Environmental evaluation of alternatives for long-term management of Defense high-level radioactive wastes at the Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

1982-09-01

The U.S. Department of Energy (DOE) is considering the selection of a strategy for the long-term management of the defense high-level wastes at the Idaho Chemical Processing Plant (ICPP). This report describes the environmental impacts of alternative strategies. These alternative strategies include leaving the calcine in its present form at the Idaho National Engineering Laboratory (INEL), or retrieving and modifying the calcine to a more durable waste form and disposing of it either at the INEL or in an offsite repository. This report addresses only the alternatives for a program to manage the high-level waste generated at the ICPP. 24 figures, 60 tables.

Environmental evaluation of alternatives for long-term management of Defense high-level radioactive wastes at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

1982-09-01

The U.S. Department of Energy (DOE) is considering the selection of a strategy for the long-term management of the defense high-level wastes at the Idaho Chemical Processing Plant (ICPP). This report describes the environmental impacts of alternative strategies. These alternative strategies include leaving the calcine in its present form at the Idaho National Engineering Laboratory (INEL), or retrieving and modifying the calcine to a more durable waste form and disposing of it either at the INEL or in an offsite repository. This report addresses only the alternatives for a program to manage the high-level waste generated at the ICPP. 24 figures, 60 tables

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Energy Technology Data Exchange (ETDEWEB)

M. D. Staiger

2007-06-01

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

Ecological vectors of radionuclide transport at a solid radioactive waste disposal facility in southeastern Idaho

International Nuclear Information System (INIS)

Arthur, W.J.; Markham, O.D.

1983-01-01

Radioecological research conducted at the Idaho National Engineering Laboratory Subsurface Disposal Area (SDA) has estimated the quantity of radionuclides transported by various ecosystem components and evaluated the impact of subsurface disposal of radioactive waste on biotic species inhabiting the area. Radiation dose rates received by small mammals ranged from 0.4 to 41790 mrad/day. Small mammal soil burrowing was an upward transport mechanism for transuranic radionuclides. Seventy-seven uCi of radioactivity occurred in SDA vegetation annually. None of these ecological vectors contributed appreciable quantities of radioactive contamination to the environment surrounding the SDA

Characterizing aquifer hydrogeology and anthropogenic chemical influences on groundwater near the Idaho Chemical Processing Plant, Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Fromm, J.M.

1995-01-01

A conceptual model of the Eastern Snake River Plain aquifer in the vicinity of monitoring well USGS-44, downgradient of the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL), was developed by synthesis and comparison of previous work (40 years) and new investigations into local natural hydrogeological conditions and anthropogenic influences. Quantitative tests of the model, and other recommendations are suggested. The ICPP recovered fissionable uranium from spent nuclear fuel rods and disposed of waste fluids by release to the regional aquifer and lithosphere. Environmental impacts were assessed by a monitoring well network. The conceptual model identifies multiple, highly variable, interacting, and transient components, including INEL facilities multiple operations and liquid waste handling, systems; the anisotropic, in homogeneous aquifer; the network of monitoring and production wells, and the intermittent flow of the Big Lost River. Pre anthropogenic natural conditions and early records of anthropogenic activities were sparsely or unreliably documented making reconstruction of natural conditions or early hydrologic impacts impossible or very broad characterizations

Summary of the engineering assessment of radioactive sands and residues, Lowman Site, Lowman, Idaho

International Nuclear Information System (INIS)

1981-09-01

Ford, Bacon and Davis Utah Inc. has reevaluated the Lowman site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive sands and residues at Lowman, Idaho. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of radioactive sands and residues and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 191,000 tons of radioactive sands, residues, and contaminated soils at the Lowman site constitutes the most significant environmental impact, although windblown radioactive sands and external gamma radiation also are factors

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

Disposal of defense spent fuel and HLW from the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Ermold, L.F.; Loo, H.H.; Klingler, R.D.; Herzog, J.D.; Knecht, D.A.

1992-12-01

Acid high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage ate the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal

Idaho Chemical Processing Plant spent fuel and waste management technology development program plan: 1994 Update

International Nuclear Information System (INIS)

1994-09-01

The Department of Energy has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until April 1992, the major activity of the ICPP was the reprocessing of SNF to recover fissile uranium and the management of the resulting high-level wastes (HLW). In 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the continued safe management and disposition of SNF and radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3,800 cubic meters of calcine waste, and 289 metric tons heavy metal of SNF are in inventory at the ICPP. Disposal of SNF and high-level waste (HLW) is planned for a repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP spent Fuel and Waste Management Technology Development Program (SF ampersand WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will be properly stored and prepared for final disposal in accordance with regulatory drivers. This Plan presents a brief summary of each of the major elements of the SF ampersand WMTDP; identifies key program assumptions and their bases; and outlines the key activities and decisions that must be completed to identify, develop, demonstrate, and implement a process(es) that will properly prepare the SNF and radioactive wastes stored at the ICPP for safe and efficient interim storage and final disposal

Idaho Chemical Processing Plant Process Efficiency improvements

International Nuclear Information System (INIS)

Griebenow, B.

1996-03-01

In response to decreasing funding levels available to support activities at the Idaho Chemical Processing Plant (ICPP) and a desire to be cost competitive, the Department of Energy Idaho Operations Office (DOE-ID) and Lockheed Idaho Technologies Company have increased their emphasis on cost-saving measures. The ICPP Effectiveness Improvement Initiative involves many activities to improve cost effectiveness and competitiveness. This report documents the methodology and results of one of those cost cutting measures, the Process Efficiency Improvement Activity. The Process Efficiency Improvement Activity performed a systematic review of major work processes at the ICPP to increase productivity and to identify nonvalue-added requirements. A two-phase approach was selected for the activity to allow for near-term implementation of relatively easy process modifications in the first phase while obtaining long-term continuous improvement in the second phase and beyond. Phase I of the initiative included a concentrated review of processes that had a high potential for cost savings with the intent of realizing savings in Fiscal Year 1996 (FY-96.) Phase II consists of implementing long-term strategies too complex for Phase I implementation and evaluation of processes not targeted for Phase I review. The Phase II effort is targeted for realizing cost savings in FY-97 and beyond

Hydrologic data for the Idaho National Engineering Laboratory site, Idaho

International Nuclear Information System (INIS)

Barraclough, J.T.; Jensen, R.G.

1976-01-01

The Idaho Chemical Processing Plant (ICPP) discharges low-level waste and chemical waste directly to the Snake River Plain aquifer through a 600-foot (180 meter) disposal well. Most of the radioactivity is removed by distillation and ion exchange prior to being discharged into the well. During 1971 to 1973, the well was used to dispose of 404 curies of radioactivity, of which 389 curies were tritium (96 percent). The average yearly discharge was about 300 million gallons (1.1 x 10 9 liters). The distribution of waste products in the Snake River Plain aquifer covers about 15 square miles (30 square kilometers). Since disposal began in 1952, the wastes have migrated about 5 miles (8 kilometers) downgradient from discharge points. The perched ground-water body contains tritium, chromium-51, cobalt-60, and strontium-90. Radionuclides are subject to radioactive decay, sorption, and dilution by dispersion in the aquifer. Chemical wastes are subject to sorption and dilution by dispersion. Waste plumes south of the ICPP containing tritium, sodium, and chloride have been mapped and all cover a similar area. The plumes follow generally southerly flow lines and are widely dispersed in the aquifer. The waste plume of strontium-90 covers a much smaller area of the aquifer, about 1.5 square miles (4 square kilometers). Based on the relatively small size of the plume, it would appear that the strontium-90 is sorbed from solution as it moves through the Snake River Plain aquifer

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste

International Nuclear Information System (INIS)

Porter, C.L.; Widmayer, D.A.

1995-09-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities

Development of waste minimization and decontamination technologies at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Ferguson, R.L.; Archibald, K.E.; Demmer, R.L.

1995-01-01

Emphasis on the minimization of decontamination secondary waste has increased because of restrictions on the use of hazardous chemicals and Idaho Chemical Processing Plant (ICPP) waste handling issues. The Lockheed Idaho Technologies Co. (LITCO) Decontamination Development Subunit has worked to evaluate and introduce new performed testing, evaluations, development and on-site demonstrations for a number of novel decontamination techniques that have not yet previously been used at the ICPP. This report will include information on decontamination techniques that have recently been evaluated by the Decontamination Development Subunit

Hydrologic conditions at the Idaho National Engineering Laboratory, Idaho - emphasis: 1974-1978

International Nuclear Information System (INIS)

Barraclough, J.T.; Lewis, B.D.; Jensen, R.G.

1982-09-01

The Idaho National Engineering Laboratory (INEL) site covers about 890 square miles of the eastern Snake River Plain and overlies the Snake River Plain aquifer. Low concentrations of aqueous chemical and radioactive wastes have been discharged to shallow ponds and to shallow or deep wells on the site since 1952. A large body of perched ground water has formed in the basalt underlying the waste disposal ponds in the Test Reactor Area. This perched zone contains tritium, chromium-51, cobalt-60, strontium-90, and several nonradioactive ions. Tritium is the only mappable waste constituent in that portion of the Snake River Plain aquifer directly underlying this perched zone. Low concentrations of chemical and low-level radioactive wastes enter directly into the Snake River Plain aquifer through the Idaho Chemical Processing Plant (ICPP) disposal well. Tritium has been discharged to the well since 1953 and has formed the largest waste plume, about 28 square miles in area, in the regional aquifer, and minute concentrations have migrated downgradient a horizontal distance of 7.5 miles. Other waste plumes south of the ICPP contain sodium, chloride, nitrate, and the resultant specific conductance. These plumes have similar configurations and flow southward; the contaminants are in general laterally dispersed in that portion of the aquifer underlying the INEL. Other waste plumes, containing strontium-90 and iodine-129, cover small areas near their points of discharge because strontium-90 is sorbed from solution as it moves through the aquifer and iodine-129 is discharged in very low quantities. Cesium-137 is also discharged through the well but it is strongly sorbed from solution and has never been detected in a sample of ground water at the INEL

In-can melting demonstration of wastes from the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Bjorklund, W.J.; Chick, L.A.; Hollis, H.H.; Mellinger, G.B.; Nelson, T.A.; Petkus, L.L.

1980-07-01

The immobilization of Idaho Chemical Processing Plant (ICPP) zirconia calcine using Idaho glass composition (ICPP-127) was evaluated at Pacific Northwest Laboratory (PNL) in two engineering-scale in-can melter tests. The glass was initially characterized in the laboratory to verify processing parameters. Glass was then produced in a pilot-scale melter and then in a full-scale melter to evaluate the processing and the resultant product. Potential corrosion problems were identified with the glass and some processing problems were encountered, but neither is insurmountable. The product is a durable leach-resistant glass. The glass appears to be nonhomogeneous, but chemically it is quite uniform

Summaries of the Idaho National Engineering Laboratory Site ecological studies information meeting held at Idaho Falls, July 10--11, 1975

International Nuclear Information System (INIS)

Markham, O.D.

1976-04-01

Brief summaries are presented for 30 papers that discuss the ecology of plants, wild animals, and birds on the Idaho National Engineering Laboratory site. Eleven of the papers report the results of studies on the diffusion of radioactive wastes in the environment and measurements of the content of various radionuclides in the tissues of animals and plants, soil, waste water leaching ponds, and aquifers. Two papers discuss the diffusion of chemical effluents in the environment

Mineralogical correlation of surficial sediment from area drainages with selected sedimentary interbeds at the Idaho National Engineering Laboratory, Idaho

Energy Technology Data Exchange (ETDEWEB)

Bartholomay, R.C.

1990-08-01

Ongoing research by the US Geological Survey at the INEL involves investigation of the migration of radioactive elements contained in low-level radioactive waste, hydrologic and geologic factors affecting waste movement, and geochemical factors that influence the chemical composition of the waste. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal. The US Geological Surveys project office at the Idaho National Engineering Laboratory, in cooperation with the US Department of Energy, used mineralogical data to correlate surficial sediment samples from the Big Lost River, Little Lost River, and Birch Greek drainages with selected sedimentary interbed core samples taken from test holes at the RWMC (Radioactive Waste Management Complex), TRA (Test Reactors Area), ICPP (Idaho Chemical Processing Plant), and TAN (Test Area North). Correlating the mineralogy of a particular present-day drainage area with a particular sedimentary interbed provides information on historical source of sediment for interbeds in and near the INEL. Mineralogical data indicate that surficial sediment samples from the Big Lost River drainage contained a larger amount of feldspar and pyroxene and a smaller amount of calcite and dolomite than samples from the Little Lost River and Birch Creek drainages. Mineralogical data from sedimentary interbeds at the RWMC, TRA, and ICPP correlate with surficial sediment of the present-day big Lost River drainage. Mineralogical data from a sedimentary interbed at TAN correlate with surficial sediment of the present-day Birch Creek drainage. 13 refs., 5 figs., 3 tabs.

Mineralogical correlation of surficial sediment from area drainages with selected sedimentary interbeds at the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Bartholomay, R.C.

1990-08-01

Ongoing research by the US Geological Survey at the INEL involves investigation of the migration of radioactive elements contained in low-level radioactive waste, hydrologic and geologic factors affecting waste movement, and geochemical factors that influence the chemical composition of the waste. Identification of the mineralogy of the Snake River Plain is needed to aid in the study of the hydrology and geochemistry of subsurface waste disposal. The US Geological Surveys project office at the Idaho National Engineering Laboratory, in cooperation with the US Department of Energy, used mineralogical data to correlate surficial sediment samples from the Big Lost River, Little Lost River, and Birch Greek drainages with selected sedimentary interbed core samples taken from test holes at the RWMC (Radioactive Waste Management Complex), TRA (Test Reactors Area), ICPP (Idaho Chemical Processing Plant), and TAN (Test Area North). Correlating the mineralogy of a particular present-day drainage area with a particular sedimentary interbed provides information on historical source of sediment for interbeds in and near the INEL. Mineralogical data indicate that surficial sediment samples from the Big Lost River drainage contained a larger amount of feldspar and pyroxene and a smaller amount of calcite and dolomite than samples from the Little Lost River and Birch Creek drainages. Mineralogical data from sedimentary interbeds at the RWMC, TRA, and ICPP correlate with surficial sediment of the present-day big Lost River drainage. Mineralogical data from a sedimentary interbed at TAN correlate with surficial sediment of the present-day Birch Creek drainage. 13 refs., 5 figs., 3 tabs

ICPP radioactive liquid and calcine waste technologies evaluation final report and recommendation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

Using a formalized Systems Engineering approach, the Latched Idaho Technologies Company developed and evaluated numerous alternatives for treating, immobilizing, and disposing of radioactive liquid and calcine wastes at the Idaho Chemical Processing Plant. Based on technical analysis data as of March, 1995, it is recommended that the Department of Energy consider a phased processing approach -- utilizing Radionuclide Partitioning for radioactive liquid and calcine waste treatment, FUETAP Grout for low-activity waste immobilization, and Glass (Vitrification) for high-activity waste immobilization -- as the preferred treatment and immobilization alternative.

Idaho Chemical Processing Plant and Plutonium-Uranium Extraction Plant phaseout/deactivation study

International Nuclear Information System (INIS)

Patterson, M.W.; Thompson, R.J.

1994-01-01

The decision to cease all US Department of Energy (DOE) reprocessing of nuclear fuels was made on April 28, 1992. This study provides insight into and a comparison of the management, technical, compliance, and safety strategies for deactivating the Idaho Chemical Processing Plant (ICPP) at Westinghouse Idaho Nuclear Company (WINCO) and the Westinghouse Hanford Company (WHC) Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this study is to ensure that lessons-learned and future plans are coordinated between the two facilities

Chemical constituents in water from wells in the vicinity of the Naval Reactors Facility, Idaho National Engineering Laboratory, Idaho, 1990--91

International Nuclear Information System (INIS)

Bartholomay, R.C.; Knobel, L.L.; Tucker, B.J.

1993-01-01

The US Geological Survey, in response to a request from the US Department of Energy's Pittsburgh Naval Reactors Office, Idaho Branch Office, sampled 12 wells as part of a long-term project to monitor water quality of the Snake River Plain aquifer in the vicinity of the Naval Reactors Facility, Idaho National Engineering Laboratory, Idaho. Water samples were analyzed for manmade contaminants and naturally occurring constituents. Sixty samples were collected from eight groundwater monitoring wells and four production wells. Ten quality-assurance samples also were collected and analyzed. Most of the samples contained concentrations of total sodium and dissolved anions that exceeded reporting levels. The predominant category of nitrogen-bearing compounds was nitrite plus nitrate as nitrogen. Concentrations of total organic carbon ranged from less than 0.1 to 2.2 milligrams per liter. Total phenols in 52 of 69 samples ranged from 1 to 8 micrograms per liter. Extractable acid and base/neutral organic compounds were detected in water from 16 of 69 samples. Concentrations of dissolved gross alpha- and gross beta-particle radioactivity in all samples exceeded the reporting level. Radium-226 concentrations were greater than the reporting level in 63 of 68 samples

Radiochemical and chemical constituents in water from selected wells and springs from the southern boundary of the Idaho National Laboratory to the Hagerman Area, Idaho, 2003

Science.gov (United States)

Rattray, Gordon W.; Wehnke, Amy J.; Hall, L. Flint; Campbell, Linford J.

2005-01-01

The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled water from 14 sites as part of an ongoing study to monitor the water quality of the eastern Snake River Plain aquifer between the southern boundary of the Idaho National Laboratory (INL) and the Burley-Twin Falls-Hagerman area. The State of Idaho, Department of Environmental Quality, Division of INL Oversight and Radiation Control cosampled with the U.S. Geological Survey and the Idaho Department of Water Resources and their analytical results are included in this report. The samples were collected from four domestic wells, two dairy wells, two springs, four irrigation wells, one observation well, and one stock well and analyzed for selected radiochemical and chemical constituents. Two quality-assurance samples, sequential replicates, also were collected and analyzed. None of the concentrations of radiochemical or organic-chemical constituents exceeded the maximum contaminant levels for drinking water established by the U.S. Environmental Protection Agency. However, the concentration of one inorganic-chemical constituent, nitrate (as nitrogen), in water from site MV-43 was 20 milligrams per liter which exceeded the maximum contaminant level for that constituent. Of the radiochemical and chemical concentrations analyzed for in the replicate-sample pairs, 267 of the 270 pairs (with 95 percent confidence) were statistically equivalent.

Radioactive sources in chemical laboratories

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2007-01-01

Radioactive sources including all radioactive materials exceeding exemption levels have to be registered in national databases according to international standards based on the recommendations ICRP 60 and a proper licensing should take place as described for example in the 96/29/EURATOM. In spite of that, unregistered sources could be found, usually due to the fact that the owner is not aware of radiation characteristics of sources. The material inventories of chemical laboratories are typical and most frequent example where radioactive sources could be found. Five different types of sources could be identified. The most frequent type are chemicals, namely thorium and uranium compounds. They are used not due to their radioactivity but due to their chemical properties. As for all other sources a stringent control is necessary in order to assure their safe use. Around hundred of stored radioactive chemical items were found during inspections of such laboratories performed by the Slovenian Nuclear Safety Administration or qualified experts in a period December 2006 - July 2007. Users of such chemicals are usually not aware that thorium and uranium chemicals are radioactive and, as unsealed sources, they could be easily spilled out and produce contamination of persons, surfaces, equipment etc. The external exposure as well as the internal exposure including exposure due to inhalation could be present. No knowledge about special precautions is usually present in laboratories and leads to underestimating of a potential risk and unintentional exposure of the laboratory personnel, students etc. Due to the long decay times in decay series of Th -232, U-238 and U- 235 the materials are also radioactive today. Even more, in case of thorium chemicals the radioactivity increased substantially from the time of their production. The implementation of safety measures has been under way and includes a survey of the qualified experts, establishment of organizational structure in a

Laboratory Evaluation of In Situ Chemical Oxidation for Groundwater Remediation, Test Area North, Operable Unit 1-07B, Idaho National Engineering and Environmental Laboratory, Volume Three - Appendix F

Energy Technology Data Exchange (ETDEWEB)

Cline, S.R.; Denton, D.L.; Giaquinto, J.M.; McCracken, M.K.; Starr, R.C.

1999-04-01

This appendix supports the results and discussion of the laboratory work performed to evaluate the feasibility of in situ chemical oxidation for Idaho National Environmental and Engineering Laboratory's (INEEL) Test Area North (TAN) which is contained in ORNL/TM-13711/V1. This volume contains Appendix F. Appendix F is essentially a photocopy of the ORNL researchers' laboratory notebooks from the Environmental Sciences Division (ESD) and the Radioactive Materials Analytical Laboratory (RMAL).

Radioactive effluent monitoring at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Simpson, O.D.

1975-01-01

The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

Hydrological, meteorological and geohydrological data for an unsaturated zone study near the Radioactive Waste Management Complex, Idaho National Engineering Laboratory, Idaho - 1987

International Nuclear Information System (INIS)

Davis, L.C.; Pittman, J.R.

1990-01-01

Since 1952, radioactive waste has been buried at the RWMC (Radioactive Waste Management Complex) at the Idaho National Engineering Laboratory in southeastern Idaho. In 1985, the US Geological Survey, in cooperation with the US Department of Energy, began a study of the geohydrology of the RWMC to provide a basis for estimating the extent of and the potential for migration of radionuclides in the unsaturated zone beneath the waste burial trenches and pits. This study is being conducted to provide hydrological, meteorological and geohydrological data for the test trench area adjacent to the northern boundary of the RWMC. During 1987, data were collected from the test trench area, where several types of instrumentation were installed in the surficial sediment in 1985. Hydrological data collected from both disturbed and undisturbed soil included measurements, from 28 thermocouple psychrometers placed at selected depths to about 6m. Soil moisture content measurements were collected bi-weekly in 9 neutron-probe access holes with a neutron moisture depth gage. Meteorological data summarized daily included: (1) incoming and emitted long-wave radiation; (2) incoming and reflected short-wave radiation; (3) air temperature; (4) relative humidity; (5) wind speed; (6) wind direction; and (7) precipitation. To describe grain-size distribution with depth, 17 samples were analyzed using sieve and pipette methods. Statistical parameters, carbonate content, color, particle roundness and sphericity, and mineralogic and clastic constituents were determined for each sample. Some samples were analyzed by x-ray diffraction techniques to determine bulk and clay mineralogy

An update of the distribution of selected radiochemical and chemical constituents in perched ground water, Idaho National Laboratory, Idaho, Emphasis 1999-2001

Science.gov (United States)

Davis, Linda C.

2006-01-01

Radiochemical and chemical wastes generated at facilities at the Idaho National Laboratory (INL) were discharged since 1952 to infiltration ponds at the Reactor Technology Complex (RTC) (known as the Test Reactor Area [TRA] until 2005), and the Idaho Nuclear Technology and Engineering Center (INTEC) and buried at the Radioactive Waste Management Complex (RWMC). Disposal of wastewater to infiltration ponds and infiltration of surface water at waste burial sites resulted in formation of perched ground water in basalts and in sedimentary interbeds above the Snake River Plain aquifer. Perched ground water is an integral part of the pathway for waste-constituent migration to the aquifer. The U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, maintains ground-water monitoring networks at the INL to determine hydrologic trends, and to monitor the movement of radiochemical and chemical constituents in wastewater discharged from facilities to both perched ground water and the aquifer. This report presents an analysis of water-quality and water-level data collected from wells completed in perched ground water at the INL during 1999-2001, and summarizes historical disposal data and water-level-and water-quality trends. At the RTC, tritium, strontium-90, cesium-137, dissolved chromium, chloride, sodium, and sulfate were monitored in shallow and deep perched ground water. In shallow perched ground water, no tritium was detected above the reporting level. In deep perched ground water, tritium concentrations generally decreased or varied randomly during 1999-2001. During October 2001, tritium concentrations ranged from less than the reporting level to 39.4?1.4 picocuries per milliliter (pCi/mL). Reportable concentrations of tritium during July-October 2001 were smaller than the reported concentrations measured during July-December 1998. Tritium concentrations in water from wells at the RTC were likely affected by: well's distance from the

Technical safety appraisal of the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

1992-05-01

On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

Chemical decontamination of radioactive waste

International Nuclear Information System (INIS)

Mohamed, H.I.

2006-01-01

Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. There is also a variety of alternatives for treatment and conditioning of the wastes prior disposal. The importance of treatment of radioactive waste for protection of human and environment has long been recognized and considerable experience has gained in this field. Generally, the methods used for treatment of radioactive wastes can be classified into three type's biological, physical and chemical treatment this physical treatment it gives good result than biological treatment. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. In chemical treatment there are different procedures, solvent extraction, ion exchange, electro dialysis but solvent extraction is best one because high purity can be optioned on the other hand the disadvantage that it is expensive. Beside the solvent extraction technique one can be used is ion exchange which gives reasonable result, but requires pretreatment that to avoid in closing of column by colloidal and large species. Electro dialysis technique gives quite result but less than solvent extraction and ion exchange technique the advantage is a cheep.(Author)

Hydrologic testing in wells near the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Johnson, G.S.; Olsen, J.H.; Ralston, D.R.

