, 1996
Creator: Degteva, M.O.; Kozheurov, V.P.; Vorobiova, M.I.; Burmistrov, D.S.; Khokhryakov, V.V.; Suslova, K.G. et al.
Partner: UNT Libraries Government Documents Department

Signatures of testing: On-site inspection technologies

Description: This paper describes the phenomenology of nuclear explosions and technologies for their detection as relevant to On-Site Inspection (OSI) for a comprehensive test-ban (CTB). Our experience with the US nuclear test program which has been primarily carried out at the Nevada Test Site (NTS) and in the Pacific Ocean. The goals of OSI are to resolve ambiguous events, reduce uncertainty, deter attempts at evasion, and provide responsive and technically competent means of confirming the occurrence of a nuclear explosion should deterrence fail. These goals would include finding evidence of an evasive nuclear explosion or evidence that the event was non-nuclear, such as an earthquake or large chemical explosion.
Date: January 1, 1995
Creator: Zucca, J.J.; Carrigan, C.; Goldstein, P.; Jarpe, S.P.; Sweeney, J.; Pickles, W.L. et al.
Partner: UNT Libraries Government Documents Department

Environmental surveillance at Los Alamos during 1994

Description: This report describes environmental monitoring activities at Los Alamos National Laboratory for 1994. Data were collected to assess external penetrating radiation, airborne emissions, liquid effluents, radioactivity of environmental materials and food stuffs, and environmental compliance.
Date: July 1, 1996
Partner: UNT Libraries Government Documents Department

Table of DOE-STD-1027-92 Hazard Category 3 threshold quantities for the ICRP-30 list of 757 radionuclides: LANL fact sheet

Description: A table of DOE-STD-1027-92 Hazard Category 3 threshold quantities, in units of curies and grams, is presented for the International Commission on Radiological Protection-30 (ICRP-30) list of 757 radionuclides. The specific activity (Ci/gm) used to convert the threshold quantities from curies to grams is also calculated and tabulated. The half-life values used to generate the specific activities are those specified in ICRP-30.
Date: August 1, 1995
Creator: Clow, J.; Elder, J.; Heindel, G.; Inkret, W. & Miller, G.
Partner: UNT Libraries Government Documents Department

Assessment of the important radionuclides in nuclear waste

Description: The relative importance of the various radionuclides contained in nuclear waste has been assessed by consideration of (1) the quantity of each radionuclide present, (2) the Environmental Protection Agency`s release limits for radionuclides, (3) how retardation processes such as solubility and sorption affect radionuclie transport, and (4) the physical and chemical forms of radionuclides in the waste. Three types of waste were reviewed: spent fuel, high-level waste, and defense high-level waste. Conditions specific to the Nevada Nuclear Waste Storage Investigations project potential site at Yucca Mountain were used to describe radionuclide transport. The actinides Am, Pu, Np, and U were identified as the waste elements for which solubility and sorption data were most urgently needed. Other important waste elements were identified as Sr, Cs, C, Ni, Zr, Tc, Th, Ra, and Sn. Under some conditions, radionuclides of three elements (C, Tc, and I) may have high solubility and negligible sorption. The potential for transport of some waste elements (C and I) in the gas phase must also be evaluated for the Yucca Mountain Site. 12 refs., 17 tabs.
Date: October 1, 1985
Creator: Kerrisk, J.F.
Partner: UNT Libraries Government Documents Department

Background Radioactivity in River and Reservoir Sediments near Los Alamos, New Mexico