1994-01-01

The Snake River Plain aquifer beneath the INEL is often viewed as a 2-dimensional system, but may actually possess 3-dimensional properties of concern. A straddle-packer system is being used by the State's INEL Oversight Program to isolate specific aquifer intervals and define the 3-dimensional chemical and hydrologic characteristics of the aquifer. The hydrologic test results from wells USGS 44, 45, and 46 near the Idaho Chemical Processing Plant indicate that: (1) Vertical variation in static head is less than 0.3 feed, (2) barometric efficiencies are between 25 and 55 percent, and (3) the system responds to distant pumping as a multi-layered, but interconnected system. 3 refs., 7 figs., 3 tabs

Geologic processes in the RWMC area, Idaho National Engineering Laboratory: Implications for long term stability and soil erosion at the radioactive waste management complex

International Nuclear Information System (INIS)

Hackett, W.R.; Tullis, J.A.; Smith, R.P.

1995-09-01

The Radioactive Waste Management Complex (RWMC) is the disposal and storage facility for low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). Transuranic waste and mixed wastes were also disposed at the RWMC until 1970. It is located in the southwestern part of the INEL about 80 km west of Idaho Falls, Idaho. The INEL occupies a portion of the Eastern Snake River Plain (ESRP), a low-relief, basalt, and sediment-floored basin within the northern Rocky Mountains and northeastern Basin and Range Province. It is a cool and semiarid, sagebrush steppe desert characterized by irregular, rolling terrain. The RWMC began disposal of INEL-generated wastes in 1952, and since 1954, wastes have been accepted from other Federal facilities. Much of the waste is buried in shallow trenches, pits, and soil vaults. Until about 1970, trenches and pits were excavated to the basalt surface, leaving no sediments between the waste and the top of the basalt. Since 1970, a layer of sediment (about 1 m) has been left between the waste and the basalt. The United States Department of Energy (DOE) has developed regulations specific to radioactive-waste disposal, including environmental standards and performance objectives. The regulation applicable to all DOE facilities is DOE Order 5820.2A (Radioactive Waste Management). An important consideration for the performance assessment of the RWMC is the long-term geomorphic stability of the site. Several investigators have identified geologic processes and events that could disrupt a radioactive waste disposal facility. Examples of these open-quotes geomorphic hazardsclose quotes include changes in stream discharge, sediment load, and base level, which may result from climate change, tectonic processes, or magmatic processes. In the performance assessment, these hazards are incorporated into scenarios that may affect the future performance of the RWMC

The enhanced variance propagation code for the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Kern, E.A.; Zack, N.R.; Britschgi, J.J.

1992-01-01

The Variance Propagation (VP) Code was developed by the Los Alamos National Laboratory's Safeguard's Systems Group to provide off-line variance propagation and systems analysis for nuclear material processing facilities. The code can also be used as a tool in the design and evaluation of material accounting systems. In this regard , the VP code was enhanced to incorporate a model of the material accountability measurements used in the Idaho Chemical Processing Plant operated by the Westinghouse Idaho Nuclear Company. Inputs to the code were structured to account for the dissolves/headend process, the waste streams, process performed to determine the sensitivity of measurement and sampling errors to the overall material balance error. We determined that the material balance error is very sensitive to changes in the sampling errors. 3 refs

Vadose zone monitoring at the radioactive waste management complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

McElroy, D.L.; Hubbell, J.M.

1989-01-01

A network of vadose zone instruments was installed in surficial sediments and sedimentary interbeds beneath the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The network of instruments monitor moisture movement in a heterogeneous geologic system comprised of sediments which overlie and are intercalated with basalt flows. The general range of matric potentials in the surficial sediments (0 to 9.1 m) was from saturation to -3 bars. The basalt layer beneath the surficial sediments impedes downward water movement. The general range of matric potentials in the 9-, 34- and 73-m interbeds was from -0.3 to 1.7 bars. Preliminary results indicated downward moisture movement through the interbeds. 8 refs., 9 figs., 1 tab

Chemical and Radiochemical Constituents in Water from Wells in the Vicinity of the Naval Reactors Facility, Idaho National Engineering and Environmental Laboratory, Idaho, 1997-98

Energy Technology Data Exchange (ETDEWEB)

R. C. Bartholomay; L. L. Knobel; B. J. Tucker; B. V. Twining (USGS)

2000-06-01

The US Geological Survey, in response to a request from the U.S Department of Energy's Pittsburgh Naval Reactors Office, Idaho Branch Office, sampled water from 13 wells during 1997-98 as part of a long-term project to monitor water quality of the Snake River Plain aquifer in the vicinity of the Naval Reactors Facility, Idaho National Engineering and Environmental Laboratory, Idaho. Water samples were analyzed for naturally occurring constituents and man-made contaminants. A total of 91 samples were collected from the 13 monitoring wells. The routine samples contained detectable concentrations of total cations and dissolved anions, and nitrite plus nitrate as nitrogen. Most of the samples also had detectable concentrations of gross alpha- and gross beta-particle radioactivity and tritium. Fourteen quality-assurance samples were also collected and analyzed; seven were field-blank samples, and seven were replicate samples. Most of the field blank samples contained less than detectable concentrations of target constituents; however some blank samples did contain detectable concentrations of calcium, magnesium, barium, copper, manganese, nickel, zinc, nitrite plus nitrate, total organic halogens, tritium, and selected volatile organic compounds.

High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tank relief piping and high-level liquid waste transfer systems. As a result of the April 1992 decision to discontinue the reprocessing of spent nuclear fuel at INEL, DOE believes that it is unlikely that the tank replacement aspect of the project will be needed in the near term. Therefore, DOE is not proposing to proceed with the replacement of the tanks as described in this-EA. The DOE's instant decision involves only the proposed upgrades aspect of the project described in this EA. The upgrades are needed to comply with Resource Conservation and Recovery Act, the Idaho Hazardous Waste Management Act requirements, and the Department's obligations pursuant to the Federal Facilities Compliance Agreement and Consent Order among the Environmental Protection Agency, DOE, and the State of Idaho. The environmental impacts of the proposed upgrades are adequately covered and are bounded by the analysis in this EA. If DOE later proposes to proceed with the tank replacement aspect of the project as described in the EA or as modified, it will undertake appropriate further review pursuant to the National Environmental Policy Act

Web technology in the separation of strontium and cesium from INEL-ICPP radioactive acid waste (WM-185)

International Nuclear Information System (INIS)

Bray, L.A.; Brown, G.N.

1995-01-01

Strontium and cesium were successfully removed from radioactive acidic waste (WM-185) at the Idaho National Engineering Laboratory, Idaho Chemical Processing Plant (ICPP), with web technology from 3M and IBC Advanced Technologies, Inc. (IBC). A technical team from Pacific Northwest Laboratory, ICPP, 3M and IBC conducted a very successful series of experiments from August 15 through 18, 1994. The ICPP, Remote Analytical Laboratory, Idaho Falls, Idaho, provided the hot cell facilities and staff to complete these milestone experiments. The actual waste experiments duplicated the initial 'cold' simulated waste results and confirmed the selective removal provided by ligand-particle web technology

Hydrologic and Meteorological Data for an Unsaturated-Zone Study Area near the Radioactive Waste Management Complex, Idaho National Engineering and Environmental Laboratory, Idaho, 1990-96

International Nuclear Information System (INIS)

Perkins, K. S.; Nimmo, J. R.; Pittman, J. R.

1998-01-01

Trenches and pits at the Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA) at the Idaho National Engineering and Environmental Laboratory (formerly known as the Idaho National Engineering Laboratory) have been used for burial of radioactive waste since 1952. In 1985, the U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, began a multi-phase study of the geohydrology of the RWMC to provide a basis for estimating the extent of and the potential for migration of radionuclides in the unsaturated zone beneath the waste trenches and pits. This phase of the study provides hydrologic and meteorological data collected at a designated test trench area adjacent to the northern boundary of the RWMC SDA from 1990 through 1996. The test trench area was constructed by the USGS in 1985. Hydrologic data presented in this report were collected during 1990-96 in the USGS test trench area. Soil-moisture content measurement from disturbed and undisturbed soil were collected approximately monthly during 1990-96 from 11 neutron-probe access holes with a neutron moisture gage. In 1994, three additional neutron access holes were completed for monitoring. A meteorological station inside the test trench area provided data for determination of evapotranspiration rates. The soil-moisture and meteorological data are contained in files on 3-1/2 inch diskettes (disks 1 and 2) included with this report. The data are presented in simple American Standard Code for Information Interchange (ASCII) format with tab-delimited fields. The files occupy a total of 1.5 megabytes of disk space

Environmental assessment: Closure of the Waste Calcining Facility (CPP-633), Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1996-07-01

The U.S. Department of Energy (DOE) proposes to close the Waste Calcining Facility (WCF). The WCF is a surplus DOE facility located at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL). Six facility components in the WCF have been identified as Resource Conservation and Recovery Ace (RCRA)-units in the INEL RCRA Part A application. The WCF is an interim status facility. Consequently, the proposed WCF closure must comply with Idaho Rules and Standards for Hazardous Waste contained in the Idaho Administrative Procedures Act (IDAPA) Section 16.01.05. These state regulations, in addition to prescribing other requirements, incorporate by reference the federal regulations, found at 40 CFR Part 265, that prescribe the requirements for facilities granted interim status pursuant to the RCRA. The purpose of the proposed action is to reduce the risk of radioactive exposure and release of hazardous constituents and eliminate the need for extensive long-term surveillance and maintenance. DOE has determined that the closure is needed to reduce potential risks to human health and the environment, and to comply with the Idaho Hazardous Waste Management Act (HWMA) requirements

1983 Environmental monitoring program report for Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Dickson, R.L.

1984-05-01

The results of the various monitoring programs for 1983 indicated that radioactivity from the Idaho National Engineering Laboratory (INEL) Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. 11 figures, 14 tables

Barn swallows nesting near radioactive leaching ponds in southeastern Idaho

International Nuclear Information System (INIS)

Millard, J.B.; Whicker, F.W.; Markham, O.D.

1978-01-01

Seasonally occurring populations of barn swallows nest near the Test Reactor Area (TRA) radioactive leaching ponds on the Idaho National Engineering Laboratory (INEL) Site. These birds utilize leaching pond arthropods and are therefore capable of accumulating radioactive materials and exporting them from the INEL Site during migration. The breeding biology is discussed for these swallows and a control group located 100 km away. Total nestling mortality for the controls and a 1977 TRA population was found to be statistically identical. Over 20 fission and activation products have been detected in immature and adult TRA birds. Mean concentrations of detectable radionuclides were used to calculate internal dose rates, and results showed that Na-24 contributed about 72% of the total average of 21.9 mrad/d for adult birds. Concentration factors were also calculated for predominant radionuclides in swallows relative to filtered pond water. Data from LiF dosimeters in swallow nests constructed with contaminated mud indicated average dose rates were 84 mrad/d for eggs and 220 mrad/d for nestlings. Growth curves were constructed for the immature TRA birds and controls. The first clutch of TRA swallows was found to have a significantly lower mean growth rate constant than the first clutch of controls. The statistical difference in growth rate between the control and TRA first clutch populations may have resulted from differences in climate, nesting site habitat, or available food sources, and cannot be solely attributed to radiation exposure as a causative factor. Growth rate parameters for TRA birds were within the range of values reported in the literature

Emissions model of waste treatment operations at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Schindler, R.E.

1995-03-01

An integrated model of the waste treatment systems at the Idaho Chemical Processing Plant (ICPP) was developed using a commercially-available process simulation software (ASPEN Plus) to calculate atmospheric emissions of hazardous chemicals for use in an application for an environmental permit to operate (PTO). The processes covered by the model are the Process Equipment Waste evaporator, High Level Liquid Waste evaporator, New Waste Calcining Facility and Liquid Effluent Treatment and Disposal facility. The processes are described along with the model and its assumptions. The model calculates emissions of NO x , CO, volatile acids, hazardous metals, and organic chemicals. Some calculated relative emissions are summarized and insights on building simulations are discussed

Black-tailed jack rabbit movements and habitat utilization at the Idaho National Engineering Laboratory radioactive waste management complex

International Nuclear Information System (INIS)

Grant, J.C.

1983-01-01

In June 1982, a study of black-tailed jack rabbit (Lepus californicus) ecology was initiated at the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC). This study will provide data necessary to evaluate the role of jack rabbits in radionuclide transport away from the Subsurface Disposal Area of the RWMC. Primary goals are to document radionuclide concentrations in jack rabbit tissues, and determine population size, movement patterns, habitat use, and food habits of jack rabbits inhabiting the RWMC area. Study design and prelimianry results are discussed

Subsurface Investigations Program at the radioactive waste management complex of the Idaho National Engineering Laboratory. Annual progress report, FY-1985

International Nuclear Information System (INIS)

Hubbell, J.M.; Hull, L.C.; Humphrey, T.G.; Russell, B.F.; Pittman, J.R.; Cannon, K.M.

1985-12-01

This report describes work conducted in FY-85 in support of the Subsurface Investigation Program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. The work is part of a continuing effort to define and predict radionuclide migration from buried waste. The Subsurface Investigation Program is a cooperative study conducted by EG and G Idaho and the US Geological Survey, INEL Office. EG and G is responsible for the shallow drilling, solution chemistry, and net downward flux portions of this program, while the US Geological Survey is responsible for the weighing lysimeters and test trench. Data collection was initiated by drilling, sampling, and instrumenting shallow wells, continuing the installation of test trenches, and modifying the two weighing lysimeters. Twenty-one shallow auger holes were around the Radioactive Waste Management Complex (RWMC) to evaluate radionuclide content in the surficial sediments, to determine the geologic and hydrologic characteristics of the surficial sediments, and to provide as monitoring sites for moisture in these sediments. Eighteen porous cup lysimeters were installed in 12 auger holes to collect soil water samples from the surficial sediments. Fourteen auger holes were instrumented with tensiometers, gypsum blocks and/or psychrometers at various depths throughout the RWMC. Readings from these instruments are taken on a monthly basis

Low-level radioactive waste management handbook series: Low-level radioactive waste management in medical and biomedical research institutions

International Nuclear Information System (INIS)

1987-03-01

Development of this handbook began in 1982 at the request of the Radhealth Branch of the California Department of Health Services. California Assembly Bill 1513 directed the DHS to ''evaluate the technical and economic feasibility of (1) reducing the volume, reactivity, and chemical and radioactive hazard of (low-level radioactive) waste and (2) substituting nonradioactive or short-lived radioactive materials for those radionuclides which require long-term isolation from the environment. A contract awarded to the University of California at Irvine-UCI (California Std. Agreement 79902), to develop a document focusing on methods for decreasing low-level radioactive waste (LLW) generation in institutions was a result of that directive. In early 1985, the US Department of Energy, through EG and G Idaho, Inc., contracted with UCI to expand, update, and revise the California text for national release

Chemical decontamination method for radioactive metal waste

International Nuclear Information System (INIS)

Tanaka, Akio; Onuma, Tsutomu; Yamazaki, Sei; Miura, Haruki.

1993-01-01

The present invention provides a chemical decontamination method for radioactive metal wastes, which are generated from radioactive material handling facilities and the surfaces of which are contaminated by radioactive materials. That is, it has a feature of applying acid dissolution simultaneously with mechanical grinding. The radioactive metal wastes are contained in a vessel such as a barrel together with abrasives in a sulfuric acid solution and rotated at several tens rotation per minute. By such procedures for the radioactive metal wastes, (1) cruds and passive membranes are mechanically removed, (2) exposed mother metal materials are uniformly brought into contact with sulfuric acid and further (3) the mother metal materials dissolve the cruds and the passive membranes also chemically by a reducing dissolution (so-called local cell effect). According to the method of the present invention, stainless steel metal wastes having cruds and passive membranes can rapidly and efficiently be decontaminated to a radiation level equal with that of ordinary wastes. (I.S.)

Separation of non-hazardous, non-radioactive components from ICPP calcine via chlorination

International Nuclear Information System (INIS)

Nelson, L.O.

1995-05-01

A pyrochemical treatment method for separating non-radioactive from radioactive components in solid granular waste accumulated at the Idaho Chemical Processing Plant was investigated. The goal of this study was to obtain kinetic and chemical separation data on the reaction products of the chlorination of the solid waste, known as calcine. Thermodynamic equilibrium calculations were completed to verify that a separation of radioactive and non-radioactive calcine components was possible. Bench-scale chlorination experiments were completed subsequently in a variety of reactor configurations including: a fixed-bed reactor (reactive gases flowed around and not through the particle bed), a packed/fluidized-bed reactor, and a packed-bed reactor (reactive gases flowed through the particle bed). Chemical analysis of the reaction products generated during the chlorination experiments verified the predictions made by the equilibrium calculations. An empirical first-order kinetic rate expression was developed for each of the reactor configurations. 20 refs., 16 figs., 21 tabs

Radioactive waste management

International Nuclear Information System (INIS)

Slansky, C.M.

1975-01-01

High-level radioactive waste is produced at Idaho Chemical Processing Plant (ICPP) during the recovery of spent highly enriched nuclear fuels. Liquid waste is stored safely in doubly contained tanks made of steel. The liquid waste is calcined to a solid and stored safely in a retrievable form in doubly contained underground bins. The calcine can be treated further or left untreated in anticipation of ultimate storage. Fluidized bed calcination has been applied to many kinds of high-level waste. The environmental impact of high-level waste management at the ICcP has been negligible and should continue to be negligible. 13 refs

A survey of process control computers at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Dahl, C.A.

1989-01-01

The Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory is charged with the safe processing of spent nuclear fuel elements for the United States Department of Energy. The ICPP was originally constructed in the late 1950s and used state-of-the-art technology for process control at that time. The state of process control instrumentation at the ICPP has steadily improved to keep pace with emerging technology. Today, the ICPP is a college of emerging computer technology in process control with some systems as simple as standalone measurement computers while others are state-of-the-art distributed control systems controlling the operations in an entire facility within the plant. The ICPP has made maximal use of process computer technology aimed at increasing surety, safety, and efficiency of the process operations. Many benefits have been derived from the use of the computers for minimal costs, including decreased misoperations in the facility, and more benefits are expected in the future

Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 2002

Science.gov (United States)

Rattray, Gordon W.; Campbell, Linford J.

2004-01-01

The U.S. Geological Survey, Idaho Department of Water Resources, and the State of Idaho INEEL Oversight Program, in cooperation with the U.S. Department of Energy, sampled water from 17 sites as part of the sixth round of a long-term project to monitor water quality of the eastern Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. The samples were collected from eight irrigation wells, three domestic wells, one stock well, one dairy well, one commercial well, one observation well, and two springs and analyzed for selected radiochemical and chemical constituents. One quality-assurance sample, a sequential replicate, also was collected and analyzed. Many of the radionuclide and inorganic-constituent concentrations were greater than the reporting levels and most of the organic-constituent concentrations were less than the reporting levels. However, none of the reported radiochemical- or chemical-constituent concentrations exceeded the maximum contaminant levels for drinking water established by the U.S. Environmental Protection Agency. Statistical evaluation of the replicate sample pair indicated that, with 95 percent confidence, 132 of the 135 constituent concentrations of the replicate pair were equivalent.

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1991-07-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1993-01-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

Corrosion monitoring of storage bins for radioactive calcines

International Nuclear Information System (INIS)

Hoffman, T.L.

1975-01-01

Highly radioactive liquid waste produced at the Idaho Chemical Processing Plant is calcined to a granular solid for long term storage in stainless steel bins. Corrosion evaluation of coupons withdrawn from these bins indicates excellent performance for the materials of construction of the bins. At exposure periods of up to six years the average penetration rates are 0.01 and 0.05 mils per year for Types 304 and 405 stainless steels, respectively. (auth)

Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1992 through 1995

International Nuclear Information System (INIS)

Bartholomay, R.C.; Tucker, B.J.; Ackerman, D.J.; Liszewski, M.J.

1997-04-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The US Geological Survey, in cooperation with the US Department of Energy, maintains a monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1992--95

Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 1997

Energy Technology Data Exchange (ETDEWEB)

R. C. Bartholomay (USGS); L. M. Williams (USGS); L. J. Campbell (Idaho Department of Water Resources)

1998-12-01

The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled 18 sites as part of the fourth round of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radiochemical and chemical constituents. The samples were collected from seven domestic wells, six irrigation wells, two springs, one dairy well, one observation well, and one stock well. Two quality-assurance samples also were collected and analyzed. None of the radiochemical or chemical constituents exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide- and inorganic-constituent concentrations were greater than their respective reporting levels.

Assessment of aircraft impact probabilities at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Lee, L.G.; Mines, J.M.; Webb, B.B.

1996-04-01

The purpose of this study is to evaluate the possibility of an aircraft crash into a facility at the Idaho Chemical Processing Plant (ICPP). The ICPP is part of the Idaho National Engineering Laboratory (INEL). Based on the data used in this study, an air crash into any single facility at the ICPP is incredible, An air crash into aggregate areas incorporating the following is extremely unlikely: (1) ICPP radiological materials storage facilities, (2) ICPP major processing facilities, and (3) the ICPP total surface area. The radiological materials storage facilities aggregate areas are areas of concern usually requiring safety analyses, According to Department of Energy guidance, if the probability of a radiological release event is determined to be incredible, no further review is required. No individual facility in this analysis has a crash potential large enough to be credible. Therefore, an aircraft crash scenario is not required in the safety analysis for a single facility, but should be discussed relative to the ICPP aggregate areas, The highest probability of concern in the study was for aircraft to crash into the aggregate area for radiological materials storage facilities at the ICPP during Federal Aviation Administration (FAA) test flights

Environmental surveillance for EG ampersand G Idaho Waste Management facilities at the Idaho National Engineering Laboratory. 1993 annual report

International Nuclear Information System (INIS)

Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.; Borsella, B.W.

1994-08-01

This report describes calendar year 1993 environmental surveillance activities of Environmental Monitoring of EG ampersand G Idaho, Inc., performed at EG ampersand G Idaho operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1993 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years

Annual report -- 1992: Environmental surveillance for EG ampersand G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

1993-08-01

This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years

HEPA filter leaching concept validation trials at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Chakravartty, A.C.

1995-04-01

The enclosed report documents six New Waste Calcining Facility (NWCF) HEPA filter leaching trials conducted at the Idaho Chemical Processing Plant using a filter leaching system to validate the filter leaching treatment concept. The test results show that a modified filter leaching system will be able to successfully remove both hazardous and radiological constituents to RCRA disposal levels. Based on the success of the filter leach trials, the existing leaching system will be modified to provide a safe, simple, effective, and operationally flexible filter leaching system

ICPP injection well alternative project, Idaho National Engineering Laboratory. Final report

International Nuclear Information System (INIS)

1980-10-01

The Idaho Chemical Processing Plant (ICPP) portion of the Idaho National Engineering Laboratory (INEL) has been obtaining water needed for its operations from the Snake River aquifer, which occupies the entire region underlying the site. Most of this water has been used for cooling operating equipment, while a small portion has found various process uses. After passing through the ICPP process area, these waters are then returned to the aquifer. A small portion (about 1%) of the returned stream contains measurable amounts of radioactivity derived from the miscellaneous process users. This report and the recommendations contained herein are based upon stream flows projected for 1985 as supplied by DOE for the ICPP. 26 different alternatives for handling cooling water, chemical, and low level radioactive water disposal are examined. These cases are considered from technical, environmental, safety, and economic points of view. The level of detail is sufficient to eliminate non-viable cases, and to identify those which offer improvements over present practice. The Environmental/Safety Risk Factors were evaluated on a qualitative comparison basis only. Before a recommended improvement is incorporated into the waste disposal system, a conceptual design study should be made which would evaluate all those secondary effects and environmental factors that, by the very nature of the screening process, this study has not provided. Certain synergistic combinations have been noted and are discussed. This report does note whether the operations considered are in regulatory compliance, or are likely to be capable of providing lasting improvement to the waste water system. Qualitative comparisons were made between the various alternatives to confirm their relationship with applicable standards

Heavy element radionuclides (Pu, Np, U) and 137Cs in soils collected from the Idaho National Engineering and Environmental Laboratory and other sites in Idaho, Montana, and Wyoming

International Nuclear Information System (INIS)

Beasley, T.M.; Rivera, W. Jr.; Liszewski, M.J.; Orlandini, K.A.

1998-10-01

The isotopic composition of Pu in soils on and near the Idaho National Engineering and Environmental Laboratory (INEEL) has been determined in order to apportion the sources of the Pu into those derived from stratospheric fallout, regional fallout from the Nevada Test Site (NTS), and facilities on the INEEL site. Soils collected offsite in Idaho, Montana, and Wyoming were collected to further characterize NTS fallout in the region. In addition, measurements of 237 Np and 137 Cs were used to further identify the source of the Pu from airborne emissions at the Idaho Chemical Processing Plant (ICPP) or fugitive releases from the Subsurface Disposal Area (SDA) in the Radioactive Waste Management Complex (RWMC). There is convincing evidence from this study that 241 Am, in excess of that expected from weapons-grade Pu, constituted a part of the buried waste at the SDA that has subsequently been released to the environment. Measurements of 236 U in waters from the Snake River Plain aquifer and a soil core near the ICPP suggest that this radionuclide may be a unique interrogator of airborne releases from the ICPP. Neptunium-237 and 238 Pu activities in INEEL soils suggest that airborne releases of Pu from the ICPP, over its operating history, may have recently been overestimated

Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 1998

Energy Technology Data Exchange (ETDEWEB)

R. C. Bartholomay; B. V. Twining (USGS); L. J. Campbell (Idaho Department of Water Resources)

1999-06-01

The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled 18 sites as part of the fourth round of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. The samples were analyzed for selected radiochemical and chemical constituents. The samples were collected from 2 domestic wells, 12 irrigation wells, 2 stock wells, 1 spring, and 1 public supply well. Two quality-assurance samples also were collected and analyzed. None of the reported radiochemical or chemical constituent concentrations exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide- and inorganic-constituent concentrations were greater than the respective reporting levels. Most of the organic-constituent concentrations were less than the reporting levels.

Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-01-01

EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-03-01

EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

Chemical treatment of radioactive wastes

International Nuclear Information System (INIS)

Pottier, P.E.

1968-01-01

This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

Mineralogy and depositional sources of sedimentary interbeds beneath the Idaho National Engineering Laboratory; eastern Snake River Plain, Idaho

International Nuclear Information System (INIS)

Reed, M.F.

1994-01-01

Idaho State University, in cooperation with the U.S. Geological Survey, and the U.S. Department of Energy, collected 57 samples of sedimentary interbeds at 19 sites at the Idaho National Engineering Laboratory (INEL) for mineralogical analysis. Previous work by the U.S. Geological Survey on surficial sediments showed that ratios detrital of quartz, total feldspars, and calcite can be used to distinguish the sedimentary mineralogy of specific stream drainages at the INEL. Semi-quantitative x-ray diffraction analyses were used to determine mineral abundances in the sedimentary interbeds. Samples were collected from wells at the New Production Reactor (NPR) area, Idaho Chemical Processing Plant (ICPP), Test Reactor Area (TRA), miscellaneous sites, Radioactive Waste Management Complex (RWMC), Naval Reactors Facility (NRF), and Test Area North (TAN). Normalized mean percentages of quartz, feldspar, and carbonate were calculated from sample data sets at each site. Percentages for quartz, feldspar, and carbonate from the NPR, ICPP, TRA, miscellaneous sites, RWMC, and NRF ranged from 37 to 59, 26 to 40, and 5 to 25, respectively. Percentages for quartz, feldspar, and carbonate from wells at Test Area North (TAN) were 24, 10, and 66, respectively. Mineralogical data indicate that sedimentary interbed samples collected from the NPR, ICPP, TRA, miscellaneous sites, RWMC, and NRF correlate with surficial sediment samples from the present day Big Lost River. Sedimentary interbeds from TAN sites correlate with surficial sediment samples from Birch Creek. These correlations suggest that the sources for the sediments at and near the INEL have remained relatively consistent for the last 580,000 years. 12 refs., 4 figs., 3 tabs

Radioactivity in Chemical Fertilizers

International Nuclear Information System (INIS)

Jankovic, M.; Nikolic, J.; Pantelic, G.; Rajacic, M.; Sarap, N.; Todorovic, D.

2013-01-01

The fertilizers are essential in agriculture as they supply nutrients to the farming fields. One of the sources of radioactivity other than those of natural origin is mainly due to extensive use of fertilizers. The concentrations of natural radionuclides, 40K, 226Ra, 238U and 235U in different chemical fertilizers, which are part of the regular control of imported goods from the border crossing were analyzed using gamma spectrometry with a high purity germanium (HPGe) detector, relative efficiency 20 %, in order to assess the implications of the extended use of chemical fertilizers. Measurements were performed at Vinca Institute, Radiation and Environmental Protection Department. The obtained results show remarkable wide variations in the radioactivity contents of different samples. The mean (ranges) of specific activities for gamma activity of those fertilizer samples for 40K, 226Ra, 238U and 235U are 4857 (23 - 12 324) Bq/kg, 87 (4-393) Bq/kg, 220 (26-1145) Bq/kg and 15 (1.6-53) Bq/kg, respectively. The radium equivalent activity (Ra eq ) as well as the external absorbed gamma dose rate (D) for all samples was also calculated.(author)

Stabilization of mixed waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Gillins, R.L.; Larsen, M.M.

1989-01-01

EG and G Idaho, Inc. has initiated a program to develop safe, efficient, cost-effective treatment methods for the stabilization of some of the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory. Laboratory-scale testing has shown that extraction procedure toxic wastes can be successfully stabilized by solidification, using various binders to produce nontoxic, stable waste forms for safe, long-term disposal as either landfill waste or low-level radioactive waste, depending upon the radioactivity content. This paper presents the results of drum-scale solidification testing conducted on hazardous, low-level incinerator flyash generated at the Waste Experimental Reduction Facility. The drum-scale test program was conducted to verify that laboratory-scale results could be successfully adapted into a production operation

1985 Environmental Monitoring Program report for the Idaho National Engineering Laboratory site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Rope, S.K.

1986-05-01

The results of the various monitoring programs for 1985 indicated that radioactivity from the Idaho National Engineering Laboratory (INEL) Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. It compares and evaluates the sample results, discussing implications, if any. Included for the first time this year are data from air and water samples routinely collected from onsite locations. The report also summarizes significant environmental activities at the INEL Site during 1985, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) groundwater monitoring program

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

International Nuclear Information System (INIS)

Romano, Stephen; Welling, Steven; Bell, Simon

2003-01-01

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

Idaho National Engineering and Environmental Laboratory Site Environmental Report for Calendar Year 1997

Energy Technology Data Exchange (ETDEWEB)

R. B. Evans; D. Roush; R. W. Brooks; D. B. Martin

1998-08-01

The results of the various monitoring programs for 1997 indicated that radioactivity from the Idaho National Engineering and Environmental Laboratory (INEEL) operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines. The maximum potential population dose from submersion, ingestion, inhalation, and deposition to the approximately 121,500 people residing within an 80-km (50-mi) radius from the geographical center of the INEEL was estimated to be 0.2 person-rem (2 x 10-3 person-Sv) using the MDIFF air dispersion model. This population dose is less than 0.0005% of the estimated 43,700 person-rem (437 person-Sv) population dose from background radioactivity.

Some problems of risk assessment in cases of environmental radioactive and chemical contamination in regions of the Ural radioactive trail

International Nuclear Information System (INIS)

Kryshev, I.I.; Isaeva, L.N.; Sazykina, T.G.

1995-01-01

A methodology of risk assessment if being developed to permit the analysis of possible consequences of radioactive and chemical environment contamination on the territory of the Urals radioactive trail. The assessment of hazards from radioactive contamination of the Techa river (Muslyumovo) has been carried out. A comparison of radioactive and chemical risks for the population of Kasli has been made

Thickness of surficial sediment at and near the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Anderson, S.R.; Liszewski, M.J.; Ackerman, D.J.

1996-06-01

Thickness of surficial sediment was determined from natural-gamma logs in 333 wells at and near the Idaho National Engineering Laboratory in eastern Idaho to provide reconnaissance data for future site-characterization studies. Surficial sediment, which is defined as the unconsolidated clay, silt, sand, and gravel that overlie the uppermost basalt flow at each well, ranges in thickness from 0 feet in seven wells drilled through basalt outcrops east of the Idaho Chemical Processing Plant to 313 feet in well Site 14 southeast of the Big Lost River sinks. Surficial sediment includes alluvial, lacustrine, eolian, and colluvial deposits that generally accumulated during the past 200 thousand years. Additional thickness data, not included in this report, are available from numerous auger holes and foundation borings at and near most facilities

77 FR 71842 - Exemption of Material for Proposed Disposal Procedures at the US Ecology Idaho Resource...

Science.gov (United States)

2012-12-04

... Proposed Disposal Procedures at the US Ecology Idaho Resource Conservation and Recovery Act Subtitle C... water solidified with clay containing low-activity radioactive material, at the US Ecology Idaho (USEI... and 10 CFR 70.17 Exemption of Humboldt Bay Power Plant Waste For Disposal at US Ecology, Inc'' [ADAMS...

The Idaho National Engineering Laboratory Site environmental report for calendar Year 1990

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.; Shaw, R.M.

1991-06-01

The results of the various monitoring programs for 1990 indicate that most radioactivity from the Idaho National Engineering Laboratory (INEL) operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEL Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. The first section of the report summarizes Calendar Year 1990 and January 1 through April 1, 1991, INEL activities related to compliance with environmental regulations and laws. The balance of the report describes the surveillance program, the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results and discusses implications, if any. Nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) ground-water monitoring program are also summarized. 33 refs., 18 figs., 29 tabs

Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Ansley, Shannon Leigh

2002-02-01

The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

International Nuclear Information System (INIS)

Ansley, Shannon L.

2002-01-01

The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

Heavy element radionuclides (Pu, Np, U) and {sup 137}Cs in soils collected from the Idaho National Engineering and Environmental Laboratory and other sites in Idaho, Montana, and Wyoming

Energy Technology Data Exchange (ETDEWEB)

Beasley, T.M.; Rivera, W. Jr. [Dept. of Energy, New York, NY (United States). Environmental Measurements Lab.; Kelley, J.M.; Bond, L.A. [Pacific Northwest National Lab., Richland, WA (United States); Liszewski, M.J. [Bureau of Reclamation (United States); Orlandini, K.A. [Argonne National Lab., IL (United States)

1998-10-01

The isotopic composition of Pu in soils on and near the Idaho National Engineering and Environmental Laboratory (INEEL) has been determined in order to apportion the sources of the Pu into those derived from stratospheric fallout, regional fallout from the Nevada Test Site (NTS), and facilities on the INEEL site. Soils collected offsite in Idaho, Montana, and Wyoming were collected to further characterize NTS fallout in the region. In addition, measurements of {sup 237}Np and {sup 137}Cs were used to further identify the source of the Pu from airborne emissions at the Idaho Chemical Processing Plant (ICPP) or fugitive releases from the Subsurface Disposal Area (SDA) in the Radioactive Waste Management Complex (RWMC). There is convincing evidence from this study that {sup 241}Am, in excess of that expected from weapons-grade Pu, constituted a part of the buried waste at the SDA that has subsequently been released to the environment. Measurements of {sup 236}U in waters from the Snake River Plain aquifer and a soil core near the ICPP suggest that this radionuclide may be a unique interrogator of airborne releases from the ICPP. Neptunium-237 and {sup 238}Pu activities in INEEL soils suggest that airborne releases of Pu from the ICPP, over its operating history, may have recently been overestimated.

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

Energy Technology Data Exchange (ETDEWEB)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000.

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

International Nuclear Information System (INIS)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000

Evaluation of technologies for remediation of disposed radioactive and hazardous wastes in a facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Reno, H.W.; Martin, D.D.; Rasmussen, T.L.

1989-01-01

For the past twenty years the US Department of Energy has been investigating and evaluating technologies for the long term management of disposed transuranic contaminated wastes at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. More than fifty technologies have been investigated and evaluated and three technologies have been selected for feasibility study demonstration at the complex. This paper discusses the evaluation of those technologies and describes the three technologies selected for demonstration. The paper further suggests that future actions under the Comprehensive Environmental Response, Compensation, and Liability Act should build from previous evaluations completed heretofore. 18 refs., 3 figs., 1 tab

Assessment of CREAMS [Chemicals, Runoff, and Erosion from Agricultural Management Systems] and ERHYM-II [Ekalaka Rangeland Hydrology and Yield Model] computer models for simulating soil water movement on the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Laundre, J.W.

1990-05-01

The major goal of radioactive waste management is long-term containment of radioactive waste. Long-term containment is dependent on understanding water movement on, into, and through trench caps. Several computer simulation models are available for predicting water movement. Of the several computer models available, CREAMS (Chemicals, Runoff, and Erosion from Agricultural Management Systems) and ERHYM-II (Ekalaka Rangeland Hydrology and Yield Model) were tested for use on the Idaho National Engineering Laboratory (INEL). The models were calibrated, tested for sensitivity, and used to evaluate some basic trench cap designs. Each model was used to postdict soil moisture, evapotranspiration, and runoff of two watersheds for which such data were already available. Sensitivity of the models was tested by adjusting various input parameters from high to low values and then comparing model outputs to those generated from average values. Ten input parameters of the CREAMS model were tested for sensitivity. 17 refs., 23 figs., 20 tabs

Principles for disposal of radioactive and chemical hazardous wastes

International Nuclear Information System (INIS)

Merz, E. R.

1991-01-01

The double hazard of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, flammability, corrosiveness as well as chemical reactivity on the other hand. Chemotoxic waste normally has a much more complex composition than radioactive waste and appears in much larger quantities. However, the two types of waste have some properties in common when it comes to their long-term impact on health and the environment. In order to minimize the risk associated with mixed waste management, the material assigned for ultimate disposal should be thoroughly detoxified, inertized, or mineralized prior to conditioning and packaging. Good control over the environmental consequence of waste disposal requires that detailed criteria for tolerable contamination should be established, and that compliance with these criteria can be demonstrated. For radioactive waste, there has been an extensive international development of criteria to protect human health. For non-radioactive waste, derived criteria exist only for a limited number of substances

Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility; TOPICAL

International Nuclear Information System (INIS)

Ansley, Shannon L.

2002-01-01

The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

International Nuclear Information System (INIS)

Patterson, M.W.

1994-10-01

The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

In summary: Idaho National Engineering Laboratory site environmental report for calendar year 1995

International Nuclear Information System (INIS)

Roush, D.; Mitchell, R.G.; Peterson, D.

1996-08-01

Every human is exposed to natural radiation. This exposure comes from many sources, including cosmic radiation from outer space, naturally-occurring radon, and radioactivity from substances in our bodies. In addition to natural sources of radiation, humans can also be exposed to man-made sources of radiation. Examples of man-made sources include nuclear medicine, X-rays, nuclear weapons testing, and accidents at nuclear power plants. The Idaho National Engineering Laboratory (INEL) is a U.S. Department of Energy (DOE) research facility that deals, in part, with studying nuclear reactors and storing radioactive materials. Careful handling and rigorous procedures do not completely eliminate the risk of releasing radioactivity. So, there is a remote possibility for a member of the public near the INEL to be exposed to radioactivity from the INEL. Extensive monitoring of the environment takes place on and around the INEL. These programs search for radionuclides and other contaminants. The results of these programs are presented each year in a site environmental report. This document summarizes the Idaho National Engineering Laboratory Site Environmental Report for Calendar Year 1995

Environmental monitoring for EG and G Idaho facilities at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Tkachyk, J.W.; Wright, K.C.; Wilhelmsen, R.N.

1990-08-01

This report describes the 1989 environmental-monitoring activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G-operated facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Additional monitoring activities performed by Environmental Monitoring are also discussed, including drinking-water monitoring and nonradiological liquid-effluent monitoring, as well as data management. The primary purposes of monitoring are to evaluate environmental conditions and to provide and interpret data, in compliance with applicable regulations, to ensure protection of human health and the environment. This report compares 1989 environmental-monitoring data with derived concentration guides and with data from previous years. This report also presents results of sampling performed by the Radiological and Environmental Sciences Laboratory and by the United States Geological Survey. 17 refs., 49 figs., 11 tabs

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling

International Nuclear Information System (INIS)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid

2010-01-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Use of ArcGIS in Environmental Monitoring at Idaho National Laboratory

International Nuclear Information System (INIS)

Oertel, Giles

2007-01-01

The Idaho National Laboratory is a U.S. Department of Energy site located in southeastern Idaho. The INL is required to perform environmental monitoring of anthropogenically introduced contaminants. One primary contaminant of interest is radioactive Cs-137 which is resident in INL soils due to past operational activities and atmospheric weapons testing. Collection of field data is performed using vehicle mounted and portable radiation detector units. All data is combined in ArcGIS and displayed over georeferenced satellite images and digital elevation models. The use of the ArcGIS geostatistical analysis package enhances the ability to look for areas of higher Cs-137 concentration. Combining current monitoring results with meteorological wind pattern maps allows for siting of new and improved monitoring locations. Use of the ArcGIS package provides an integrated analysis and mapping protocol for use in radioactive contaminant monitoring

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

W. Mahlon Heileson

2006-10-01

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

Evans, R.B.; Brooks, R.W.; Roush, D.; Martin, D.B. [Environmental Science and Research Foundation, Idaho Falls, ID (United States); Lantz, B.S. [Dept. of Energy, Idaho Falls, ID (United States). Idaho Operations Office

1998-08-01

To verify that exposures resulting from operations at Department of Energy (DOE) nuclear facilities remain very small, each site at which nuclear activities are conducted operates an environmental surveillance program to monitor the air, water and any other pathway whereby radionuclides from operations might conceivably reach workers and members of the public. Environmental surveillance and monitoring results are reported annually to the DOE-Headquarters. This report presents a compilation of data collected in 1997 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering and Environmental Laboratory (INEEL). The results of the various monitoring programs for 1997 indicated that radioactivity from the INEEL operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines.

Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

International Nuclear Information System (INIS)

Evans, R.B.; Brooks, R.W.; Roush, D.; Martin, D.B.; Lantz, B.S.

1998-08-01

To verify that exposures resulting from operations at Department of Energy (DOE) nuclear facilities remain very small, each site at which nuclear activities are conducted operates an environmental surveillance program to monitor the air, water and any other pathway whereby radionuclides from operations might conceivably reach workers and members of the public. Environmental surveillance and monitoring results are reported annually to the DOE-Headquarters. This report presents a compilation of data collected in 1997 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering and Environmental Laboratory (INEEL). The results of the various monitoring programs for 1997 indicated that radioactivity from the INEEL operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines

Mixed waste treatment at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

1988-01-01

The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

Issues in radioactive mixed waste compliance with RCRA [Resource Conservation and Recovery Act]: Some examples from ongoing operations at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Eaton, D.L.; Smith, T.H.; Clements, T.L. Jr.; Hodge, V.

1990-01-01

Radioactive mixed waste is subject to regulation under both the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). The regulation of such waste is the responsibility of the Environmental Protection Agency (EPA) and either the Nuclear Regulatory Commission (NRC) or the Department of Energy (DOE), depending on whether the waste is commercially generated or defense-related. The recent application of the RCRA regulations to ongoing operations at the DOE's Idaho National Engineering Laboratory (INEL) are described in greater detail. 8 refs., 2 figs

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

2003-01-01

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, ''Radioactive Waste Management Manual.'' This equipment is known collectively as the Tank Farm Facility. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility

Chemical decontamination method for radioactive metal waste

International Nuclear Information System (INIS)

Onuma, Tsutomu; Akimoto, Hidetoshi

1991-01-01

The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

Assessment of impacts at the advanced test reactor as a result of chemical releases at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Rood, A.S.

1991-02-01

This report provides an assessment of potential impacts at the Advanced Test Reactor Facility (ATR) resulting from accidental chemical spill at the Idaho Chemical Processing Plant (ICPP). Spills postulated to occur at the Lincoln Blvd turnoff to ICPP were also evaluated. Peak and time weighted average concentrations were calculated for receptors at the ATR facility and the Test Reactor Area guard station at a height above ground level of 1.0 m. Calculated concentrations were then compared to the 15 minute averaged Threshold Limit Value - Short Term Exposure Limit (TLV-STEL) and the 30 minute averaged Immediately Dangerous to Life and Health (IDLH) limit. Several different methodologies were used to estimate source strength and dispersion. Fifteen minute time weighted averaged concentrations of hydrofluoric acid and anhydrous ammonia exceeded TLV-STEL values for the cases considered. The IDLH value for these chemicals was not exceeded. Calculated concentrations of ammonium hydroxide, hexone, nitric acid, propane, gasoline, chlorine and liquid nitrogen were all below the TLV-STEL value

Population ecology of small mammals on the radioactive waste management complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Groves, C.R.; Keller, B.L.

1983-01-01

Species composition, diversity, biomass, population dynamics, absolute density, and movements of small mammal populations were examined on and adjacent to a solid radioactive waste disposal area in southeastern Idaho. The 15-month live-trapping study resulted in marking 2384 individuals representing 10 species of small mammals. Three vegetation types were sampled: crested wheatgrass (Agropyron cristatum) and Russian thistle (Salsola kali) habitats on the disposal area and native sagebrush (Artemisia tridentata) habitat surrounding the disposal area. The deer mouse (Peromyscus maniculatus) was the most common rodent in both disposal area habitats as well as the adjacent sagebrush habitat; Ord's kangaroo rat (Dipodomys ordii) was also an abundant rodent in all vegetation types. The montane vole (Microtus montanus) was common only in crested wheatgrass stands on the disposal area. The annual total small mammal biomass of 346 kg for the entire disposal area represents a potentially large vector for movement of radionuclides off the disposal area. However, the number of animals known to contact waste areas and traverse at least 50 m beyond the perimeter of the SDA appears to be small (8.7%)

Depth and temporal variations in water quality of the Snake River Plain aquifer in well USGS-59 near the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

Frederick, D.B.; Johnson, G.S.

1997-03-01

In-situ measurements of the specific conductance and temperature of ground water in the Snake River Plain aquifer were collected in observation well USGS-59 near the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. These parameters were monitored at various depths in the aquifer from October 1994 to August 1995. The specific conductance of ground water in well USGS-59, as measured in the borehole, ranged from about 450 to 900 microS/cm at standard temperature (25 C). The pumping cycle of the production wells at the Idaho Chemical Processing Plant causes changes in borehole circulation patterns, and as a result the specific conductance of ground water at some depths in the well varies by up to 50% over a period of about 14 hours. However, these variations were not observed at all depths, or during each pumping cycle. The temperature of ground water in the well was typically between 12.8 and 13.8 C. The results of this study indicate that temporal variations in specific conductance of the ground water at this location are caused by an external stress on the aquifer--pumping of a production well approximately 4,000 feet away. These variations are believed to result from vertical stratification of water quality in the aquifer and a subsequent change in intrawell flow related to pumping. When sampling techniques that do not induce a stress on the aquifer (i.e., thief sampling) are used, knowledge of external stresses on the system at the time of sampling may aid in the interpretation of geochemical data

Chemically reducing decontamination method for radioactive metal

International Nuclear Information System (INIS)

Tanaka, Akio; Onuma, Tsutomu; Sato, Hitoshi.

1994-01-01

The present invention concerns a decontamination method of electrolytically reducing radioactive metal wastes, then chemically dissolving the surface thereof with a strong acid decontaminating solution. This method utilizes dissolving characteristics of stainless steels in the strong acid solution. That is, in the electrolytic reduction operation, a portion of the metal wastes is brought into contact with a strong acid decontaminating solution, and voltage and current are applied to the portion and keep it for a long period of time so as to make the potential of the immersed portion of the metal wastes to an active soluble region. Then, the electrolytic reduction operation is stopped, and the metal wastes are entirely immersed in the decontaminating solution to decontaminate by chemical dissolution. As the decontaminating solution, strong acid such as sulfuric acid, nitric acid is used. Since DC current power source capacity required for causing reaction in the active soluble region can be decreased, the decontamination facility can be minimized and simplified, and necessary electric power can be saved even upon decontamination of radioactive metal wastes made of stainless steels and having a great area. Further, chemical dissolution can be conducted without adding an expensive oxidizing agent. (N.H.)

Idaho Chemical Processing Plant (ICPP) injection well: Operations history and hydrochemical inventory of the waste stream

International Nuclear Information System (INIS)

Fromm, J.; McCurry, M.; Hackett, W.; Welhan, J.

1994-01-01

Department of Energy (DOE), United States Geological Survey (USGS), and Idaho Chemical Processing Plant (ICPP) documents were searched for information regarding service disposal operations, and the chemical characteristics and volumes of the service waste emplaced in, and above, the Eastern Snake River Plain aquifer (ESRP) from 1953-1992. A summary database has been developed which synthesizes available, but dispersed, information. This assembled data records spatial, volumetric and chemical input patterns which will help establish the initial contaminant water characteristics required in computer modeling, aid in interpreting the monitoring well network hydrochemical information, and contribute to a better understanding of contaminant transport in the aquifer near the ICPP. Gaps and uncertainties in the input record are also identified with respect to time and type. 39 refs., 5 figs., 5 tabs

ICPP [Idaho Chemical Processing Plant] environmental monitoring report, CY-1988

International Nuclear Information System (INIS)

Krivanek, K.R.

1989-08-01

Summarized in this report are the data collected through Environmental Monitoring programs conducted at the Idaho Chemical Processing Plant (ICPP) by the Environmental Engineering (EE) Section of the Nuclear and Industrial Safety (N and IS) Department. The ICPP is responsible for complying with all applicable Federal, State, Local and DOE Rules, Regulations and Orders. Radiological effluent and emissions are regulated by the DOE. The Environmental Protection Agency (EPA) regulates all nonradiological waste resulting from the ICPP operations including all airborne, liquid, and solid waste. The EE subsection completed a Quality Assurance (QA) Plan for Environmental Monitoring activities during the third quarter of 1986. QA activities have resulted in the ICPP's implementation of the Environmental Protection Agency rules and guidelines pertaining to the collection, analyses, and reporting of environmentally related samples. Where no approved methods for analyses existed for radionuclides, currently used methods were submitted for the EPA approval. 33 figs., 14 tabs

TRUEX partitioning from radioactive ICPP sodium bearing waste

International Nuclear Information System (INIS)

Herbst, R.S.; Brewer, K.N.; Tranter, T.J.; Todd, T.A.

1995-03-01

The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in resulting volumes of high activity waste (HAW) which must be dispositioned. Numerous studies conducted at the ICPP indicate the applicability of the TRUEX process has been demonstrated; however, these studies relied on a simulated SBW surrogate for the real waste. Consequently, a series of batch contacts were performed on samples of radioactive ICPP SBW taken from tank WM-185 to verify that actual waste would behave similarly to the simulated waste. The test results with SBW from tank WM-185 indicate the TRUEX solvent effectively extracts the actinides from the samples of actual waste. Gross alpha radioactivity, attributed predominantly to Pu and Am, was reduced from 3.14E+04 dps/mL to 1.46 dps/mL in three successive batch contacts with fresh TRUEX solvent. This reduction corresponds to a decontamination factor of DF = 20,000 or 99.995% removal of the gross a activity in the feed. The TRUEX solvent also extracted the matrix components Zr, Fe, and Hg to an appreciable extent (D Zr > 10, D Fe ∼ 2, D Hg ∼6). Iron co-extracted with the actinides can be successfully scrubbed from the organic with 0.2 M HNO 3 . Mercury can be selectively partitioned from the actinides with either sodium carbonate or nitric acid (≥ 5 M HNO 3 ) solutions

Idaho National Engineering Laboratory radioecology and ecology programs. 1983 progress report

International Nuclear Information System (INIS)

Markham, O.D.