Description: As part of its continuing Environmental Surveillance Program, regional river and lake-bottom sediments have been collected annually by Los Alamos National Laboratory (the Laboratory) since 1974 and 1979, respectively. These background samples are collected from three drainage basins at ten different river stations and five reservoirs located throughout northern New Mexico and southern Colorado. Radiochemical analyses for these sediments include tritium, strontium-90, cesium-137, total uranium, plutonium-238, plutonium-239,-240, americium-241, gross alpha, gross beta, and gross gamma radioactivity. Detection-limit radioactivity originates as worldwide fallout from aboveground nuclear weapons testing and satellite reentry into Earth's atmosphere. Spatial and temporal variations in individual analyte levels originate from atmospheric point-source introductions and natural rate differences in airborne deposition and soil erosion. Background radioactivity values on sediments reflect this variability, and grouped river and reservoir sediment samples show a range of statistical distributions that appear to be analyte dependent. Traditionally, both river and reservoir analyte data were blended together to establish background levels. In this report, however, we group background sediment data according to two criteria. These include sediment source (either river or reservoir sediments) and station location relative to the Laboratory (either upstream or downstream). These grouped data are statistically evaluated through 1997, and background radioactivity values are established for individual analytes in upstream river and reservoir sediments. This information may be used to establish the existence and areal extent of trace-level environmental contamination resulting from historical Laboratory research activities since the early 1940s.
Date: May 5, 2002
Creator: McLin, Stephen G. & Lyons, Dale W.
Partner: UNT Libraries Government Documents Department

Radionuclide and heavy metal concentrations in soil, vegetation, and fish collected around and within Tsicoma Lake in Santa Clara Canyon

Description: Radionuclide ({sup 3}H, {sup 90}Sr, {sup 137}Cs, {sup 238}Pu, {sup 239}Pu, total U) and heavy metal (Ag, As, Ba, Be, Cd, Cr, Hg, Ni, Pb, Sb, Se, Tl) contents were determined in soil, vegetation (overstory and understory), and fish (rainbow trout) collected around and within Tsicoma Lake in Santa Clara Canyon in 1995. All heavy metal and most radionuclide contents around or within the lake, except for U in soil, vegetation, and fish, were within or just above upper limit background. Detectable levels (where the analytical result was greater than two times counting uncertainty) of U in soils, vegetation, and fish were found in slightly higher concentrations than in background samples. Overall, however, maximum total committed effective dose equivalent (CEDE)(95% confidence level)--based on consumption of 46 lb of fish--from Tsicoma Lake (0.066 mrem/y) was within the maximum total CEDE from the ingestion of fish from the Mescalero National Fish Hatchery (background)(0.113 mrem/y).
Date: March 1, 1996
Creator: Fresquez, P.R.; Armstrong, D.R. & Naranjo, L. Jr.
Partner: UNT Libraries Government Documents Department

Current status and features of the T-2 Nuclear Information Service

Description: This service is run by Group T-2 (Nuclear Theory and Applications) of the Theoretical Division of the Los Alamos National Laboratory, which is operated by the University of California for the US Department of Energy. The author works on nuclear modeling, nuclear data, cross sections, nuclear masses, ENDF, NJOY data processing, nuclear astrophysics, radioactivity, radiation shielding, data for medical radiotherapy, data for high-energy accelerator applications, data and codes for fission and fusion systems, and more. For an introduction to the field of nuclear data and his site, take his Guided Tour. Much of this information can also be accessed using anonymous ftp t2.lanl.gov.
Date: April 24, 1998
Creator: MacFarlane, R.E.
Partner: UNT Libraries Government Documents Department

Laboratory and field studies related to the radionuclide migration project. Progress report, October 1, 1980-September 30, 1981

Description: FY 1981 laboratory and field studies related to the Radionuclide Migration project are described. Results are presented for radiochemical analyses of water samples collected from the RNM-1 well and the RNM-2S satellite well at the Cambric site. Data are included for tritium, {sup 85}Kr, {sup 129}I, and {sup 36}Cl. The maximum-concentration tritium, peak appears to have arrived at RNM-2S near the end of FY-1981. Laboratory studies emphasize the sorptive behavior of alluvium and tuff and its dependence on mineralogy. Results from batch measurements and crushed-rock and whole-core column studies are presented.
Date: February 1, 1982
Creator: Daniels, W.R. (comp.)
Partner: UNT Libraries Government Documents Department