1983-06-01

Progress is reported in research on: the baseline ecology of the Idaho National Engineering Laboratory (INEL), the effects of disturbance on animal and plant communities, and the behavior of radionuclides in the environment surrounding radioactive waste sites. Separate abstracts have been prepared for individual reports

Radioactive waste management information for 1993 and record-to-date

International Nuclear Information System (INIS)

Taylor, K.A.

1994-07-01

This document presents detailed data, bar graphs, and pie charts on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1993. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System

Radioactive waste management information for 1990 and record-to-date

International Nuclear Information System (INIS)

Litteer, D.L.; Peterson, C.N.; Sims, A.M.

1991-07-01

This document presents detailed data and graphics on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1990. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System (RWMIS)

1982 environmental monitoring program report for Idaho National Engineering Laboratory site

International Nuclear Information System (INIS)

1983-05-01

The results of the various monitoring programs for 1982 indicated that radioactivity from the Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region. Although some radioactive materials were discharged during Site operations, concentrations and dose to the surrounding population were of no health consequence and were far less than State of Idaho and federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site. The report also compares and evaluates the sample results and discusses implications

Natural radiation, radioactive waste and chemical risk determinants

International Nuclear Information System (INIS)

Christensen, T.; Mustonen, R.; Edhwall, H.; Hansen, H.; Soerensen, A.; Stranden, E.

1990-01-01

Doses from natural radiation to the population in the Nordic countries are summarized, and man-made modifications of the natural radiation environment are discussed. An account is given for the radiological concequences of energy concervation by reduced ventilation. Risks from possible future releases of radioactivity from final depositories of spent nuclear fuel are compared to the risks from present natural radioactivity in the environment. The possibilities for comparison between chemical and radiological risks are discussed. 104 refs., 36 figs., 47 tabs

Idaho National Engineering Laboratory radioecology and ecology programs. 1983 progress report

Energy Technology Data Exchange (ETDEWEB)

Markham, O. D. [ed.

1983-06-01

Progress is reported in research on: the baseline ecology of the Idaho National Engineering Laboratory (INEL), the effects of disturbance on animal and plant communities, and the behavior of radionuclides in the environment surrounding radioactive waste sites. Separate abstracts have been prepared for individual reports. (ACR)

Site-specific probabilistic seismic hazard analyses for the Idaho National Engineering Laboratory. Volume 1: Final report

International Nuclear Information System (INIS)

1996-05-01

This report describes and summarizes a probabilistic evaluation of ground motions for the Idaho National Engineering Laboratory (INEL). The purpose of this evaluation is to provide a basis for updating the seismic design criteria for the INEL. In this study, site-specific seismic hazard curves were developed for seven facility sites as prescribed by DOE Standards 1022-93 and 1023-96. These sites include the: Advanced Test Reactor (ATR); Argonne National Laboratory West (ANL); Idaho Chemical Processing Plant (ICPP or CPP); Power Burst Facility (PBF); Radioactive Waste Management Complex (RWMC); Naval Reactor Facility (NRF); and Test Area North (TAN). The results, probabilistic peak ground accelerations and uniform hazard spectra, contained in this report are not to be used for purposes of seismic design at INEL. A subsequent study will be performed to translate the results of this probabilistic seismic hazard analysis to site-specific seismic design values for the INEL as per the requirements of DOE Standard 1020-94. These site-specific seismic design values will be incorporated into the INEL Architectural and Engineering Standards

Chemical durability of glasses containing radioactive fission product waste

International Nuclear Information System (INIS)

Mendel, J.E.; Ross, W.A.

1974-04-01

Measurements made to determine the chemical durability of glasses for disposal of radioactive waste are discussed. The term glass covers materials varying from true glass with only minute quantities of crystallites, such as insoluble RuO 2 , to quasi glass-ceramics which are mostly crystalline. Chemical durability requirements and Soxhlet extractor leach tests are discussed

Geothermometric evaluation of geothermal resources in southeastern Idaho

Science.gov (United States)

Neupane, G.; Mattson, E. D.; McLing, T. L.; Palmer, C. D.; Smith, R. W.; Wood, T. R.; Podgorney, R. K.

2016-01-01

Southeastern Idaho exhibits numerous warm springs, warm water from shallow wells, and hot water from oil and gas test wells that indicate a potential for geothermal development in the area. We have estimated reservoir temperatures from chemical composition of thermal waters in southeastern Idaho using an inverse geochemical modeling technique (Reservoir Temperature Estimator, RTEst) that calculates the temperature at which multiple minerals are simultaneously at equilibrium while explicitly accounting for the possible loss of volatile constituents (e.g., CO2), boiling and/or water mixing. The temperature estimates in the region varied from moderately warm (59 °C) to over 175 °C. Specifically, hot springs near Preston, Idaho, resulted in the highest reservoir temperature estimates in the region.

Remote ignitability analysis of high-level radioactive waste

International Nuclear Information System (INIS)

Lundholm, C.W.; Morgan, J.M.; Shurtliff, R.M.; Trejo, L.E.

1992-09-01

The Idaho Chemical Processing Plant (ICPP), was used to reprocess nuclear fuel from government owned reactors to recover the unused uranium-235. These processes generated highly radioactive liquid wastes which are stored in large underground tanks prior to being calcined into a granular solid. The Resource Conservation and Recovery Act (RCRA) and state/federal clean air statutes require waste characterization of these high level radioactive wastes for regulatory permitting and waste treatment purposes. The determination of the characteristic of ignitability is part of the required analyses prior to calcination and waste treatment. To perform this analysis in a radiologically safe manner, a remoted instrument was needed. The remote ignitability Method and Instrument will meet the 60 deg. C. requirement as prescribed for the ignitability in method 1020 of SW-846. The method for remote use will be equivalent to method 1020 of SW-846

Hazardous and mixed waste solidification development conducted at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Boehmer, A.M.; Larsen, M.M.

1986-04-01

EG and G Idaho, Inc., has initiated a program to develop safe, efficient, cost-effective solidification treatment methods for the disposal of some of the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). Testing has shown that Extraction Procedure (EP) toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long-term disposal as general or low-level waste, depending upon the radioactivity. The results of the solidification development program are presented in this report

Chemical precipitation processes for the treatment of aqueous radioactive waste

International Nuclear Information System (INIS)

1992-01-01

Chemical precipitation by coagulation-flocculation and sedimentation has been commonly used for many years to treat liquid (aqueous) radioactive waste. This method allows the volume of waste to be substantially reduced for further treatment or conditioning and the bulk of the waste to de discharged. Chemical precipitation is usually applied in combination with other methods as part of a comprehensive waste management scheme. As with any other technology, chemical precipitation is constantly being improved to reduce cost to increase the effectiveness and safety on the entire waste management system. The purpose of this report is to review and update the information provided in Technical Reports Series No. 89, Chemical Treatment of Radioactive Wastes, published in 1968. In this report the chemical methods currently in use for the treatment of low and intermediate level aqueous radioactive wastes are described and illustrated. Comparisons are given of the advantages and limitations of the processes, and it is noted that good decontamination and volume reduction are not the only criteria according to which a particular process should be selected. Emphasis has been placed on the need to carefully characterize each waste stream, to examine fully the effect of segregation and the importance of looking at the entire operation and not just the treatment process when planning a liquid waste treatment facility. This general approach includes local requirements and possibilities, discharge authorization, management of the concentrates, ICRP recommendations and economics. It appears that chemical precipitation process and solid-liquid separation techniques will continue to be widely used in liquid radioactive waste treatment. Current research and development is showing that combining different processes in one treatment plant can provide higher decontamination factors and smaller secondary waste arisings. Some of these processes are already being incorporated into new and

Estimation of hydraulic properties and development of a layered conceptual model for the Snake River plain aquifer at the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Frederick, D.B.; Johnson, G.S.

1996-02-01

The Idaho INEL Oversight Program, in association with the University of Idaho, Idaho Geological Survey, Boise State University, and Idaho State University, developed a research program to determine the hydraulic properties of the Snake River Plain aquifer and characterize the vertical distribution of contaminants. A straddle-packer was deployed in four observation wells near the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory. Pressure transducers mounted in the straddle-packer assembly were used to monitor the response of the Snake River Plain aquifer to pumping at the ICPP production wells, located 2600 to 4200 feet from the observation wells. The time-drawdown data from these tests were used to evaluate various conceptual models of the aquifer. Aquifer properties were estimated by matching time-drawdown data to type curves for partially penetrating wells in an unconfined aquifer. This approach assumes a homogeneous and isotropic aquifer. The hydraulic properties of the aquifer obtained from the type curve analyses were: (1) Storativity = 3 x 10 -5 , (2) Specific Yield = 0.01, (3) Transmissivity = 740 ft 2 /min, (4) Anisotropy (Kv:Kh)= 1:360

Retrofit design of remotely removable decontamination spray nozzles for the new waste calcining facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Gay, J.A.

1988-01-01

High level radioactive liquid waste is converted to a solid form at the Idaho Chemical Processing Plant (ICPP). The conversion is done by a fluidized bed combustion process in the calciner vessel. The interior decontamination system for the calciner vessel uses a common header bolted to four decontamination nozzles around the upper head. The retrofit was required to eliminate hands-on maintenance and difficulty in nozzle removal because of nozzle plugging. The retrofit design for this project demonstrates the solution of problems associated with thermal phenomena, structural supports, seismic requirements, remote handling and installations into extremely restricted spaces

Idaho: basic data for thermal springs and wells as recorded in GEOTHERM, Part A

Energy Technology Data Exchange (ETDEWEB)

Bliss, J.D.

1983-07-01

All chemical data for geothermal fluids in Idaho available as of December 1981 is maintained on GEOTHERM, computerized information system. This report presents summaries and sources of records for Idaho. 7 refs. (ACR)

Improvement of the safety regulations in the management of radioactive waste accumulated in the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), the Siberian Chemical Plant (Seversk) and the Mining-Chemical Plant (Zheleznogorsk)

International Nuclear Information System (INIS)

Vishnevski, Y.G.; Kislov, A.I.; Irushkin, V.M.

2002-01-01

One of the most important problems of radiation safety in Russia is the decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). The liquid radioactive waste water basins were constructed in 1950-1960 for the collection and storage of liquid waste from the radiochemical plants. The potential hazards of the liquid in the radioactive waste water basins are: migration of radionuclides into the soil of the liquid radioactive waste water basin floors; wind-induced carry-over of radionuclides from the liquid radioactive waste water basins; hazards (radiation included) to the environment and population arising in case physical barriers and hydraulic structures are damaged; and criticality hazards. The classification of the liquid radioactive waste water basins were developed based on the collection and analyzes of the information on liquid radioactive waste water basin characteristics and the method of multicriterion expert assessment of potential hazards. Three main directions for the improvement of safety regulation in the management of radioactive waste accumulated in the liquid radioactive waste water basins were defined: 1. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories contaminated with radioactive substances. 2. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories, such as the liquid radioactive waste water basins. 3. Special directions for the regulatory activities in the area of operation and decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). As a result, concrete recommendations on safety regulation for the management of radioactive waste accumulated in the water basins were developed. (author)

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Energy Technology Data Exchange (ETDEWEB)

Staiger, M. Daniel, Swenson, Michael C.

2011-09-01

This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Staiger, M. Daniel; Swenson, Michael C.

2011-01-01

This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Remedial action selection report for the Lowman UMTRA project site, Idaho

International Nuclear Information System (INIS)

Matthews, M.L.; Nagel, J.

1991-09-01

The inactive uranium mill tailings site near Lowman, Idaho, was designated as one of 24 abandoned uranium tailings sites to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan and certify that the remedial action complies with the standards promulgated by the US Environmental Protection Agency (EPA). The remedial action plan (RAP), which includes this remedial action selection report (RAS), has been developed to serve a two-fold purpose. First, it describes the activities that are proposed by the DOE to accomplish long-term stabilization and control of residual radioactive materials at the inactive uranium processing site near Lowman, Idaho. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Idaho, and the NRC, becomes Appendix B of the Cooperative Agreement (No. DE-FC04-85AL20535) between the DOE and the State of Idaho

Neutron interrogator assay system for the Idaho Chemical Processing Plant waste canisters and spent fuel: preliminary description and operating procedures manual

International Nuclear Information System (INIS)

Menlove, H.O.; Eccleston, G.; Close, D.A.; Speir, L.G.

1978-05-01

A neutron interrogation assay system is being designed for the measurement of waste canisters and spent fuel packages at the new Idaho Chemical Processing Plant to be operated by Allied Chemical Corp. The assay samples consist of both waste canisters from the fluorinel dissolution process and spent fuel assemblies. The assay system is a 252 Cf ''Shuffler'' that employs a cyclic sequence of fast-neutron interrogation with a 252 Cf source followed by delayed-neutron counting to determine the 235 U content

In situ technology evaluation and functional and operational guidelines for treatability studies at the radioactive waste management complex at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hyde, R.A.; Donehey, A.J.; Piper, R.B.; Roy, M.W.; Rubert, A.L.; Walker, S.

1991-07-01

The purpose of this document is to provide EG ampersand G Idaho's Waste Technology Development Department with a basis for selection of in situ technologies for demonstration at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL) and to provide information for Feasibility Studies to be performed according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The demonstrations will aid in meeting Environmental Restoration/Waste Management (ER/WM) schedules for remediation of waste at Waste Area Group (WAG) 7. This report is organized in six sections. Section 1, summarizes background information on the sites to be remediated at WAG-7, specifically, the acid pit, soil vaults, and low-level pits and trenches. Section 2 discusses the identification and screening of in situ buried waste remediation technologies for these sites. Section 3 outlines the design requirements. Section 4 discusses the schedule [in accordance with Buried Waste Integrated Demonstration (BWID) scoping]. Section 5 includes recommendations for the acid pit, soil vaults, and low-level pits and trenches. A listing of references used to compile the report is given in Section 6. Detailed technology information is included in the Appendix section of this report

Chlorine-36 in the Snake River Plain aquifer at the Idaho National Engineering Laboratory: Origin and implications

International Nuclear Information System (INIS)

Beasley, T.M.; Cecil, L.D.; Mann, L.J.; Sharma, P.; Fehn, U.; Gove, H.E.; Kubik, P.W.

1993-01-01

Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. The measurements of 36 Cl in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3 H and 36 Cl concentrations in aquifer water and the advantages of 36 Cl as a tracer of subsurface-water dynamics at the site are discussed

Chlorine-36 in the Snake River Plain Aquifer at the Idaho National Engineering Laboratory; origin and implications

Science.gov (United States)

Beasley, T.M.; Cecil, L.D.; Sharma, P.; Kubik, P.W.; Fehn, U.; Mann, L.J.; Gove, H.E.

1993-01-01

Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. Our measurements of 36C1 in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3H and 36Cl concentrations in aquifer water and the advantages of 36C1 as a tracer of subsurface-water dynamics at the site are discussed.

The Idaho National Engineering Laboratory Site environmental report for calendar year 1991

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.; Bingham, L.

1992-09-01

The results of the various monitoring programs for 1991 indicate that most radioactivity from the Idaho National Engineering Laboratory (INEL) operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEL Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. The first section of the report summarizes Calendar Year 1991 and January 1 through June 1, 1992, INEL activities related to compliance with environmental regulations and laws. The major portion of the report summarizes results of the RESL environmental surveillance program, which includes the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to appropriate federal regulations and standards and discusses implications, if any. The US Geological Survey (USGS) groundwater monitoring program is briefly summarized and data from USGS reports are included in tables and maps showing the spread of contaminants. Effluent monitoring and nonradiological drinking water monitoring performed by INEL contractors are discussed briefly and data are summarized in tables

Argonne-West facility requirements for a radioactive waste treatment demonstration

International Nuclear Information System (INIS)

Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

1995-01-01

At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

Seismic scoping evaluation of high level liquid waste tank vaults at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Hashimoto, P.S.; Uldrich, E.D.; McGee, W.D.

1991-01-01

A seismic scoping evaluation of buried vaults enclosing high level liquid waste storage tanks at the Idaho Chemical Processing Plant has been performed. The objective of this evaluation was to scope out which of the vaults could be demonstrated to be seismically adequate against the Safe Shutdown Earthquake (SSE). Using approximate analytical methods, earthquake experience data, and engineering judgement, this study determined that one vault configuration would be expected to meet ICPP seismic design criteria, one would not be considered seismically adequate against the SSE, and one could be shown to be seismically adequate against the SSE using nonlinear analysis

1984 Environmental monitoring program report for Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Dickson, R.L.

1985-05-01

The results of the various monitoring programs for 1984 indicated that radioactivity from INEL Site operations could not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the Site. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and federal health protection guidelines. This report describes the air, water, and foodstuff samples routinely collected at the INEL boundary locations and at locations distant from the INEL Site; and it compares and evaluates the sample results, discussing implications, if any. The report also summarizes significant environmental activities at the INEL Site during 1984, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) groundwater monitoring program. 28 refs., 13 figs., 22 tabs

Chemical Composition Analysis of INEEL Phase 3 Glasses: Task Technical and QA Plan

International Nuclear Information System (INIS)

Peeler, D.

2000-01-01

For about four decades radioactive wastes have been collected and calcined from nuclear fuels reprocessing at the Idaho Chemical Processing Plant (ICPP). Over this time span, secondary radioactive waste from decontamination, laboratory activities and fuels storage activities have also been collected and stored as liquid. These liquid high-activity wastes (HAW) are collectively called Sodium Bearing Wastes (SBW). Currently about 5.7 million liters of these wastes are temporarily stored in stainless steel tanks at the Idaho National Engineering and Environmental Laboratory (INEEL). Vitrification is being considered as a treatment option for SBW. The resulting glass can be sent to either the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as remote handled transuranic waste (RH-TRU) or to the federal geologic repository for final disposal. In addition to the SBW, roughly 4,000 m3 of calcined high-level wastes (HLW) are currently being stored at INEEL in stainless steel bin sets. These calcined HLW may also be vitrified, either with or without a dissolution and separation process, and sent to the federal geologic repository for final disposal

Aerial gamma ray and magnetic survey: Idaho Project, Hailey, Idaho Falls, Elk City quadrangles of Idaho/Montana and Boise quadrangle, Oregon/Idaho. Final report

International Nuclear Information System (INIS)

1979-09-01

During the months of July and August, 1979, geoMetrics, Inc. collected 11561 line mile of high sensitivity airborne radiometric and magnetic data in Idaho and adjoining portions of Oregon and Montana over four 1 0 x 2 0 NTMS quadrangles (Boise, Hailey, Idaho Falls, and Elk City) as part of the Department of Energy's National Uranium Resource Evaluation Program. All radiometric and magnetic data were fully corrected and interpreted by geoMetrics and are presented as five volumes (one Volume I and four Volume II's). Approximately 95 percent of the surveyed areas are occupied by exposures of intrusive and extrusive rocks. The Cretaceous-Tertiary Idaho Batholith dominates the Elk City and Hailey quadrangles. The Snake River volcanics of Cenozoic Age dominate the Idaho Falls quadrangle and southeast part of the Hailey sheet. Tertiary Columbia River basalts and Idaho volcanics cover the Boise quadrangle. There are only two uranium deposits within the four quadrangles. The main uranium producing areas of Idaho lie adjacent to the surveyed area in the Challis and Dubois quadrangles

Idaho National Engineering and Environmental Laboratory Site Report on the Production and Use of Recycled Uranium

Energy Technology Data Exchange (ETDEWEB)

L. C. Lewis; D. C. Barg; C. L. Bendixsen; J. P. Henscheid; D. R. Wenzel; B. L. Denning

2000-09-01

Recent allegations regarding radiation exposure to radionuclides present in recycled uranium sent to the gaseous diffusion plants prompted the Department of Energy to undertake a system-wide study of recycled uranium. Of particular interest, were the flowpaths from site to site operations and facilities in which exposure to plutonium, neptunium and technetium could occur, and to the workers that could receive a significant radiation dose from handling recycled uranium. The Idaho National Engineering and Environmental Laboratory site report is primarily concerned with two locations. Recycled uranium was produced at the Idaho Chemical Processing Plant where highly enriched uranium was recovered from spent fuel. The other facility is the Specific Manufacturing Facility (SMC) where recycled, depleted uranium is manufactured into shapes for use by their customer. The SMC is a manufacturing facility that uses depleted uranium metal as a raw material that is then rolled and cut into shapes. There are no chemical processes that might concentrate any of the radioactive contaminant species. Recyclable depleted uranium from the SMC facility is sent to a private metallurgical facility for recasting. Analyses on the recast billets indicate that there is no change in the concentrations of transuranics as a result of the recasting process. The Idaho Chemical Processing Plant was built to recover high-enriched uranium from spent nuclear fuel from test reactors. The facility processed diverse types of fuel which required uniquely different fuel dissolution processes. The dissolved fuel was passed through three cycles of solvent extraction which resulted in a concentrated uranyl nitrate product. For the first half of the operating period, the uranium was shipped as the concentrated solution. For the second half of the operating period the uranium solution was thermally converted to granular, uranium trioxide solids. The dose reconstruction project has evaluated work exposure and

Biological effects of concomitant influence of radioactive and chemical factors. (Experimental research)

International Nuclear Information System (INIS)

Meshkov, N.A.

1995-01-01

Remote consequences of concomitant influence of radioactive and chemical hazards substances, modeling the ecological situation at the territory of the Altaj region after the nuclear tests at the Semipalatinsk test site is studied on the mice. Negative effect of the concomitant impact of radioactive and hazardous chemical substances on the basic morpho-functional systems of animals is revealed; the reproduction function proved to be the most sensitive one. It is noted that the radiation factor constitutes the basis of all violations of bone marrow blood-producing function by concomitant influence

Radioactive waste management information, 1982 summary and record-to-date

International Nuclear Information System (INIS)

Cassidy, G.B.

1983-07-01

This document summarizes radioactive waste data records for the Idaho National Engineering Laboratory (INEL) compiled since 1952. Kinds of information include volume, radioactivity, isotopic identity, origin, and decay status. The radioactive waste data presented was obtained from the INEL Radioactive Waste Management Information System (RWMIS). This report is updated annually to incorporate waste management data for the current year and reflects changes in previous annual reports. Changes are made to more accurately reflect the current status of waste operations at the INEL

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

International Nuclear Information System (INIS)

French, D.L.; Lisee, D.J.; Taylor, K.A.

1995-07-01

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

Three-dimensional chemical structure of the INEL aquifer system near the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

McCurry, M.; Estes, M.; Fromm, J.; Welhan, J.; Barrash, W.

1994-01-01

Sampling and analysis from the Snake River Plain aquifer using a stainless-steel and teflon constructed straddle-packer system has established detailed vertical profiles of aquifer chemistry from three wells near a major source of low-level waste injection at the Idaho Chemical Processing Plant. Multiple intervals, varying from 4.6 to 6.1 m in length, were sampled between the water table (140.5 mbls - meters below land surface), and approximately 200 mbls to obtain a wide spectrum of metals, anions, radiological and organic components analyses. Measurements were also made at the well sites of important transient parameters (T, Eh, Fe 3+ , Fe 2+ , DO and SC). The principal purpose of this ongoing work is to improve our understanding of the third (i.e. vertical) dimension of aquifer chemistry at the INEL as a basis for critically evaluating site-wide monitoring procedures, and, ultimately, for improving fate and transport models for aquifer contaminants within basalt-hosted aquifers. Chemical and radiological data indicates that substantial systematic vertical and lateral variations occur in the aquifer hydrochemistry - in particular for conservative radiological nuclide concentrations. Radiological data define a three-layered zonation. Ground water within upper and lower zones contain up to 10 times higher concentrations of H-3 and I-129 than in the middle zone. Sr-90 activity is decoupled from H-3 and I-129-relatively high activity was detected within the upper zone nearest the ICPP, but activities elsewhere are very low. 27 refs., 4 figs., 1 tab

Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Fourr, B.R.; Owen, A.H.; Williamson, D.J.; Nash, C.L.

1992-01-01

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO)

Lipid spectrum of the newborn rats' blood at the radioactive and chemical effects in the prenatal period

International Nuclear Information System (INIS)

Buzan, Kh.

1998-01-01

The radioactive and chemical factors used in complex or separately during the prenatal period in the experiment induce ambiguous effects on the lipid metabolism in blood plasma and erythrocytes of newborn rats. The chemicals cause more significant changes in the blood plasma lipid metabolism than the radioactive irradiation does. Being used combined the radioactive and chemical factors do not increase each other's effect- their effects have opposite directions. The radiochemical exposure induce more significant shifts in the lipid spectrum in erythrocytic membranes than the separate factors

Spread-sheet application to classify radioactive material for shipment

International Nuclear Information System (INIS)

Brown, A.N.

1998-01-01

A spread-sheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spread-sheet are used to confirm the proper US DOT classification when offering radioactive material packages for transport. The user must input to the spread-sheet the mass of the material being classified, the physical form (liquid or not) and the activity of each regulated nuclide. The spread-sheet uses these inputs to calculate two general values: 1)the specific activity of the material and a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material. If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three low specific activity designations (LSA-I, LSA-II, LSA-III, or not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity). This spread-sheet has proven to be an invaluable aid for shippers of radioactive materials at the Idaho National Engineering and Environmental Laboratory. (authors)

A summary of the environmental restoration program Retrieval Demonstration Project at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

McQuary, J.

1991-01-01

This document summarizes the of retrieval techniques developed to excavate buried transuranic (TRU) mixed waste from the Subsurface Disposal Area (SDA). The SDA is located at the Idaho National Engineering Laboratory (INEL) in the Radioactive Waste Management Complex (RWMC). 31 refs., 1 fig

Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2009

International Nuclear Information System (INIS)

2010-01-01

In February 1997, the U.S. Department of Energy (DOE), Nevada Operations Office (now known as the Nevada Site Office) issued the Mitigation Action Plan which addressed potential impacts described in the ''Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada'' (DOE/EIS 0243). The DOE, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Site (RWMS) at Area 5 and Area 3. Since 2006, the Area 3 RWMS has been in cold stand-by. This document satisfies requirements regarding low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to and from the NTS during FY 2009. In addition, this document provides shipment, volume, and route information on transuranic (TRU) waste shipped from the NTS to the Idaho National Laboratory, near Idaho Falls, Idaho.

Changes is radioactive iodine metabolism in acute chemical intoxications

International Nuclear Information System (INIS)

Selyutitskij, G.V.; Likhtarev, I.A.; Volkova, N.V.; Zvonova, I.A.; Ostryakova, N.I.

1978-01-01

It is shown that the response of the endocrine system (iodine-absorbing and hormone-secreting fUnctions of the thyroid) as studied by the radioactive iodine test may be a reasonably versatile indicator of the response of the thyroid component of the endocrine system to acute intoxication of the organism. Trials of this test using seven chemical substances have confirmed that the radioiodine test is a sufficienty universal method to be used in setting sanitary and hygienic standards for permissible levels of chemical substances

Description and hydrogeologic implications of cored sedimentary material from the 1975 drilling program at the Radioactive Waste Management Complex, Idaho

International Nuclear Information System (INIS)

Rightmire, C.T.

1984-08-01

Samples of sedimentary material from interbeds between basalt flows and from fractures in the flows, taken from two drill cores at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory were analyzed for (1) particle-size distribution, (2) bulk mineralogy, (3) clay mineralogy, (4) cation-exchange capacity, and (5) carbonate content. Thin sections of selected sedimentary material were made for petrographic examination. These analyses are needed for a characterization of paths and rates of movement of radionuclides transported by infiltrating water. Preliminary interpretations indicate that (1) it may be possible to distinguish the various sedimentary interbeds on the basis of their mineralogy, (2) the presence of carbonate horizons in sedimentary interbeds may be utilized to approximate the time of exposure and the climate while the surface was exposed, and (3) the type and orientation of fracture-filling material may be utilized to determine the mechanism by which fractures were filled. 9 references, 14 figures, 8 tables

Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1983-11-01

This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

Cost-time management for environmental restoration activities at the Department of Energy`s Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

Fourr, B.R.; Owen, A.H.; Williamson, D.J. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Nash, C.L. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1992-05-22

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy`s goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

Environmental assessment of remedial action at the Lowman Uranium Mill Tailings Site near Lowman, Idaho

International Nuclear Information System (INIS)

1991-01-01

This document assesses the environmental impacts of stabilization on site of the contaminated materials at the Lowman uranium mill tailings site. The Lowman site is 0.5 road mile northeast of the unincorporated village of Lowman, Idaho, and 73 road miles from Boise, Idaho. The Lowman site consists of piles of radioactive sands, an ore storage area, abandoned mill buildings, and windblown/waterborne contaminated areas. A total of 29.5 acres of land are contaminated and most of this land occurs within the 35-acre designated site boundary. The proposed action is to stabilize the tailings and other contaminated materials on the site. A radon barrier would be constructed over the consolidated residual radioactive materials and various erosion control measures would be implemented to ensure the long-term stability of the disposal cell. Radioactive constituents and other hazardous constituents were not detected in the groundwater beneath the Lowman site. The groundwater beneath the disposal cell would not become contaminated during or after remedial action so the maximum concentration limits or background concentrations for the contaminants listed in the draft EPA groundwater protection standards would be met at the point of compliance. No significant impacts were identified as a result of the proposed remedial action at the Lowman site

Low-level waste incineration: experience at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bohrer, H.A.; Dalton, J.D.

1987-01-01

The Waste Experimental Reduction Facility (WERF) is a low level radioactive waste treatment facility being operated at the Idaho National Engineering Laboratory (INEL). A key component of the facility is a dual chambered controlled air incinerator with a dry off-gas treatment system. The incinerator began processing radioactive waste in September, 1984. Limited operations continued from that data until October, 1985, at which time all INEL generators began shipping combustible waste for incineration. The incinerator is presently processing all available INEL combustible Dry Active Waste (DAW) (approximately 1700 m 3 per year) operating about five days per month. Performance to date has demonstrated the effectiveness, viability and safety of incineration as a volume reduction method of DAW. 3 figures

INEEL Radioactive Liquid Waste Reduction Program

International Nuclear Information System (INIS)

Millet, C.B.; Tripp, J.L.; Archibald, K.E.; Lauerhauss, L.; Argyle, M.D.; Demmer, R.L.

1999-01-01

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most

Chemical treatment of liquid radioactive waste at the Boris Kidric Institute

International Nuclear Information System (INIS)

Lazic, S.; Vukovic, Z.; Voko, A.

1989-01-01

The results of lab-scale experiments on the chemical treatment of radioactive liquid waste collected at the Boris Kidric Institute are presented. The radioactive waste was treated by cobalt hexacyanoferrate precipitation followed by flocculation with polyelectrolyte flocculating agents. The main parameters investigated were standing time, pH and ratio of reagents. The flocculating agents were tested by filtration test and floccule stability test. Satisfactory decontamination factors by precipitation at pH 10 and good separation of solid and liquid phase by applying Praestol polyelectrolytes were obtained (author)

Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 2 of 2. Appendices

International Nuclear Information System (INIS)

1983-11-01

This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

Design criteria for the new waste calcining facility at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Anderson, F.H.; Bingham, G.E.; Buckham, J.A.; Dickey, B.R.; Slansky, C.M.; Wheeler, B.R.

1976-01-01

The New Waste Calcining Facility (NWCF) at the Idaho Chemical Processing Plant (ICPP) is being built to replace the existing fluidized-bed, high-level waste calcining facility (WCF). Performance of the WCF is reviewed, equipment failures in WCF operation are examined, and pilot-plant studies on calciner improvements are given in relation to NWCF design. Design features of the NWCF are given with emphasis on process and equipment improvements. A major feature of the NWCF is the use of remote maintenance facilities for equipment with high maintenance requirements, thereby reducing personnel exposures during maintenance and reducing downtime resulting from plant decontamination. The NWCF will have a design net processing rate of 11.36 m 3 of high-level waste per day, and will incorporate in-bed combustion of kerosene for heating the fluidized bed calciner. The off-gas cleaning system will be similar to that for the WCF

Characterization of radioactive contamination inside pipes with the Pipe Explorer trademark system

International Nuclear Information System (INIS)

Lowry, W.

1994-01-01

The objective for the development of the Pipe Explorer trademark radiological characterization system is to achieve a cost effective, low risk means of characterizing gamma radioactivity on the inside surface of pipes. The unique feature of this inspection system is the use of a pneumatically inflated impermeable membrane which transports the detector into the pipe as it inverts. The membrane's internal air pressure tows the detector and tether through the pipe. This mechanism isolates the detector and its cabling from the contaminated surface, yet allows measurement of radioactive emissions which can readily penetrate the thin plastic membrane material (such as gamma and high energy beta emissions). In Phase 1, an initial survey of DOE facilities was conducted to determine the physical and radiological characteristics of piping systems. The inverting membrane deployment system was designed and extensively tested in the laboratory. A range of membrane materials was tested to evaluate their ruggedness and deployment characteristics. Two different sizes of gamma scintillation detectors were procured and tested with calibrated sources. Radiation transport modeling evaluated the measurement system's sensitivity to detector position relative to the contaminated surface, the distribution of the contamination, background gamma levels, and gamma source energy levels. In the culmination of Phase 1, a field demonstration was conducted at the Idaho National Engineering Laboratory's Idaho Chemical Processing Plant. The project is currently in transition from Phase 1 to Phase 2, where more extensive demonstrations will occur at several sites. Results to date are discussed

Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

Fourr, B.R.; Owen, A.H.; Williamson, D.J. (Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)); Nash, C.L. (USDOE Idaho Field Office, Idaho Falls, ID (United States))

1992-05-22

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Guenther, R.J.; Johnson, A.B. Jr.; Lund, A.L.; Gilbert, E.R.

1994-11-01

The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl x , UAl x -Al and U 3 O 8 -Al cermets, U-5% fissium, UMo, UZrH x , UErZrH, UO 2 -stainless steel cermet, and U 3 O 8 -stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified

Design and fabrication of a glovebox for the Plasma Hearth Process radioactive bench-scale system

International Nuclear Information System (INIS)

Wahlquist, D.R.

1996-01-01

This paper presents some of the design considerations and fabrication techniques for building a glovebox for the Plasma Hearth Process (PHP) radioactive bench-scale system. The PHP radioactive bench-scale system uses a plasma torch to process a variety of radioactive materials into a final vitrified waste form. The processed waste will contain plutonium and trace amounts of other radioactive materials. The glovebox used in this system is located directly below the plasma chamber and is called the Hearth Handling Enclosure (HHE). The HHE is designed to maintain a confinement boundary between the processed waste and the operator. Operations that take place inside the HHE include raising and lowering the hearth using a hydraulic lift table, transporting the hearth within the HHE using an overhead monorail and hoist system, sampling and disassembly of the processed waste and hearth, weighing the hearth, rebuilding a hearth, and sampling HEPA filters. The PHP radioactive bench-scale system is located at the TREAT facility at Argonne National Laboratory-West in Idaho Falls, Idaho

Physical and chemical removal of radioactive oxide layers

International Nuclear Information System (INIS)

Blesa, M.A.; Baumgartner, E.C.; Maroto, A.J.G.

1983-01-01

When a nuclear reactor is operating under steady state conditions, the balance between release of activated crud and pick-up and activation of circulating crud dictates the overall contribution to the growth of radiation fields by the release of crud from the fuel elements. Whole-circuit decontamination procedures which are carried out with the fuel elements in-core must take into account that during such procedure this balance is abruptly changed in the sense of releasing considerable amounts of radioactivity towards out-of-core components. In principle, this disruption of balance operates against the decontamination objectives, usually the lowering of radiation fields throughout the primary circuit. This is applicable to the two processes that involve fuel decontamination: cycling redox techniques and whole-circuit chemical decontaminations. However, data on actual cycling redox procedures performed in Atucha I Nuclear Power Station are presented which demonstrate that under appropriate process conditions such release does not prevent the achieval of reasonable decontamination factors in critical components. The relevance of optimum cleaning rates, redeposition rates, reagent injection strategies, and the ways to achieve these are discussed. In chemical decontamination procedures, it is of importance to assess the relative contribution of fuel elements and out-of-core components to dissolved radioactive crud. In order to do this, the mechanisms of dissolution of crud on steel surfaces and on Zircaloy surfaces are compared for the most usual reagents

Radioactive and hazardous chemical wastes. Impact on man and his environment

International Nuclear Information System (INIS)

Parker, F.L.; Suess, M.J.

1984-01-01

The main objective of the various safety measures in all fields of human activities is to prevent deleterious effects of various agents on human health. Preventive health and safety measures therefore play an important role in achieving the main goal of the World Health Organization (WHO): 'Health for all by the year 2000'. The present WHO programme on environmental health emphasizes the prevention of chemical hazards as one of the most important environmental factors affecting human health. At the same time, protection from physical factors, including radiological protection, is part of this programme. Therefore, WHO compares health detriments from both physical and chemical agents. The paper describes the hazardous waste problems of great concern in industrialized countries. For instance, the Commission of the European Communities countries produce about 2x10 9 tonnes of waste per year, a rate which grows by 2 to 3% annually. This poses serious problems of pollution, particularly where the toxic ingredients do not decay. Special attention will also be given to the safe handling of high-level radioactive waste from the peaceful use of nuclear technology. These wastes have to be stored in safe storage facilities, or be disposed of without causing damage to man and his environment. The international measures to contain and control these wastes are described, including the activities of WHO within the Global Environmental Monitoring System and Regional Sea programmes of the United Nations Environment Programme. Guidelines and methodologies for the management of hazardous chemical and radioactive wastes are being developed through WHO to assist national authorities in this task. The paper pays special attention to a comparative assessment of environmental and public health impacts of toxic chemical and radioactive wastes. (author)

Radioactivity in chemical and organic fertilizer used in Egypt

International Nuclear Information System (INIS)

Abbady, A.G.E.; Yousef, A.M.M.; Abbady, A.; El-Taher, A.

2005-01-01

The Egypt Chemical factories (ECF); such as Talkha, Sues, Abo Qeyer, Kafer Elzayat, and Assuit factories, produces and markets a range of phosphate based fertilizers, including Simple Super Phosphate (SSP) fertilizer, Triple Super Phosphate (TSP) fertilizer and Urea. Phosphate fertilizers produced by ECF are derived from phosphate ore. In addition to phosphate minerals, these ores can contain significant amounts of a wide range of impurities, including heavy metals and naturally occurring radionuclides. This study was carried out to determine the content of radionuclides in fertilizer products produced by ECF and some organic fertilizer (animal manure) includes cow, sheep and chicken fertilizer. In both samples (Chemical and organic fertilizers), the activity concentrations of Ra 2 26 are higher than those Th 2 32. The radioactivity of 226 R a in chemical fertilizers ranged from 21.6 ± 3.6 to 111.2 ± 8.9 Bq kg-1, phosphate fertilizers TSP contained high contents of 226 R a. The average radioactivity of 226 R a in TSP was 79.3 ± 7.4 Bq kg-1, in SSP 51.2 ± 5 Bq kg-1, and in Urea 35.1± 3.5 Bq kg-1. The activity of 232 T h in the different fertilizers ranged from 1.3 ± 1.1 to 9.9 ± 3.2 Bq kg-1,the highest activity observed in SSP fertilizer. The activity of 40 K was found to be great in the TSP fertilizer, which contained a mean activity 478.1± 21.3 Bq kg-1. With respect to organic fertilizers the average radioactivity of 226 R a, 232 T h and 40 K are 40 ± 1.6 Bq kg-1, 3.1± 1.2 and 427.1± 20 Bq kg-1. The data are discussed and compared with those given in the literatures. This study could be useful as baseline data for radiation exposure to fertilizers, and their impact on human health

Vapor vacuum extraction treatability study at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Herd, M.D.; Matthern, G.; Michael, D.L.; Spang, N.; Downs, W.; Weidner, J.; Cleary, P.

1993-01-01

During the 1960s and early 1970s, barreled mixed waste containing volatile organic compounds (VOCS) and radioactive waste was buried at the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). Over time, some of the barrels have deteriorated allowing, VOC vapors to be released into the vadose zone. The primary VOC contaminates of concern are CCl 4 and trichloroethylene; however, chloroform, tetrachloroethylene, and 1,1,1-trichloroethane have also been detected. Vapor Vacuum Extraction (VVE) is one alternative being considered for remediation of the RWMC SDA vadose zone. A proposed pilot-scale treatability study (TS) will provide operation and maintenance costs for the design of the potential scale-up of the system

Changes in soil hydraulic properties caused by construction of a simulated waste trench at the Idaho National Engineering Laboratory, Idaho

International Nuclear Information System (INIS)

Shakofsky, S.

1995-03-01

In order to assess the effect of filled waste disposal trenches on transport-governing soil properties, comparisons were made between profiles of undisturbed soil and disturbed soil in a simulated waste trench. The changes in soil properties induced by the construction of a simulated waste trench were measured near the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL) in the semiarid southeast region of Idaho. The soil samples were collected, using a hydraulically-driven sampler to minimize sample disruption, from both a simulated waste trench and an undisturbed area nearby. Results show that the undisturbed profile has distinct layers whose properties differ significantly, whereas the soil profile in the simulated waste trench is, by comparison, homogeneous. Porosity was increased in the disturbed cores, and, correspondingly, saturated hydraulic conductivities were on average three times higher. With higher soil-moisture contents (greater than 0.32), unsaturated hydraulic conductivities for the undisturbed cores were typically greater than those for the disturbed cores. With lower moisture contents, most of the disturbed cores had greater hydraulic conductivities. The observed differences in hydraulic conductivities are interpreted and discussed as changes in the soil pore geometry

A comparison and cross-reference of commercial low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

Kerr, T.A.

1997-04-01

This document, prepared by the National Low-Level Waste Management Program at the Idaho National Engineering and Environmental Laboratory, is a comparison and cross-reference of commercial low-level radioactive waste acceptance criteria. Many of these are draft or preliminary criteria as well as implemented criteria at operating low-level radioactive waste management facilities. Waste acceptance criteria from the following entities are included: US Nuclear Regulatory Commission, South Carolina, Washington, Utah, Nevada, California, illinois, Texas, North Carolina, Nebraska, Pennsylvania, New York, and the Midwest Compact Region. Criteria in the matrix include the following: physical form, chemical form, liquid limits, void space in packages, concentration averaging, types of packaging, chelating agents, solidification media, stability requirements, sorptive media, gas, oil, biological waste, pyrophorics, source material, special nuclear material, package dimensions, incinerator ash, dewatered resin, transuranics, and mixed waste. Each criterion in the matrix is cross-referenced to its source document so that exact requirements can be determined

Los Alamos Controlled Air Incinerator for hazardous chemical and mixed radioactive wastes

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Koenig, R.A.; Warner, C.L.

1986-01-01

The Los Alamos Controlled Air Incinerator (CAI) is currently the only radioactive waste incineration facility in the US permitted to treat polychlorinated biphenyls (PCBs). The CAI was developed in the mid-1970's as a demonstration system for volume reduction of transuranic (TRU) contaminated combustible solid wastes. It has since undergone additions and modifications to accommodate hazardous chemical wastes in response to a need within the Department of Energy (DOE) to treat mixed radioactive/chemical wastes. An overview of these additions which include a liquid feed system, a high intensity liquid injection burner, and an activated carbon adsorption unit is presented here. Also included is a discussion of the procedures required for Toxic Substances Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) permitting of the CAI

The role of performance assessment in the evaluation of remedial action alternatives for the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rood, A.S.; Case, M.J.

1988-01-01

The Idaho National Engineering Laboratory (INEL) is operated by the Department of Energy (DOE) and is involved in nuclear research and development. The Radioactive Waste Management Complex (RWMC) at the INEL serves as a disposal facility for low level radioactive wastes generated onsite. Transuranic (TRU) wastes received from other DOE sites are currently stored at the RWMC, but were buried at the facility from 1952 until 1970. Recent findings of the Subsurface Investigations Program have determined that migration of TRU nuclides and hazardous materials from the RWMC has occurred. The primary source of organics in the buried TRU waste was generated by the Rocky Flats Plant. The INEL has proposed an aggressive four-year action plan for buried TRU waste. As a part of this plan, a task has been identified to evaluate existing remedial technologies for preventing further contaminant migration or removing the source of TRU radionuclides and nonradioactive hazardous material from the RWMC. A systems approach is being applied to evaluate, compare and recommend technologies or combinations of technologies. One criterion used in the evaluation is the net risk reduction afforded by each proposed remedial action. The method used to develop the criterion relies on models to assess the potential pathways and scenarios for the migration of radioactive and nonradioactive materials and the subsequent exposure of individuals to those materials. This paper describes the approach used to assess the performance of various remedial actions and the results obtained to date

Impact of surface water recharge on the design of a groundwater monitoring system for the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wood, T.R.

1990-01-01

Recent hydrogeologic studies have been initiated to characterize the hydrogeologic conditions at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Measured water levels in wells penetrating the Snake River Plain aquifer near the RWMC and the corresponding direction of flow show change over time. This change is related to water table mounding caused by recharge from excess water diverted from the Big Lost River for flood protection during high flows. Water levels in most wells near the RWMC rise on the order of 10 ft (3 m) in response to recharge, with water in one well rising over 60 ft (18 m). Recharge changes the normal south-southwest direction of flow to the east. Design of the proposed groundwater monitoring network for the RWMC must account for the variable directions of groundwater flow. 11 refs., 9 figs., 2 tabs

1975 progress report: Idaho National Engineering Laboratory site radioecology--ecology programs

International Nuclear Information System (INIS)

Markham, O.D.

1976-06-01

Results are reported from measurements of the content of various radionuclides in the tissues of wild animals on or near the Idaho National Engineering Laboratory sampled during 1975. Tissue samples from antelope, waterfowl, rodents, rabbits, and doves were analyzed for 13 radionuclides, including 134 Cs, 137 Cs, 95 Zr, 95 Nb, 103 Ru, 238 Pu, 239 Pu, 90 Sr, 131 I, and 60 Co which were responsible for the largest amounts of radioactivity. Measurements were also made of the content of 238 Pu, 239 Pu, and 241 Am in soil samples and the radioactivity in tumbling weeds at the radioactive waste management site. Data are included from studies on the ecology of the pygmy rabbit, Salvilagus idahoensis, amphibians, reptiles, birds of prey, rodents, and coyotes, and vegetation in relation to land use at the site. Seasonal variations in the deposition and retention of 141 Ce and 134 Cs on sagebrush and bottlebrush grass were compared

Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

International Nuclear Information System (INIS)

Jacobson, Victor Levon

2002-01-01

U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodium-bearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements

Investigation of the subsurface environment at the Idaho National Engineering Laboratory Radioactive Waste Management Complex

International Nuclear Information System (INIS)

Russell, B.F.; Mizell, S.A.; Hull, L.C.; Smith, T.H.; Lewis, B.D.; Barraclough, J.T.; Humphrey, T.G.

1984-01-01

A comprehensive, 10-year plan to investigate radionuclide migration in the subsurface at the Radioactive Waste Management Complex (RWMC) has been prepared and initiated (in FY-84). The RWMC Subsurface Investigation is designed to address two objectives set forth by the DOE Idaho Operations Office: (1) determine the extent of radionuclide migration, if any, from the buried waste, and (2) develop and calibrate a computer model to simulate long-term radionuclide migration. At the RWMC, the Snake River Plain Aquifer underlies about 177 m of partially saturated, fractured basalts and thin sedimentary units. Three sedimentary units, accounting for no more than 20 m of the partially saturated thickness, appear to be continuous throughout the area. Thinner sedimentary units are discontinuous. Low-level waste and (prior to 1970) transuranic waste have been buried in the surficial sediments at the RWMC. The first burials took place in 1952. Due to the complicated disposal system, a comprehensive review of state-of-the-art vadose zone monitoring instrumentation and techniques, an analysis of conceptual migration pathways, and an evaluation of potential hazard from buried radionuclides were conducted to guide preparation of the investigation plan. The plan includes an overview of the RWMC facility, subsurface work conducted to date at the RWMC and other DOE laboratory facilities, an evaluation and selection of the methods and studies to be used, a radionuclide hazard evaluation, a cost analysis, and external peer review results. In addition, an Appendix contains the details for each method/study to be employed. 4 references, 5 figures, 1 table

Idaho National Engineering and Environmental Laboratory Site Environmental Report for Calendar Year 1998

Energy Technology Data Exchange (ETDEWEB)

T. R. Saffle; R. G. Mitchell; R. B. Evans; D. B. Martin

2000-07-01

The results of the various monitoring programs for 1998 indicated that radioactivity from the DOE's Idaho National Engineering and Environmental Laboratory (INEEL) operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines. Gross alpha and gross beta measurements, used as a screening technique for air filters, were investigated by making statistical comparisons between onsite or boundary location concentrations and the distant community group concentrations. Gross alpha activities were generally higher at distant locations than at boundary and onsite locations. Air samples were also analyzed for specific radionuclides. Some human-made radionuclides were detected at offsite locations, but most were near the minimum detectable concentration and their presence was attributable to natural sources, worldwide fallout, and statistical variations in the analytical results rather than to INEEL operations. Low concentrations of 137Cs were found in muscle tissue and liver of some game animals and sheep. These levels were mostly consistent with background concentrations measured in animals sampled onsite and offsite in recent years. Ionizing radiation measured simultaneously at the INEEL boundary and distant locations using environmental dosimeters were similar and showed only background levels. The maximum potential population dose from submersion, ingestion, inhalation, and deposition to the approximately 121,500 people residing within an 80-km (50-mi) radius from the geographical center of the INEEL was estimated to be 0.08 person-rem (8 x 10-4 person-Sv) using the MDIFF air dispersion model. This population dose is less than 0.0002 percent of the estimated 43,7 00

Inconsistency... or why differentiate, where prevention is concerned, between radioactive substances and carcinogenic chemicals

International Nuclear Information System (INIS)

Choquet, R.; Vinit, J.

1982-01-01

Radiotracers, low-activity unsealed radioactive sources, and certain chemical products belong to the list of substances and agents known to promote cancers in humans. The dangers of radiotracers and carcinogenic chemicals being very similar, or even identical, it is inadmissible that preventive measures have not been equally developed and are not viewed in the same way in our country. It should be noted that the International Labour Bureau has long since included radioactive products in the list of carcinogenic substances and agents and treated preventive measures as a whole by proceeding in this way it would be easier to account for the possible combined effects of ionising radiations and chemical molecules. After a review of some facts about cancer the present situation is examined with regard to statutory measures applied on the one hand to radioelements and on the other to chemicals recognised as carcinogenic by international organisations. Proposals are made to remedy this illogical situation [fr

Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

International Nuclear Information System (INIS)

Harvego, Lisa

2009-01-01

The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory's recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy's ability to meet obligations with the State of Idaho

Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

Energy Technology Data Exchange (ETDEWEB)

Guenther, R J; Johnson, Jr, A B; Lund, A L; Gilbert, E R [and others

1996-07-01

The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

Energy Technology Data Exchange (ETDEWEB)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Regulatory controls on the hydrogeological characterization of a mixed waste disposal site, Radioactive Waste Management Complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Ruebelmann, K.L.

1990-01-01

Following the detection of chlorinated volatile organic compounds in the groundwater beneath the SDA in the summer of 1987, hydrogeological characterization of the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory (INEL) was required by the Resource Conservation and Recovery Act (RCRA). The waste site, the Subsurface Disposal Area (SDA), is the subject of a RCRA Corrective Action Program. Regulatory requirements for the Corrective Action Program dictate a phased approach to evaluation of the SDA. In the first phase of the program, the SDA is the subject of a RCRA Facility Investigation (RIF), which will obtain information to fully characterize the physical properties of the site, determine the nature and extent of contamination, and identify pathways for migration of contaminants. If the need for corrective measures is identified during the RIF, a Corrective Measures Study (CMS) will be performed as second phase. Information generated during the RIF will be used to aid in the selection and implementation of appropriate corrective measures to correct the release. Following the CMS, the final phase is the implementation of the selected corrective measures. 4 refs., 1 fig

Technology for the long-term management of defense HLW at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Staples, B.A.; Berreth, J.R.; Knecht, D.A.

1986-01-01

The Defense Waste Management Plan of June 1983 includes a reference plan for the long-term management of Idaho Chemical Processing Plant (ICPP) high-level waste (HLW), with a goal of disposing of the annual output in 500 canisters a year by FY-2008. Based on the current vitrification technology, the ICPP base-glass case would produce 1700 canisters per year after FY-2007. Thus, to meet the DWMP goal processing steps including fuel dissolution, waste treatment, and waste immobilization are being studied as areas where potential modifications could result in HLW volume reductions for repository disposal. It has been demonstrated that ICPP calcined wastes can be densified by hot isostatic pressing to multiphase ceramic forms of high loading and density. Conversion of waste by hot isostatic pressing to these forms has the potential of reducing the annual ICPP waste production to volumes near those of the goal of the DWMP. This report summarizes the laboratory-scale information currently available on the development of these forms

Bioprocessing of low-level radioactive and mixed hazard wastes

International Nuclear Information System (INIS)

Stoner, D.L.

1990-01-01

Biologically-based treatment technologies are currently being developed at the Idaho National Engineering Laboratory (INEL) to aid in volume reduction and/or reclassification of low-level radioactive and mixed hazardous wastes prior to processing for disposal. The approaches taken to treat low-level radioactive and mixed wastes will reflect the physical (e.g., liquid, solid, slurry) and chemical (inorganic and/or organic) nature of the waste material being processed. Bioprocessing utilizes the diverse metabolic and biochemical characteristics of microorganisms. The application of bioadsorption and bioflocculation to reduce the volume of low-level radioactive waste are strategies comparable to the use of ion-exchange resins and coagulants that are currently used in waste reduction processes. Mixed hazardous waste would require organic as well as radionuclide treatment processes. Biodegradation of organic wastes or bioemulsification could be used in conjunction with radioisotope bioadsorption methods to treat mixed hazardous radioactive wastes. The degradation of the organic constituents of mixed wastes can be considered an alternative to incineration, while the use of bioemulsification may simply be used as a means to separate inorganic and organics to enable reclassification of wastes. The proposed technology base for the biological treatment of low-level radioactive and mixed hazardous waste has been established. Biodegradation of a variety of organic compounds that are typically found in mixed hazardous wastes has been demonstrated, degradative pathways determined and the nutritional requirements of the microorganisms are understood. Accumulation, adsorption and concentration of heavy and transition metal species and transuranics by microorganisms is widely recognized. Work at the INEL focuses on the application of demonstrated microbial transformations to process development

Background concentrations of selected radionuclides, organic compounds, and chemical constituents in ground water in the vicinity of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Orr, B.R.; Cecil, L.D.; Knobel, L.L.

1991-01-01

Background concentrations of radionuclides, organic compounds, and other chemical constituents in water in the Snake River Plain aquifer in Idaho were estimated from groundwater sample analyses. Detectable concentrations of transuranic elements should not be present in water from the Snake River Plain aquifer. Background concentrations of tritium generally range from 75 to 150 pCi/L. Strontium-90 and iodine-129 concentrations generally are 0 and from 0.05 pCi/L, respectively. At the INEL, comparison of the mean and median concentrations of tritium, strontium-90, and iodine-129 indicates that operations locally have affected concentrations in groundwater. Gross alpha-particle and beta-particle radioactivity in water from the Snake River Plain aquifer ranges from 0 to 5 pCi/L and 0 to 8 pCi/L, respectively. Background gamma radiation in groundwater is attributed to cesium-137, cobalt-60, and potassium-40. Cesium-137 and cobalt-60 concentrations generally are zero in groundwater at the INEL. Naturally occurring concentrations of potassium-40 probably are about 300 pCi/L. Background concentrations of organic compounds in water from the Snake River Plain aquifer generally are less than 0.2 microg/L. Background arsenic and chromium concentrations both are about 2 to 3 microg/L. Barium concentrations are from about 50 to about 70 microg/L. Lead and mercury concentrations generally are less than 5 microg/L and 0.1 microg/L, respectively. Cadmium, selenium, and silver concentrations generally are less than 1 microg/L. Nitrate concentrations range from 0 to about 1.4 mg/L

Environmental surveillance report for the INEL radioactive waste management complex. Annual report, 1976

International Nuclear Information System (INIS)

Dolenc, M.R.; Janke, D.H.

1977-05-01

This report describes the environmental surveillance activities during 1976 at the two solid waste facilities of the Idaho National Engineering Laboratory. The monitoring program encompasses periodic and random sampling of air, water, and soil within and adjacent to the Radioactive Waste Management Complex and SL-1 Burial Ground. It was found that operation of the Radioactive Waste Management Complex and SL-1 during 1976 had little radiological impact on the environment and radioactivity levels were shown to be within appropriate guidelines for worker safety

Sequential chemical extraction for a phosphogypsum environmental impact evaluation

Science.gov (United States)

Gennari, R. F.; Garcia, I.; Medina, N. H.; Silveira, M. A. G.

2013-05-01

Phosphogypsum (PG) is gypsum generated during phosphoric acid production. PG is stocked in large stacks or accumulated in lakes; it contains heavy metals and naturally occurring radioactive elements. The metal contamination may affect the functionality, sustainability and biodiversity of ecosystems. In this work, PG samples were analyzed by Plasma Spectrometry. Total metal content and in the extractable fraction of chemical elements were determined. For K, Ni, Zn, Cr, Cd, Ba, Pb and U, the results obtained are lower than those obtained in a Idaho plant are including and also lower than those found in the soil, indicating this PG sample analyzed probably will not cause any additional metal neither natural radiation contamination.

Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego

2009-06-01

The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.

An update of hydrologic conditions and distribution of selected constituents in water, Snake River Plain aquifer, Idaho National Laboratory, Idaho, Emphasis 1999-2001

Science.gov (United States)

Davis, Linda C.

2006-01-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds, evaporation ponds, and disposal wells at the Idaho National Laboratory (INL) has affected water quality in the Snake River Plain aquifer underlying the INL. The U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, maintains ground-water monitoring networks at the INL to determine hydrologic trends, and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from wells in the USGS ground-water monitoring networks during 1999-2001. Water in the Snake River Plain aquifer moves principally through fractures and interflow zones in basalt, generally flows southwestward, and eventually discharges at springs along the Snake River. The aquifer is recharged principally from infiltration of irrigation water, infiltration of streamflow, ground-water inflow from adjoining mountain drainage basins, and infiltration of precipitation. Water levels in wells rose in the northern and west-central parts of the INL by 1 to 3 feet, and declined in the southwestern parts of the INL by up to 4 feet during 1999-2001. Detectable concentrations of radiochemical constituents in water samples from wells in the Snake River Plain aquifer at the INL generally decreased or remained constant during 1999-2001. Decreases in concentrations were attributed to decreased rates of radioactive-waste disposal, radioactive decay, changes in waste-disposal methods, and dilution from recharge. Tritium concentrations in water samples decreased as much as 8.3 picocuries per milliliter (pCi/mL) during 1999-2001, ranging from 0.43?0.14 to 13.6?0.6 pCi/mL in October 2001. Tritium concentrations in five wells near the Idaho Nuclear Technology and Engineering Center (INTEC) increased a few picocuries per milliliter from October 2000 to October 2001. Strontium-90 concentrations decreased or remained

Mockup testing of remote systems for zirconium fuel dissolution process at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Paige, D.M.

1979-01-01

A facility is being constructed at the Idaho National Engineering Laboratory for storage and dissolution of spent zirconium reactor fuels. The dissolution is carried out in chemical type equipment contained in a large shielded cell. The design provides for remote operations and maintenance as required. Equipment predicted to fail within 5 years is designed for remote maintenance. Each system was fabricated for mockup testing using readily available materials. The mockups were tested, redesigned, and retested until satisfactory remote designs were achieved. Records were made of all the work. All design changes were then incorporated into the ongoing detailed design for the actual equipment. Several of these systems are discussed and they include valve replacement, pump replacement, waste solids handling, mechanism operations and others. The mockup program has saved time and money by eliminating many future problems. In addition, the mockup program will continue through construction, cold startup, and hot operations

Vadose zone monitoring at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, 1985--1989

International Nuclear Information System (INIS)

McElroy, D.L.

1990-12-01

Vadose zone monitoring at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL) was implemented under the Subsurface Investigation Program Plan. The objective of the Subsurface Investigation Program was to characterize the subsurface at the RWMC in order to measure and predict radionuclide transport. Soil moisture sensors were installed to characterize the uniformity of water entry to the surficial sediments and moisture flux in the surficial sediments and the deeper stratigraphic units. From 1985 to 1987, a network of vadose zone instruments was installed in sediments at the RWMC. The instruments included psychrometers, gypsum blocks, heat-dissipation sensors (HDSs), tensiometers, lysimeters, and neutron access tubes. These instruments were placed at depths up to 230 ft below land surface (BLS) in a heterogeneous geologic system comprised of sediments that overlie and are intercalated with basalt flows. After organic contaminants were detected in the subsurface at the RWMC in 1988, the vadose zone monitoring project was incorporated into a broader characterization effort. This report presents the analyses of the vadose zone monitoring data collected from FY-1985 to FY-1989. The performance of the instruments are compared. Matric potential ranges and trends in the surficial sediments and interbeds are discussed. Hydraulic gradients are calculated to determine the direction of moisture movement. Using the neutron logging data in conjunction with the matric potential and hydraulic gradient data, infiltration is examined with respect to seasonal nature and source. 14 refs., 19 figs., 4 tabs

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; Brion Bennett

2011-09-01

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

International Nuclear Information System (INIS)

Harvego, Lisa; Bennett, Brion

2011-01-01

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Water information bulletin No. 30 geothermal investigations in Idaho

Energy Technology Data Exchange (ETDEWEB)

Mitchell, J.C.; Johnson, L.L.; Anderson, J.E.; Spencer, S.G.; Sullivan, J.F.

1980-06-01

There are 899 thermal water occurrences known in Idaho, including 258 springs and 641 wells having temperatures ranging from 20 to 93/sup 0/C. Fifty-one cities or towns in Idaho containing 30% of the state's population are within 5 km of known geothermal springs or wells. These include several of Idaho's major cities such as Lewiston, Caldwell, Nampa, Boise, Twin Falls, Pocatello, and Idaho Falls. Fourteen sites appear to have subsurface temperatures of 140/sup 0/C or higher according to the several chemical geothermometers applied to thermal water discharges. These include Weiser, Big Creek, White Licks, Vulcan, Roystone, Bonneville, Crane Creek, Cove Creek, Indian Creek, and Deer Creek hot springs, and Raft River, Preston, and Magic Reservoir areas. These sites could be industrial sites, but several are in remote areas away from major transportation and, therefore, would probably be best utilized for electrical power generation using the binary cycle or Magma Max process. Present uses range from space heating to power generation. Six areas are known where commercial greenhouse operations are conducted for growing cut and potted flowers and vegetables. Space heating is substantial in only two places (Boise and Ketchum) although numerous individuals scattered throughout the state make use of thermal water for space heating and private swimming facilities. There are 22 operating resorts using thermal water and two commercial warm-water fish-rearing operations.

Guidelines for generators of hazardous chemical waste at LBL and Guidelines for generators of radioactive and mixed waste at LBL

International Nuclear Information System (INIS)

1991-07-01

The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical, radioactive, and mixed waste to Lawrence Berkeley Laboratory's (LBL) Hazardous Waste Handling Facility (HWHF). These guidelines describe how a generator of wastes can meet LBL's acceptance criteria for hazardous chemical, radioactive, and mixed waste. 9 figs

Aerial gamma ray and magnetic survey: Idaho Project, Idaho Falls quadrangle, Idaho. Final report

International Nuclear Information System (INIS)

1979-10-01

The Idaho Falls quadrangle in southeastern Idaho lies at the juncture of the Snake River Plain, the Northern Rocky Mountains, and the Basin-Range Province. Quaternary basalts of the Snake River Plain occupy 70% of the quadrangle. The rest of the area is covered by uplifted Paleozoic, Mesozoic, and Cenozoic rocks of the Pre-Late Cenozoic Orogenic Complex. Magnetic data apparently show contributions from both shallow and deep sources. The apparent expression of intrusive and extrusive rocks of late Mesozoic and Cenozoic age tends to mask the underlying structural downtrap thought to exist under the Snake River Plain. The Idaho Falls quadrangle has been unproductive in terms of uranium mining. A single claim exists in the Sawtooth Mountains, but no information was found concerning its present status at the time of this study. A total of 169 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle, though one large group appears to relate to unnatural radiation sources in the Reactor Test Site area. The most distinctive anomalies occur in the Permian Phosphoria Formation and the Starlight Volcanics in the Port Neuf Mountains

Polonium-210 in the environment around a radioactive waste disposal area and phosphate ore processing plant

Energy Technology Data Exchange (ETDEWEB)

Arthur, III, W J; Markham, O D

1984-04-01

Polonium-210 concentrations were determined for soil, vegetation and small mammal tissues collected at a solid radioactive waste disposal area, near a phosphate ore processing plant and at two rural areas in southeastern Idaho. Polonium concentrations in media sampled near the radioactive waste disposal facility were equal to or less than values from rural area samples, indicating that disposal of solid radioactive waste at the Idaho National Engineering Laboratory Site has not resulted in increased environmental levels of polonium. Concentrations of /sup 210/Po in soils, deer mice hide and carcass samples collected near the phosphate processing plant were statistically greater than the other sampling locations; however, the mean /sup 210/Po concentration in soils and small mammal tissues from sampling areas near the phosphate plant were only four and three times greater, respectively, than control values. No statistical difference was observed for /sup 210/Po concentrations in vegetation among any of the sampling locations.

Analysis of determination modalities concerning the exposure and emission limits values of chemical and radioactive substances

International Nuclear Information System (INIS)

Schieber, C.; Schneider, T.

2002-08-01

This document presents the generic approach adopted by various organizations for the determination of the public exposure limits values to chemical and radioactive substances and for the determination of limits values of chemical products emissions by some installations. (A.L.B.)

First use of in situ vitrification on radioactive wastes

International Nuclear Information System (INIS)

Bowlds, L.

1992-01-01

A high-temperature method for containing hazardous wastes, which was first developed in the 1980s, is being adapted for the in situ treatment of buried radioactive wastes by the US DOE's Idaho National Engineering Laboratory (INEL), following its recent report on successful preliminary tests. The method, called in situ vitrification (ISV), is an electrically induced thermal process that melts and fuses soil and wastes into a glass-like material at least as strong as natural obsidian or granite. Gases released during the process are captured and treated by an off-gas treatment system. After the wastes are vitrified, they could be left in place, or the mass could be broken up and transported to a disposal site. The glass-like substance would be chemically and physically similar to obsidian and from 4 to 10 times more durable than typical borosilicate glasses used to immobolize high-level nuclear wastes

Applicability of a generic monitoring program for radioactive waste burial grounds at Oak Ridge National Laboratory and Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1978-07-01

Six burial grounds were evaluated at Oak Ridge to determine which would be most suitable for testing the generic monitoring approach, and two were selected. Burial Ground 4 was chosen because it is known to be leaking radioactivity and a monitoring program is desirable to determine the source, pattern and extent of the leakage. Burial Ground 6 was chosen because the most complete radiologic and geologic data is available and modern burial practices have been utilized at this site. At the Idaho National Engineering Laboratory (INEL) only one burial ground exists, the Radioactive Waste Management Complex (RWMC). The data available on the burial grounds are insufficient for an adequate understanding of radionuclide migration patterns and accordingly, inadequate for the design of reliable monitoring programs. It was decided, therefore, that preliminary monitoring programs should be designed in order to obtain additional data for a later implementation of reliable monitoring programs. The monitoring programs designed for ORNL consist primarily of the installation of surface water monitoring stations, the surveillance of trench sump wells, a test boring program to study subsurface geologic conditions, a ground water sampling program and the installation of instrumentation, specifically infiltrometers and evaporation pans, to develop data on site water balances. The program designed for the INEL burial ground includes installation of trench sumps, a ground water monitoring program, test borings to further define subsurface geohydrologic conditions and the installation of instrumentation to develop data on the site water balance. The estimated costs of implementing the recommended programs are about $420,820 for monitoring Burial Grounds 4 and 6 at Oak Ridge and $382,060 for monitoring the RWMC at INEL. 12 figures

Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

International Nuclear Information System (INIS)

1997-01-01

This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

International Nuclear Information System (INIS)

2011-01-01

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Idaho National Engineering Laboratory response to the December 13, 1991, Congressional inquiry on offsite release of hazardous and solid waste containing radioactive materials from Department of Energy facilities

International Nuclear Information System (INIS)

Shapiro, C.; Garcia, K.M.; McMurtrey, C.D.; Williams, K.L.; Jordan, P.J.

1992-05-01

This report is a response to the December 13, 1991, Congressional inquiry that requested information on all hazardous and solid waste containing radioactive materials sent from Department of Energy facilities to offsite facilities for treatment or disposal since January 1, 1981. This response is for the Idaho National Engineering Laboratory. Other Department of Energy laboratories are preparing responses for their respective operations. The request includes ten questions, which the report divides into three parts, each responding to a related group of questions. Part 1 answers Questions 5, 6, and 7, which call for a description of Department of Energy and contractor documentation governing the release of waste containing radioactive materials to offsite facilities. ''Offsite'' is defined as non-Department of Energy and non-Department of Defense facilities, such as commercial facilities. Also requested is a description of the review process for relevant release criteria and a list of afl Department of Energy and contractor documents concerning release criteria as of January 1, 1981. Part 2 answers Questions 4, 8, and 9, which call for information about actual releases of waste containing radioactive materials to offsite facilities from 1981 to the present, including radiation levels and pertinent documentation. Part 3 answers Question 10, which requests a description of the process for selecting offsite facilities for treatment or disposal of waste from Department of Energy facilities. In accordance with instructions from the Department of Energy, the report does not address Questions 1, 2, and 3

The Idaho National Engineering Laboratory Site environmental report for calendar year 1988

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Moore, R.

1989-06-01

This report describes the monitoring program, the collection of foodstuffs at the Idaho National Engineering Laboratory (INEL) boundary and distant offsite locations, and the collection of air and water samples at Site locations and offsite boundary and distant locations. The report also compares and evaluates the samples results, discussing implications, if any. Significant environmental activities at the INEL Site during 1988, nonradioactive and radioactive effluent monitoring at the Site, and the US Geological Survey (USGS) ground-water monitoring program are also summarized. 42 refs., 15 figs., 12 tabs

Radioactive Tank Waste Remediation Focus Area. Technology summary

International Nuclear Information System (INIS)

1995-06-01

In February 1991, DOE's Office of Technology Development created the Underground Storage Tank Integrated Demonstration (UST-ID), to develop technologies for tank remediation. Tank remediation across the DOE Complex has been driven by Federal Facility Compliance Agreements with individual sites. In 1994, the DOE Office of Environmental Management created the High Level Waste Tank Remediation Focus Area (TFA; of which UST-ID is now a part) to better integrate and coordinate tank waste remediation technology development efforts. The mission of both organizations is the same: to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. The TFA has focused on four DOE locations: the Hanford Site in Richland, Washington, the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho, the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site (SRS) in Aiken, South Carolina

Events of radioactive waste management - a chronological table

International Nuclear Information System (INIS)

1985-01-01

In chronological order the leaflet abstracted points out the essential data of German radioactive waste management. The data reach from December 1951 with EBR I (Idaho/USA) being the first one to feed electric power to the distribution grid to February 1985 known as the date of the submission of building applications for the first partial license of the Wackersdorf reprocessing plant. (HSCH) [de

Management of low and intermediate level radioactive wastes with regard to their chemical toxicity

International Nuclear Information System (INIS)

2002-12-01

A preliminary overview is provided of management options for low and intermediate level radioactive waste (LILW) with regard to its chemical toxicity. In particular, the following issues are identified and described associated with the management and safe disposal of chemically toxic materials in LILW: the origin and characteristics; the regulatory approaches; the pre-disposal management; the disposal; the safety assessment. Also included are: regulatory framework for chemically toxic low level wastes in the USA; pre-disposal processing options for LILW containing chemically toxic components; example treatment technologies for LILW containing chemically toxic components and safety assessment case studies for Germany, Belgium, France and Sweden

Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

Energy Technology Data Exchange (ETDEWEB)

Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

1998-05-01

Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility`s processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory.

Idaho Nuclear Technology and Engineering Center (INTEC) (formerly ICPP) ash reutilization study

International Nuclear Information System (INIS)

Langenwalter, T.; Pettet, M.; Ochoa, R.; Jensen, S.

1998-05-01

Since 1984, the coal-fired plant at the Idaho Nuclear Technology and Engineering Center (INTEC, formerly Idaho Chemical Processing Plant) has been generating fly ash at a rate of approximately 1,000 tons per year. This ash is hydrated and placed in an ash bury pit near the coal-fired plant. The existing ash bury pit will be full in less than 1 year at its present rate of use. A conceptual design to build a new ash bury pit was completed, and the new pit is estimated to cost $1.7 million. This report evaluates ash reutilization alternatives that propose to eliminate this waste stream and save the $1.7 million required to build a new pit. The alternatives include using ash for landfill day cover, concrete admixture, flowable fill, soil stabilization, waste remediation, and carbon recovery technology. Both physical and chemical testing, under the guidance of the American Society for Testing and Materials, have been performed on ash from the existing pit and from different steps within the facility's processes. The test results have been evaluated, compared to commercial ash, and are discussed as they relate to reutilization alternatives. This study recommends that the ash be used in flowable fill concrete for Deactivation and Demolition work at the Idaho National Engineering and Environmental Laboratory

Effect of chemical structure on the radioactive decay rate of 71Ge

International Nuclear Information System (INIS)

Makariunas, K.; Makariuniene, E.; Dragunas, A.

1979-01-01

The influence of the chemical structure on the electron capture radioactive decay rate of 71 Ge was observed. 71 Ge nuclei in bivalent sulphide GeS decay faster than in quadrivalent sulphide GeS 2 . The relative change Δlambda/lambda of the decay constant lambda is + (11.4 +- 1.7) X 10 -4 . A possibility to use the experimental values of Δlambda/lambda to determine the chemical changes in the electron density at germanium nuclei in germanium chemical compounds is discussed. Quantitative determination of the changes in the electron density is complicated because of insufficient reliability of the published values of exchange and overlap corrections to the electron capture probabilities. (Auth.)

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen. Kurzanleitung fuer die CBRN-Probenahme

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid (and others)

2010-07-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Thermal treatment technology at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hillary, J.M.

1994-01-01

Recent surveys of mixed wastes in interim storage throughout the 30-site Department of Energy complex indicate that only 12 of those sites account for 98% of such wastes by volume. Current inventories at the Idaho National Engineering Laboratory (INEL) account for 38% of total DOE wastes in interim storage, the largest of any single site. For a large percentage of these waste volumes, as well as the substantial amounts of buried and currently generated wastes, thermal treatment processes have been designated as the technologies of choice. Current facilities and a number of proposed strategies exist for thermal treatment of wastes of this nature at the INEL. High-level radioactive waste is solidified in the Waste Calciner Facility at the Idaho Central Processing Plant. Low-level solid wastes until recently have been processed at the Waste Experimental Reduction Facility (WERF), a compaction, size reduction, and controlled air incineration facility. WERF is currently undergoing process upgrading and RCRA Part B permitting. Recent systems studies have defined effective strategies, in the form of thermal process sequences, for treatment of wastes of the complex and heterogeneous nature in the INEL inventory. This presentation reviews the current status of operating facilities, active studies in this area, and proposed strategies for thermal treatment of INEL wastes

78 FR 68466 - BLM Director's Response to the Idaho Governor's Appeal of the BLM Idaho State Director's Governor...

Science.gov (United States)

2013-11-14

... Bureau of Land Management (BLM) is publishing this notice to explain why the BLM Director is denying the...] BLM Director's Response to the Idaho Governor's Appeal of the BLM Idaho State Director's Governor's... (Finding) to the BLM Idaho State Director (State Director). The State Director determined the Governor's...

The Idaho National Engineering Laboratory Site Environmental Report for Calendar Year 1993

International Nuclear Information System (INIS)

Mitchell, R.G.

1994-07-01

Results of the various environmental monitoring programs for 1993 are presented from the Idaho National Engineering Laboratory (INEL) operations. Although some radioactive materials were discharged during Site operations, concentrations and doses to the surrounding population were of no health consequence and were far less than State of Idaho and Federal health protection guidelines. Chapter 2 summarizes INEL activities related to compliance with environmental regulations and laws for Calendar Year 1993. The major portion of the report summarizes results of the environmental surveillance program conducted by the DOE Radiological and Environmental Sciences Laboratory, which includes the collection of foodstuffs at the INEL boundary and distant offsite locations, and the collection of air and water samples at onsite locations and offsite boundary and distant locations. The report also compares and evaluates the sample results to appropriate federal regulations and standards and discusses implications, if any. The US Geological Survey (USGS) ground-water monitoring program is briefly summarized and data are included in maps showing the spread of contaminants. Effluent monitoring and nonradiological drinking water monitoring are discussed briefly and data are summarized

Layered packaging: A synergistic method of transporting radioactive material

International Nuclear Information System (INIS)

Hohmann, G.L.

1989-01-01

The DOE certification for a transportation cask used to ship radioactive Krypton 85 from the Idaho Chemical Processing Plant (ICPP) to Oak Ridge National Laboratory (ORNL), was allowed to expire in 1987. The Westinghouse Idaho Nuclear Company (WINCO) was charged by DOE with modifying this cask to meet all current NRC requirements and preparing an updated Safety Analysis Report for Packaging, which would be submitted by DOE to the NRC for certification. However, an urgent need arose for ORNL to receive Krypton 85 which was in storage at the ICPP, which would not allow time to obtain certification of the modified shipping cask. WINCO elected to use a layered shipping configuration in which the gaseous Krypton 85 was placed in the uncertified, modified shipping cask to make use of its shielding and thermal insulation properties. This cask was then inserted into the Model No. 6400 (Super Tiger) packaging using a specially constructed plywood box and polyurethane foam dunnage. Structural evaluations were completed to assure the Super Tiger would provide the necessary impact, puncture, and thermal protection during maximum credible accidents. Analyses were also completed to determine the uncertified Krypton shipping cask would provide the necessary containment and shielding for up to 3.7 E+14 Bq of Krypton 85 when packaged inside the Super Tiger. The resulting reports, based upon this layered packaging concept, were adequate to first obtain DOE certification for several restricted shipments of Krypton 85 and then NRC certification for unrestricted shipments

In summary: Idaho National Engineering and Environmental Laboratory site environmental report for calendar year 1997

International Nuclear Information System (INIS)

Mitchell, R.G.; Roush, D.E. Jr.; Evans, R.B.

1998-10-01

Every human is exposed to natural radiation. This exposure comes from many sources, including cosmic radiation from outer space, naturally-occurring radon, and radioactivity from substances in the body. In addition to natural sources of radiation, humans can also be exposed to human-generated sources of radiation. Some examples of these sources include nuclear medicine, X-rays, nuclear weapons testing, and accidents at nuclear power plants. The Idaho National Engineering and Environmental Laboratory (INEEL) is a US Department of Energy (DOE) research facility that deals, in part, with studying nuclear reactors and the storage and cleanup of radioactive materials. Careful handling and rigorous procedures do not completely eliminate the risk of releasing radioactivity. So, there is a possibility for a member of the public near the INEEL to be exposed to radioactivity from the INEEL. Extensive monitoring of the environment takes place one and around the INEEL. These programs search for radionuclides and other contaminants. The results of these programs are presented each year in a site environmental report. This document summarizes the INEEL site environmental report for 1997

Test Plan for Lockheed Idaho Technologies Company (LITCO), ARROW-PAK Packaging, Docket 95-40-7A, Type A Container

International Nuclear Information System (INIS)

Kelly, D.L.

1995-01-01

This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance testing to be followed for qualification of the Lockheed Idaho Technologies Company, ARROW-PAK, for use as a Type A Packaging. The packaging configuration being tested is intended for transportation of radioactive solids, Form No. 1, Form No. 2, and Form No. 3

Study about the integrated treatment of chemical and radioactive effluents, introducing the zero release concept

International Nuclear Information System (INIS)

Mierzwa, Jose Carlos

1996-01-01

An Integrated System to the treatment of Chemical and Radioactive Effluents to the Centro Experimental Aramar is proposed and evaluated, introducing the Effluent Zero Release concept, where factors related to the environmental regulation in vigor in the country, as well as the availability of hydrological resources in the place where CEA have been implanted, are considered. Through a literature analysis of the main effluents treatment techniques available nowadays and after a case of study selection, take into account two industrial installations that will be implanted at CEA, it was defined an arrangement to compose the Integrated System to the Treatment of Chemicals and Radioactive Effluents, focusing the Zero Release concept consolidation. A defined arrangement uses a combination among three treatment processes, it means chemical precipitation, reverse osmosis and evaporation, that were experimentally evaluated. The proposed arrangement was evaluated using synthetic effluents, that were prepared based on data from literature and conception documents of the installation considered in this work. Three kinds of effluents were simulated, one arising from a nuclear reactor laundry, one arising from the water refrigeration system and demineralized water production to the nuclear reactor and the other one arising from a nuclear material production laboratory. Each effluent were individually submitted to the selected treatment processes, to get the best operational conditions for each treatment process. The results got during the laboratory assays show that the proposed Integrated System to the Treatment of Chemicals and Radioactive Effluents is feasible, consolidating the Effluent Zero Release concept, which is the proposition of this work. (author)

Experience base for Radioactive Waste Thermal Processing Systems: A preliminary survey

International Nuclear Information System (INIS)

Mayberry, J.; Geimer, R.; Gillins, R.; Steverson, E.M.; Dalton, D.; Anderson, G.L.

1992-04-01

In the process of considering thermal technologies for potential treatment of the Idaho National Engineering Laboratory mixed transuranic contaminated wastes, a preliminary survey of the experience base available from Radioactive Waste Thermal Processing Systems is reported. A list of known commercial radioactive waste facilities in the United States and some international thermal treatment facilities are provided. Survey focus is upon the US Department of Energy thermal treatment facilities. A brief facility description and a preliminary summary of facility status, and problems experienced is provided for a selected subset of the DOE facilities

Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

International Nuclear Information System (INIS)

Horvath, J.; Dugovic, L.

1999-01-01

Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

Study of chemically synthesized ZnO nano particles under a bio template using radioactive ion beam

CERN Multimedia

This is a project proposal to study nano sized semiconductor ZnO system, useful in biology and medicinal purposes, using radioactive ion beam from ISOLDE. Doping of the nano particles with Cu, Cd and Ga ions (in their variable valancy states) are expected to impart changes in the electrical structure and properties in the said system under study. The morphological changes, chemical environment, micro structure, electrical and optical properties of the nano size particles of ZnO system (developed under a bio template of folic acid) after the interaction with radioactive ion beam will be studied. The provision of perturbed angular correlation (PAC) study with respect to the changes in chemical environment, where ever possible will be attempted.

Radioactive particles revealed by electron microscopy. Chemical and physical properties of radioactive particles in aerosol samples emitted during the early stage of Fukushima Dai-ichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Adachi, Kouji

2015-01-01

Water-insoluble radioactive materials emitted during an early stage of the Fukushima Dai-ichi Nuclear Power Plant accident in 2011 were identified, and their chemical and physical properties were characterized as particulate matters. In this report, studies on radioactive particles collected from filter samples in Tsukuba on March 14–15, 2011 are summarized. Their compositions, chemical states, sizes, shapes, crystallinity, and hygroscopicity were analyzed using microscopic analyses such as electron microscopy and synchrotron with a micro-beam. The results indicate that they include Cs, Fe, and Zn as well as elements from fission products and are water insoluble, spherical-glassy particles with ca. 2 micrometer in size. Understanding of their detailed properties is significant to improve the numerical models during the accident and to understand their occurrences in soil as well as the accident itself. In addition to the water-insoluble radioactive materials, water-soluble radioactive materials, which were likely emitted in different events during the accident, should be investigated to have comprehensive understanding of the accident and its environmental effects. More samples from various environments such as soil will be needed, and more detailed chemical and physical analyses will help to understand their formation process, influences on human health, and long term decrements in ambient conditions. (author)

Idaho Chemical Processing Plant low-level waste grout stabilization development program FY-96 status report

International Nuclear Information System (INIS)

Herbst, A.K.

1996-09-01

The general purpose of the Grout Stabilization Development Program is to solidify and stabilize the liquid low-level wastes (LLW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LLW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste; (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines; (3) facility decontamination processes; and (4) process equipment waste. The main tasks completed this fiscal year as part of the program were chromium stabilization study for sodium-bearing waste and stabilization and solidification of LLW from aluminum and zirconium calcines. The projected LLW will be highly acidic and contain high amounts of nitrates. Both of these are detrimental to Portland cement chemistry; thus, methods to precondition the LLW and to cure the grout were explored. A thermal calcination process, called denitration, was developed to solidify the waste and destroy the nitrates. A three-way blend of Portland cement, blast furnace slag, and fly ash was successfully tested. Grout cubes were prepared at various waste loadings to maximize loading while meeting compressive strength and leach resistance requirements. For the sodium LLW, a 25% waste loading achieves a volume reduction of 3.5 and a compressive strength of 2,500 pounds per square inch while meeting leach, mix, and flow requirements. It was found that the sulfur in the slag reduces the chromium leach rate below regulatory limits. For the aluminum LLW, a 15% waste loading achieves a volume reduction of 8.5 and a compressive strength of 4,350 pounds per square inch while meeting leach requirements. Likewise for zirconium LLW, a 30% waste loading achieves a volume reduction of 8.3 and a compressive strength of 3,570 pounds per square inch

Boise State's Idaho Eclipse Outreach Program

Science.gov (United States)

Davis, Karan; Jackson, Brian

2017-10-01

The 2017 total solar eclipse is an unprecedented opportunity for astronomical education throughout the continental United States. With the path of totality passing through 14 states, from Oregon to South Carolina, the United States is expecting visitors from all around the world. Due to the likelihood of clear skies, Idaho was a popular destination for eclipse-chasers. In spite of considerable enthusiasm and interest by the general population, the resources for STEM outreach in the rural Pacific Northwest are very limited. In order to help prepare Idaho for the eclipse, we put together a crowdfunding campaign through the university and raised over $10,000. Donors received eclipse shades as well as information about the eclipse specific to Idaho. Idaho expects 500,000 visitors, which could present a problem for the many small, rural towns scattered across the path of totality. In order to help prepare and equip the public for the solar eclipse, we conducted a series of site visits to towns in and near the path of totality throughout Idaho. To maximize the impact of this effort, the program included several partnerships with local educational and community organizations and a focus on the sizable refugee and low-income populations in Idaho, with considerable attendance at most events.

1986 environmental monitoring program report for the Idaho National Engineering Laboratory Site

International Nuclear Information System (INIS)

Hoff, D.L.; Chew, E.W.; Rope, S.K.

1987-05-01

This report presents onsite and offsite data collected in 1986 for the routine environmental monitoring program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL) Site. The purpose of this routine program is to monitor radioactive and nonradioactive materials resulting from INEL Site operations which may reach the surrounding offsite environment and population. This report is prepared in accordance with the DOE requirements in draft DOE Order 5484.1 and is not intended to cover the numerous special environmental research programs being conducted at the INEL by RESL and others

Idaho radionuclide exposure study: Literature review

International Nuclear Information System (INIS)

Baker, E.G.; Freeman, H.D.; Hartley, J.N.

1987-10-01

Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily 210 Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report

Radioactive liquid waste processing system

International Nuclear Information System (INIS)

Noda, Tetsuya; Kuramitsu, Kiminori; Ishii, Tomoharu.

1997-01-01

The present invention provides a system for processing radioactive liquid wastes containing laundry liquid wastes, shower drains or radioactive liquid wastes containing chemical oxygen demand (COD) ingredients and oil content generated from a nuclear power plant. Namely, a collecting tank collects radioactive liquid wastes. A filtering device is connected to the exit of the collective tank. A sump tank is connected to the exit of the filtering device. A powdery active carbon supplying device is connected to the collecting tank. A chemical fluid tank is connected to the collecting tank and the filtering device by way of chemical fluid injection lines. Backwarding pipelines connect a filtered water flowing exit of the filtering device and the collecting tank. The chemical solution is stored in the chemical solution tank. Then, radioactive materials in radioactive liquid wastes generated from a nuclear power plant are removed by the filtering device. The water quality standard specified in environmental influence reports can be satisfied. In the filtering device, when the filtering flow rate is reduced, the chemical fluid is supplied from the chemical fluid tank to the filtering device to recover the filtering flow rate. (I.S.)

Correlation between basalt flows and radiochemical and chemical constituents in selected wells in the southwestern part of the Idaho National Laboratory, Idaho

Science.gov (United States)

Bartholomay, Roy C.; Hodges, Mary K. V.; Champion, Duane E.

2017-12-21

Wastewater discharged to wells and ponds and wastes buried in shallow pits and trenches at facilities at the Idaho National Laboratory (INL) have contributed contaminants to the eastern Snake River Plain (ESRP) aquifer in the southwestern part of the INL. This report describes the correlation between subsurface stratigraphy in the southwestern part of the INL with information on the presence or absence of wastewater constituents to better understand how flow pathways in the aquifer control the movement of wastewater discharged at INL facilities. Paleomagnetic inclination was used to identify subsurface basalt flows based on similar inclination measurements, polarity, and stratigraphic position. Tritium concentrations, along with other chemical information for wells where tritium concentrations were lacking, were used as an indicator of which wells were influenced by wastewater disposal.The basalt lava flows in the upper 150 feet of the ESRP aquifer where wastewater was discharged at the Idaho Nuclear Technology and Engineering Center (INTEC) consisted of the Central Facilities Area (CFA) Buried Vent flow and the AEC Butte flow. At the Advanced Test Reactor (ATR) Complex, where wastewater would presumably pond on the surface of the water table, the CFA Buried Vent flow probably occurs as the primary stratigraphic unit present; however, AEC Butte flow also could be present at some of the locations. At the Radioactive Waste Management Complex (RWMC), where contamination from buried wastes would presumably move down through the unsaturated zone and pond on the surface of the water table, the CFA Buried Vent; Late Basal Brunhes; or Early Basal Brunhes basalt flows are the flow unit at or near the water table in different cores.In the wells closer to where wastewater disposal occurred at INTEC and the ATR-Complex, almost all the wells show wastewater influence in the upper part of the ESRP aquifer and wastewater is present in both the CFA Buried Vent flow and AEC Butte

The results of an ecological risk assessment screening at the Idaho National Engineering's waste area group 2

International Nuclear Information System (INIS)

VanHorn, R.

1995-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA)

Idaho | Midmarket Solar Policies in the United States | Solar Research |

Science.gov (United States)

% interest for solar PV projects. Low-interest financing Idaho Energy Resources Authority Solar PV project for financing through the Idaho Governor's Office and the Idaho Energy Resources Authority. Latest -owned community solar project for Idaho Power. Net Metering Idaho does not have statewide net metering

Radioactivity in fossils at the Hagerman Fossil Beds National Monument.

Science.gov (United States)

Farmer, C Neal; Kathren, Ronald L; Christensen, Craig

2008-08-01

Since 1996, higher than background levels of naturally occurring radioactivity have been documented in both fossil and mineral deposits at Hagerman Fossil Beds National Monument in south-central Idaho. Radioactive fossil sites occur primarily within an elevation zone of 900-1000 m above sea level and are most commonly found associated with ancient river channels filled with sand. Fossils found in clay rich deposits do not exhibit discernable levels of radioactivity. Out of 300 randomly selected fossils, approximately three-fourths exhibit detectable levels of natural radioactivity ranging from 1 to 2 orders of magnitude above ambient background levels when surveyed with a portable hand held Geiger-Muller survey instrument. Mineral deposits in geologic strata also show above ambient background levels of radioactivity. Radiochemical lab analysis has documented the presence of numerous natural radioactive isotopes. It is postulated that ancient groundwater transported radioactive elements through sand bodies containing fossils which precipitated out of solution during the fossilization process. The elevated levels of natural radioactivity in fossils may require special precautions to ensure that exposures to personnel from stored or displayed items are kept as low as reasonably achievable (ALARA).

Chemical durability of soda-lime-aluminosilicate glass for radioactive waste vitrification

International Nuclear Information System (INIS)

Eppler, F.H.; Yim, M.S.

1998-01-01

Vitrification has been identified as one of the most viable waste treatment alternatives for nuclear waste disposal. Currently, the most popular glass compositions being selected for vitrification are the borosilicate family of glasses. Another popular type that has been around in glass industry is the soda-lime-silicate variety, which has often been characterized as the least durable and a poor candidate for radioactive waste vitrification. By replacing the boron constituent with a cheaper substitute, such as silica, the cost of vitrification processing can be reduced. At the same time, addition of network intermediates such as Al 2 O 3 to the glass composition increases the environmental durability of the glass. The objective of this study is to examine the ability of the soda-lime-aluminosilicate glass as an alternative vitrification tool for the disposal of radioactive waste and to investigate the sensitivity of product chemical durability to variations in composition

Economic Cost of Crashes in Idaho

Science.gov (United States)

2016-06-01

The Idaho Transportation Departments Office of Highway Safety contracted with Cambridge Systematics (CS) for an assessment of the feasibility of calculating the Idaho-specific economic and comprehensive costs associated with vehicle crashes. Resea...

Test and evaluation of radioactively contaminated transducers and transmitters

International Nuclear Information System (INIS)

Strahm, R.C.

1983-01-01

People in the nuclear industries face some unique problems when handling, testing, or examining transducers and transmitters that have been radioactively contaminated. Although many people and organizations, including EG and G Idaho, have performed such work for many years, there are no set, structured approaches or procedures. This paper discusses a disciplined laboratory approach to contaminated transducer testing and evaluation, utilizing equipment and facilities developed specifically for this type of work

Regional groundwater chemical characteristics of Aqishan pre-selected site for high level radioactive waste repository and its hydrogeological significance

International Nuclear Information System (INIS)

Guo Yonghai; Dong Jiannan; Liu Shufen; Zhou Zhichao

2014-01-01

Aqishan area located in Xinjiang Uygur Automonous Region is one of the main preselected site of disposal repository for high-level radioactive waste (HLW) in our country. Groundwater chemical feature is one of the most important consideration factors in the siting and site evaluation for high-level radioactive waste repository, From 2012 to 2013, the regional field hydrogeochemical investigation was carried out in study area and more than 30 groundwater samples were collected. According to the measurement data, the groundwater chemical features for different subareas are discussed in the paper. Furthermore, the location of discharge area of groundwater in Aqishan area was estimated according to the chemical features of different subareas. (authors)

1997 Idaho National Engineering and Environmental Laboratory (INEEL) National Emission Standard for Hazardous Air Pollutants - Radionuclides. Annual report

International Nuclear Information System (INIS)

1998-06-01

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities, each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1997. Section 1 of this report provides an overview of the INEEL facilities and a brief description of the radioactive materials and processes at the facilities. Section 2 identifies radioactive air effluent release points and diffuse sources at the INEEL and actual releases during 1997. Section 2 also describes the effluent control systems for each potential release point. Section 3 provides the methodology and EDE calculations for 1997 INEEL radioactive emissions

The physical and chemical environment and radionuclide migration in a low level radioactive waste repository

International Nuclear Information System (INIS)

Torok, J.; Buckley, L.P.

1988-01-01

The expected physical and chemical environment within the low-level radioactive waste repository to be sited at Chalk River is being studied to establish the rate of radionuclide migration. Chemical conditions in the repository are being assessed for their effect on buffer performance and the degradiation of the concrete structure. Experimental programs include the effect of changes in solution chemistry on radionuclide distribution between buffer/backfill materials and the aqueous phase; the chemical stability of the buffer materials and the determination of the controlling mechanism for radionuclide transport during infiltration

General-purpose chemical analyzer for on-line analyses of radioactive solutions

International Nuclear Information System (INIS)

Spencer, W.A.; Kronberg, J.W.

1983-01-01

An automated analyzer is being developed to perform analytical measurements on radioactive solutions on-line in a hostile environment. This General Purpose Chemical Analyzer (GPCA) samples a process stream, adds reagents, measures solution absorbances or electrode potentials, and automatically calculates the results. The use of modular components, under microprocessor control, permits a single analyzer design to carry out many types of analyses. This paper discusses the more important design criteria for the GPCA, and describes the equipment being tested in a prototype unit

78 FR 23522 - Idaho Roadless Rule

Science.gov (United States)

2013-04-19

... occur in T47N, R6E, sections 29, 31, and 32, Boise Meridian and were part of the Lucky Swede Land... List of designated Idaho Roadless Areas. * * * * * Forest Idaho roadless area Number WLR Primitive BCR...

The development of radioactive sample surrogates for training and exercises

Energy Technology Data Exchange (ETDEWEB)

Martha Finck; Bevin Brush; Dick Jansen; David Chamberlain; Don Dry; George Brooks; Margaret Goldberg

2012-03-01

The development of radioactive sample surrogates for training and exercises Source term information is required for to reconstruct a device used in a dispersed radiological dispersal device. Simulating a radioactive environment to train and exercise sampling and sample characterization methods with suitable sample materials is a continued challenge. The Idaho National Laboratory has developed and permitted a Radioactive Response Training Range (RRTR), an 800 acre test range that is approved for open air dispersal of activated KBr, for training first responders in the entry and exit from radioactively contaminated areas, and testing protocols for environmental sampling and field characterization. Members from the Department of Defense, Law Enforcement, and the Department of Energy participated in the first contamination exercise that was conducted at the RRTR in the July 2011. The range was contaminated using a short lived radioactive Br-82 isotope (activated KBr). Soil samples contaminated with KBr (dispersed as a solution) and glass particles containing activated potassium bromide that emulated dispersed radioactive materials (such as ceramic-based sealed source materials) were collected to assess environmental sampling and characterization techniques. This presentation summarizes the performance of a radioactive materials surrogate for use as a training aide for nuclear forensics.

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Bryant, J.W.; Nenni, J.A.

2003-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Jeffrey Bryant

2008-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

The results of an ecological risk assessment screening at the Idaho National Engineering`s waste area group 2

Energy Technology Data Exchange (ETDEWEB)

VanHorn, R.

1995-11-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho and occupies approximately 890 square miles on the northwestern portion of the eastern Snake River Plain. INEL has been devoted to nuclear energy research and related activities since its establishment in 1949. In the process of fulfilling this mission, wastes were generated, including radioactive and hazardous materials. Most materials were effectively stored or disposed of, however, some release of contaminants to the environment has occurred. For this reason, the INEL was listed by the US environmental Protection Agency on the National Priorities List (NPL), in November, 1989. This report describes the results of an ecological risk assessment performed for the Waste Area Groups 2 (WAG 2) at the INEL. It also summarizes the performance of screening level ecological risk assessments (SLERA).

Irradiated Beryllium Disposal Workshop, Idaho Falls, ID, May 29-30, 2002

Energy Technology Data Exchange (ETDEWEB)

Longhurst, Glen Reed; Anderson, Gail; Mullen, Carlan K; West, William Howard

2002-07-01

In 2001, while performing routine radioactive decay heat rate calculations for beryllium reflector blocks for the Advanced Test Reactor (ATR), it became evident that there may be sufficient concentrations of transuranic isotopes to require classification of this irradiated beryllium as transuranic waste. Measurements on samples from ATR reflector blocks and further calculations confirmed that for reflector blocks and outer shim control cylinders now in the ATR canal, transuranic activities are about five times the threshold for classification. That situation implies that there is no apparent disposal pathway for this material. The problem is not unique to the ATR. The High Flux Isotope Reactor at Oak Ridge National Laboratory, the Missouri University Research Reactor at Columbia, Missouri and other reactors abroad must also deal with this issue. A workshop was held in Idaho Falls Idaho on May 29-30, 2002 to acquaint stakeholders with these findings and consider a path forward in resolving the issues attendant to disposition of irradiated material. Among the findings from this workshop were (1) there is a real potential for the US to be dependent on foreign sources for metallic beryllium within about a decade; (2) there is a need for a national policy on beryllium utilization and disposition and for a beryllium coordinating committee to be assembled to provide guidance on that policy; (3) it appears it will be difficult to dispose of this material at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico due to issues of Defense classification, facility radioactivity inventory limits, and transportation to WIPP; (4) there is a need for a funded DOE program to seek resolution of these issues including research on processing techniques that may make this waste acceptable in an existing disposal pathway or allow for its recycle.

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

Energy Technology Data Exchange (ETDEWEB)

M. D. Staiger

1999-06-01

A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

75 FR 32210 - United States v. Idaho Orthopaedic Society, Timothy Doerr, Jeffrey Hessing, Idaho Sports Medicine...

Science.gov (United States)

2010-06-07

..., Jeffrey Hessing, Idaho Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins; Proposed... Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins, Civil Case No. 10-268. On May 28..., Jeffrey Hessing, Idaho Sports Medicine Institute, John Kloss, David Lamey, and Troy Watkins, Defendants...

Low-level waste incineration at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Gillins, R.L.; Davis, J.N.; Maughan, R.Y.; Logan, J.A.

1985-01-01

A facility for the incineration of low-level beta/gamma contaminated combustible waste has been constructed at the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL). The incineration facility was established to: (1) reduce the volume of currently generated contaminated combustible waste being disposed at the INEL's radioactive waste disposal site and thereby prolong the site's useful life; and (2) develop waste processing technology by providing a facility where full-size processes and equipment can be demonstrated and proven during production-scale operations. Cold systems testing has been completed, and contaminated operations began in September of 1984. Currently the facility is processing waste packaged in 2 x 2 x 2 ft cardboard boxes and measuring <10mR/h at contact. 3 figs

Process for improving the separation efficiency in the isolation of radioactive isotopes in elementary or chemically bonded form from liquids and gases

International Nuclear Information System (INIS)

Schmidberger, R.; Kirch, R.; Kock, W.

1986-01-01

In the process for the improvement of the separation efficiency in the isolation of radioactive isotopes in elementary or chemically bonded form from liquids or gases by ion exchange and adsorption, non-radioactive isotopes of the element to be isolated are added to the fluid before the isolation, whereas at the same time a large surplus of the non-radioactive isotopes to the radioactive isotopes is achieved by addition of only small quantities of compounds of the non-radioactive isotopes. (orig./RB) [de

Forest decline, natural and technically generated radioactivity

International Nuclear Information System (INIS)

Teufel, D.

1983-06-01

The question investigated is whether the radioactive rare gases emanating from nuclear plants are causative or participate in the triggering of forest disease. For one thing, a chemical reaction could be responsible for such an effect exerted by these artificial radioactive effluents. However, a calculation shows the concentration of radionuclides, respectively, in this case, their decomposition products, to be by many orders of magnitude smaller than other constituents in air; so a chemical reaction of this kind may be excluded. For the other part, rare gases might contribute to forest damage by their radioactive decomposition and late physical, chemical, and biological effects. In this connection, a detailed analysis is made of the comparability of natural radioactivity with radioactivity generated by nuclear plants. A possible contribution towards the total stress situation of forests (chemical air pollution, natural radioactivity, artificially produced radioactive rare gases, weather conditions and conditions arising from forest management and the like) would amount to a proportion smaller than 1/1000 considering natural radioactivity as a possible stress factor only. (orig.) [de

Public Participation Plan for Waste Area Group 7 Operable Unit 7-13/14 at the Idaho National Laboratory Site

International Nuclear Information System (INIS)

B. G. Meagher

2007-01-01

This Public Participation Plan outlines activities being planned to: (1) brief the public on results of the remedial investigation and feasibility study, (2) discuss the proposed plan for remediation of Operable Unit 7-13/14 with the public, and (3) encourage public participation in the decision-making process. Operable Unit 7-13/14 is the Comprehensive Remedial Investigation/Feasibility Study for Waste Area Group 7. Analysis focuses on the Subsurface Disposal Area (SDA) within the Radioactive Waste Management Complex at the Idaho National Laboratory (Site). This plan, a supplement to the Idaho National Laboratory Community Relations Plan (DOE-ID 2004), will be updated as necessary. The U.S. Department of Energy (DOE), Idaho Department of Environmental Quality (DEQ), and U.S. Environmental Protection Agency (EPA) will participate in the public involvement activities outlined in this plan. Collectively, DOE, DEQ, and EPA are referred to as the Agencies. Because history has shown that implementing the minimum required public involvement activities is not sufficient for high-visibility cleanup projects, this plan outlines additional opportunities the Agencies are providing to ensure that the public's information needs are met and that the Agencies can use the public's input for decisions regarding remediation activities

Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory: Annual technology assessment and progress report

International Nuclear Information System (INIS)

Low, J.O.; Allman, D.W.; Shaw, P.G.; Sill, C.W.

1987-01-01

In-situ grouting, an improved-confinement technology that could be applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste, is being investigated by EG and G Idaho, Inc. In situ grouting has been demonstrated as the culmination of a two-year engineering feasibility test at the INEL. In situ stabilization and hydrologic isolation of a simulated buried TRU waste trench at an arid site were performed using an experimental dynamic compaction in situ grouting process developed by Rockwell Hanford Operations (RHO). A series of laboratory evaluations relative to the grout permeation characteristics of microfine particulate cements with INEL-type soil was performed prior to the grouting operations. In addition, an extensive pre-grouting hydrologic assessment of the test trench was performed to support the performance assessment analysis. Laboratory testing of various chemical materials yielded a suitable hydrologic tracer for use in the hydrologic monitoring phase of the experiment. Various plutonium transport laboratory evaluations were performed to assess the plutonium retention capabilities of a microfine grout/INEL-soil waste product similar to that expected to result if the grout is injected in situ into the INEL test trench. The test trench will be hydrologically assessed in FY 1987 to determine if the RHO grouting system attained the performance acceptance criteria of the experiment. The report includes a technology assessment of buried waste technologies developed by other DOE sites. Field demonstrations at ORNL and Hanford are reported under this technology assessment. Also included is information on activities related to buried waste management at the INEL. These include environmental surveillance of the Radioactive Waste Management Complex and the Subsurface Migration Studies Program

The development of radioactive sample surrogates for training and exercises

International Nuclear Information System (INIS)

Kevin Carney; Martha Finck; Christopher McGrath; Bevin Brush; Dick Jansen; Donald Dry; George Brooks; David Chamberlain

2013-01-01

Source term information is required for to reconstruct a device used in a dispersed radiological dispersal device. Simulating a radioactive environment to train and exercise sampling and sample characterization methods with suitable sample materials is a continued challenge. The Idaho National Laboratory has developed and permitted a radioactive response training range (RRTR), an 800 acre test range that is approved for open air dispersal of activated KBr, for training first responders in the entry and exit from radioactively contaminated areas, and testing protocols for environmental sampling and field characterization. Members from the Department of Defense, Law Enforcement, and the Department of Energy participated in the first contamination exercise that was conducted at the RRTR in the July 2011. The range was contaminated using a short lived radioactive 82 Br isotope (activated KBr). Soil samples contaminated with KBr (dispersed as a solution) and glass particles containing activated potassium bromide that emulated dispersed radioactive materials (such as ceramic-based sealed source materials) were collected to assess environmental sampling and characterization techniques. This presentation summarizes the performance of a radioactive materials surrogate for use as a training aide for nuclear forensics. (author)

The interaction between bitumen matrix and chemical components of radioactive wastes of WWER type

International Nuclear Information System (INIS)

Selucky, P.; Sazavsky, P.; Peka, V.; Krupka, M.

2000-01-01

The interaction between bitumen matrix and chemical components of WWER type radioactive wastes was studied. So called ''cold'' model bitumen products were prepared and compared with real products using macroDTA method. On the basis of obtained curves, the evaluation of bitumen product fire risks was performed with the aim to minimize risks of bituminization process. (authors)

Weed hosts Globodera pallida from Idaho

Science.gov (United States)

The potato cyst nematode, Globodera pallida (PCN), a restricted pest in the USA, was first reported in Bingham and Bonneville counties of Idaho in 2006. The US government and Idaho State Department of Agriculture hope to eradicate it from infested fields. Eradicating PCN will require depriving the n...

Design of chemical treatment unit for radioactive liquid wastes in Serpong nuclear facilities

International Nuclear Information System (INIS)

Salimin, Z.; Walman, E.; Santoso, P.; Purnomo, S.; Sugito; Suwardiyono; Wintono

1996-01-01

The chemical treatment unit for radioactive liquid wastes arising from nuclear fuel fabrication, radioisotopes production and radiometallurgy facility has been designed. The design of chemical processing unit is based on the characteristics of liquid wastes containing fluors from uranium fluoride conversion process to ammonium uranyl carbonate on the fuel fabrication. The chemical treatment has the following process steps: coagulation-precipitation of fluoride ion by calcium hydroxide coagulant, separation of supernatant solution from sludge, coagulation of remaining fluoride on the supernatant solution by alum, separation of supernatant from sludge, and than precipitation of fluors on the supernatant by polymer resin WWS 116. The processing unit is composed of 3 storage tanks for raw liquid wastes (capacity 1 m 3 per tank), 5 storage tanks for chemicals (capacity 0.5 m 3 per tank), 2 mixing reactors (capacity 0.5 m 3 per reactor), 1 storage tank for supernatant solution (capacity 1 m 3 ), and 1 storage tank for sludge (capacity 1 m 3 )

Chemical treatment of radioactive liquid wastes from medical applications

International Nuclear Information System (INIS)

Castillo A, J.

1995-01-01

This work is a study about the treatment of the most important radioactive liquid wastes from medical usages, generated in medical institutions with nuclear medicine services. The radionuclides take in account are 32 P, 35 S, 125 I. The treatments developed and improved were specific chemical precipitations for each one of the radionuclides. This work involve to precipitate the radionuclide from the liquid waste, making a chemical compound insoluble in the aqueous phase, for this process the radionuclide stay in the precipitate, lifting the aqueous phase with a very low activity than the begin. The 32 P precipitated in form of Ca 3 32 P O 4 and Ca 2 H 32 P O 4 with a value for Decontamination Factor (DF) at the end of the treatment of 32. The 35 S was precipitated in form of Ba 35 SO 4 with a DF of 26. The 125 I was precipitated in Cu 125 I to obtain a DF of 24. The results of the treatments are between the limits given for the International Atomic Energy Agency and the 10 Code of Federal Regulation 20, for the safety release at the environment. (Author)

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

Idaho Transportation Department 2011 customer satisfaction survey.

Science.gov (United States)

2011-10-01

In the spring and summer of 2011, the Idaho Transportation Department (ITD) commissioned a statewide customer satisfaction survey of Idaho residents to assess their perception of ITDs performance in several key areas of customer service. The areas...

Spreadsheet application to classify radioactive material for shipment

International Nuclear Information System (INIS)

Brown, A.N.

1997-12-01

A spreadsheet application has been developed at the Idaho National Engineering and Environmental Laboratory to aid the shipper when classifying nuclide mixtures of normal form, radioactive materials. The results generated by this spreadsheet are used to confirm the proper US Department of Transportation (DOT) classification when offering radioactive material packages for transport. The user must input to the spreadsheet the mass of the material being classified, the physical form (liquid or not), and the activity of each regulated nuclide. The spreadsheet uses these inputs to calculate two general values: (1) the specific activity of the material, and (2) a summation calculation of the nuclide content. The specific activity is used to determine if the material exceeds the DOT minimal threshold for a radioactive material (Yes or No). If the material is calculated to be radioactive, the specific activity is also used to determine if the material meets the activity requirement for one of the three Low Specific Activity designations (LSA-I, LSA-II, LSA-III, or Not LSA). Again, if the material is calculated to be radioactive, the summation calculation is then used to determine which activity category the material will meet (Limited Quantity, Type A, Type B, or Highway Route Controlled Quantity)

Geophysical surveys for buried waste detection at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Sandness, G.A.; Rising, J.L.; Kimbrough, J.R.

1979-12-01

This report describes a series of geophysical surveys performed at the Idaho National Engineering Laboratory (INEL). The main purpose of the surveys was to evaluate techniques, principally ground-penetrating radar, for detecting and mapping radioactive wastes buried in shallow trenches and pits. A second purpose was to determine the feasibility of using ground-penetrating radar to measure the depth of basalt bedrock. A prototype geophyscal survey system developed by the US Department of Energy's Pacific Northwest Laboratory was used for this study. Radar, magnetometer, and metal detector measurements were made at three sites in the Radioactive Waste Management Complex (RWMC) at INEL. Radar measurements were made at fourth site adjacent to the RWMC. The combination of three geophysical methods was shown to provide considerable information about the distribution of buried waste materials. The tests confirmed the potential effectiveness of the radar method, but they also pointed out the need for continued research and development in ground-penetrating radar technology. The radar system tested in this study appears to be capable of measuring the depth to basalt in the vicinity of the RWMC

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Idaho Transportation Department 2016 Customer Communication Survey

Science.gov (United States)

2017-06-23

In 2016, the Idaho Transportation Department contracted with the University of Idaho's Social Science Research Unit to conduct a survey on the general public's engagement and communication with the department. The goal of conducting this survey was t...

Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho

International Nuclear Information System (INIS)

Stevens, G.H.; Coleman, R.L.; Jensen, M.K.; Pierce, G.A.; Egidi, P.V.; Mather, S.K.

1993-01-01

An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site's compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiation scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building's interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor's report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for 60 Co were below the detection limit. The highest 137 Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g

U.S. Geological Survey geohydrologic studies and monitoring at the Idaho National Laboratory, southeastern Idaho

Science.gov (United States)

Bartholomay, Roy C.

2017-09-14

BackgroundThe U.S. Geological Survey (USGS) geohydrologic studies and monitoring at the Idaho National Laboratory (INL) is an ongoing, long-term program. This program, which began in 1949, includes hydrologic monitoring networks and investigative studies that describe the effects of waste disposal on water contained in the eastern Snake River Plain (ESRP) aquifer and the availability of water for long-term consumptive and industrial use. Interpretive reports documenting study findings are available to the U.S. Department of Energy (DOE) and its contractors; other Federal, State, and local agencies; private firms; and the public at https://id.water.usgs.gov/INL/Pubs/index.html. Information contained within these reports is crucial to the management and use of the aquifer by the INL and the State of Idaho. USGS geohydrologic studies and monitoring are done in cooperation with the DOE Idaho Operations Office.

Idaho Transportation Department 2009 customer satisfaction survey.

Science.gov (United States)

2010-02-01

In the summer and fall of 2009, the Idaho Transportation Department (ITD) commissioned a statewide customer satisfaction survey of Idaho residents in order to assess the overall level of satisfaction with several key areas of service provided by the ...

Aerial gamma ray and magnetic survey: Idaho Project, Hailey quadrangle of Idaho. Final report

International Nuclear Information System (INIS)

1979-12-01

The Hailey quadrangle in central Idaho lies at the boundary between the Northern Rocky Mountains and the western Cordilleran Physiographic Provinces. The area is dominated by intrusives of the Idaho and Sawtooth Batholiths, but contains considerable exposures of Tertiary and Quaternary volcanics, and Paleozoic sedimentary rocks. Magnetic data apparently show some expression of the intrusives of the Idaho Batholith. Areas of faulted Paleozoic and Tertiary rocks appear to express themselves as roughly defined regions of high frequency/high amplitude wavelengths. The Hailey quadrangle has been unproductive in terms of uranium mining, though some prospects do exist south of the town of Hailey. The quadrangle contains significant exposures of the Tertiary Challis Formation (primarily volcanics) which has been productive in other areas to the north. A total of 161 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle. The most distinctive groups of anomalies are associated with Tertiary igneous rocks in the mountainous areas

An update of hydrologic conditions and distribution of selected constituents in water, Snake River Plain aquifer and perched groundwater zones, Idaho National Laboratory, Idaho, emphasis 2006-08

Science.gov (United States)

Davis, Linda C.

2010-01-01

Since 1952, radiochemical and chemical wastewater discharged to infiltration ponds (also called percolation ponds), evaporation ponds, and disposal wells at the Idaho National Laboratory (INL) has affected water quality in the eastern Snake River Plain aquifer and perched groundwater zones underlying the INL. The U.S. Geological Survey, in cooperation with the U.S. Department of Energy, maintains groundwater monitoring networks at the INL to determine hydrologic trends, and to delineate the movement of radiochemical and chemical wastes in the aquifer and in perched groundwater zones. This report presents an analysis of water-level and water-quality data collected from aquifer and perched groundwater wells in the USGS groundwater monitoring networks during 2006-08. Water in the Snake River Plain aquifer primarily moves through fractures and interflow zones in basalt, generally flows southwestward, and eventually discharges at springs along the Snake River. The aquifer primarily is recharged from infiltration of irrigation water, infiltration of streamflow, groundwater inflow from adjoining mountain drainage basins, and infiltration of precipitation. From March-May 2005 to March-May 2008, water levels in wells generally remained constant or rose slightly in the southwestern corner of the INL. Water levels declined in the central and northern parts of the INL. The declines ranged from about 1 to 3 feet in the central part of the INL, to as much as 9 feet in the northern part of the INL. Water levels in perched groundwater wells around the Advanced Test Reactor Complex (ATRC) also declined. Detectable concentrations of radiochemical constituents in water samples from wells in the Snake River Plain aquifer at the INL generally decreased or remained constant during 2006-08. Decreases in concentrations were attributed to decreased rates of radioactive-waste disposal, radioactive decay, changes in waste-disposal methods, and dilution from recharge and underflow. In April

An Update of Hydrologic Conditions and Distribution of Selected Constituents in Water, Snake River Plain Aquifer and Perched-Water Zones, Idaho National Laboratory, Idaho, Emphasis 2002-05

Science.gov (United States)

Davis, Linda C.

2008-01-01

Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds, evaporation ponds, and disposal wells at the Idaho National Laboratory (INL) has affected water quality in the Snake River Plain aquifer and perched-water zones underlying the INL. The U.S. Geological Survey, in cooperation with the U.S. Department of Energy, maintains ground-water monitoring networks at the INL to determine hydrologic trends, and to delineate the movement of radiochemical and chemical wastes in the aquifer and in perched-water zones. This report presents an analysis of water-level and water-quality data collected from aquifer and perched-water wells in the USGS ground-water monitoring networks during 2002-05. Water in the Snake River Plain aquifer primarily moves through fractures and interflow zones in basalt, generally flows southwestward, and eventually discharges at springs along the Snake River. The aquifer is recharged primarily from infiltration of irrigation water, infiltration of streamflow, ground-water inflow from adjoining mountain drainage basins, and infiltration of precipitation. From March-May 2001 to March-May 2005, water levels in wells declined throughout the INL area. The declines ranged from about 3 to 8 feet in the southwestern part of the INL, about 10 to 15 feet in the west central part of the INL, and about 6 to 11 feet in the northern part of the INL. Water levels in perched water wells declined also, with the water level dropping below the bottom of the pump in many wells during 2002-05. For radionuclides, concentrations that equal 3s, wheres s is the sample standard deviation, represent a measurement at the minimum detectable concentration, or 'reporting level'. Detectable concentrations of radiochemical constituents in water samples from wells in the Snake River Plain aquifer at the INL generally decreased or remained constant during 2002-05. Decreases in concentrations were attributed to decreased rates of radioactive-waste disposal

Current practice of incineration of low-level institutional radioactive waste

International Nuclear Information System (INIS)

Cooley, L.R.; McCampbell, M.R.; Thompson, J.D.

1981-02-01

During 1972, 142 medical and academic institutions were surveyed to assess the current practice of incineration of low-level radioactive waste. This was one activity carried out by the University of Maryland as part of a contract with EG and G Idaho, Inc., to site a radioactive waste incineration system. Of those surveyed, 46 (approximately 32%) were presently incinerating some type of radioactive waste. All were using controlled-air, multistage incinerators. Incinerators were most often used to burn animal carcasses and other biological wastes (96%). The average size unit had a capacity of 113 kg/h. Disposal of liquid scintillation vials posed special problems; eight institutions incinerated full scintillation vials and five incinerated scintillation fluids in bulk form. Most institutions (87%) used the incinerator to dispose of other wastes in addition to radioactive wastes. About half (20) of the institutions incinerating radioactive wastes reported shortcomings in their incineration process; those most often mentioned were: problems with liquid scintillation wastes, ash removal, melting glass, and visible smoke. Frequently cited reasons for incinerating wastes were: less expensive than shipping for commercial shallow land burial, volume reduction, convenience, and closure of existing disposal sites

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Goldberg, Edward S.; Keating, John J.

1991-08-01

The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG G Idaho, Inc. (EG G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes.

Idaho National Engineering Laboratory: Annual report, 1986

International Nuclear Information System (INIS)

1986-01-01

The INEL underwent a year of transition in 1986. Success with new business initiatives, the prospects of even better things to come, and increased national recognition provided the INEL with a glimpse of its promising and exciting future. Among the highlights were: selection of the INEL as the preferred site for the Special Isotope Separation Facility (SIS); the first shipments of core debris from the Three Mile Island Unit 2 reactor to the INEL; dedication of three new facilities - the Fluorinel Dissolution Process, the Remote Analytical Laboratory, and the Stored Waste Experimental Pilot Plant; groundbreaking for the Fuel Processing Restoration Facility; and the first IR-100 award won by the INEL, given for an innovative machine vision system. The INEL has been assigned project management responsibility for the SDI Office-sponsored Multimegawatt Space Reactor and the Air Force-sponsored Multimegawatt Terrestrial Power Plant Project. New Department of Defense initiatives have been realized in projects involving development of prototype defense electronics systems, materials research, and hazardous waste technology. While some of our major reactor safety research programs have been completed, the INEL continues as a leader in advanced reactor technologies development. In April, successful tests were conducted for the development of the Integral Fast Reactor. Other 1986 highlights included the INEL's increased support to the Office of Civilian Radioactive Waste Management for complying with the Nuclear Waste Policy Act of 1982. Major INEL activities included managing a cask procurement program, demonstrating fuel assembly consolidation, and testing spent fuel storage casks. In addition, the INEL supplied the Tennessee Valley Authority with management and personnel experienced in reactor technology, increased basic research programs at the Idaho Research Center, and made numerous outreach efforts to assist the economies of Idaho communities

Study of chemical reactions in the nuclear underground explosion - Incidence on radioactivity

International Nuclear Information System (INIS)

Picq, Jean Maurice

1970-01-01

In order to find out and state the theoretical or semi-empirical laws governing the reaction of radioactivity in contained nuclear explosion, we are studying the chemical reactions during the different stages of the cavity and chimney formation, as well as thermal transfers. At the same time, we are carrying an experimental study on melted rock and gas samples taken from the French underground explosions. The results of which can be found in this paper are derived from our present experiments at the plant (have been obtained from partial studies). During the French underground explosions, we took gaseous samples. The gas analysis, without taking water vapour into consideration, showed that those samples were composed of hydrogen, carbon dioxide, carbon monoxide with small quantities of hydrocarbons (chiefly methane - about one per cent). The total amount of gas being quite large and proportional to the burst power, we came to the conclusion that those gases were produced by rock reactions (that rock was granite). We considered the following reagents because they were found in sufficient quantities to alter the balance between the different components: ferrous ions contained in mica, biotite, carbon dioxide from carbonates and water, either free or in a component state, contained in the rock. A comparison between theoretical and experimental results led us to notice among other things: the temperature of rock re-solidification; pressure nearing lithostatic pressure. Since the components of the environment, water not included, is quite homogeneous, the gas volume produced by '1 kiloton' is quite constant. On the other hand, the relative proportion of the gases undergoes a few changes, particularly the ratio CO/CO 2 which normally depends on the quantity of water contained in the environment. This statement is verified by the calculation of thermodynamic equilibriums. In order to calculate the simultaneous chemical equilibrium we have first selected five reactions. We

Evaluation of quality assurance/quality control data collected by the U.S. Geological Survey for water-quality activities at the Idaho National Engineering and Environmental Laboratory, Idaho, 1994 through 1995

International Nuclear Information System (INIS)

Williams, L.M.

1997-03-01

More than 4,000 water samples were collected by the US Geological Survey (USGS) from 179 monitoring sites for the water-quality monitoring program at the Idaho National Engineering Laboratory from 1994 through 1995. Approximately 500 of the water samples were replicate or blank samples collected for the quality assurance/quality control program. Analyses were performed to determine the concentrations of major ions, nutrients, trace elements, gross radioactivity and radionuclides, total organic carbon, and volatile organic compounds in the samples. To evaluate the precision of field and laboratory methods, analytical results of the replicate pairs of samples were compared statistically for equivalence on the basis of the precision associated with each result. In all, the statistical comparison of the data indicated that 95% of the replicate pairs were equivalent. Within the major ion analyses, 97% were equivalent; nutrients, 88%; trace elements, 95%; gross radioactivity and radionuclides, 93%; and organic constituents, 98%. Ninety percent or more of the analytical results for each constituent were equivalent, except for nitrite, orthophosphate, phosphorus, aluminum, iron, strontium-90, and total organic carbon

Time-table of important events in connection with radioactive waste disposal

International Nuclear Information System (INIS)

1982-07-01

This data compilation is a small manual in connection with the radioactive waste disposal of German nuclear power plants. The record begins December 12, 1951, when electric power from nuclear energy was first generated in the Arco Reactor in Idaho/USA, and is continued till July 20, 1982, when the government of the Land Hessen confirmed a previous decision selecting Wangershausen as the site for a projected reprocessing plant. (orig./HSCH) [de

Upper parameters of toxicity (LDsub(50/30)) of some radioactive and chemical substances

International Nuclear Information System (INIS)

Rodionova, L.F.; Kupriyanova, V.M.; Zasedatelev, A.A.

1978-01-01

The toxicities of radioactive ( 90 Sr, 210 Po) and chemical (lead nitrate, mercuric chloride) substances were compared using equivalent procedures. Ninety six doses of toxic substances in various concentrations were tested on mice to which these substances were administered by intragastric intubation. The material was processed and analyzed by conventional methods used in toxicology. The upper limits of toxicity for the tested substances were determined from their LDsub(50/30) values by various methods of calculation

Refining technology for the recycling of stainless steel radioactive scrap metals, FY 94 bi-annual report

International Nuclear Information System (INIS)

Mizia, R.E.; Atteridge, D.G.; Buckentin, J.; Carter, J.; Davis, H.L.; Devletian, J.H.; Scholl, M.R.; Turpin, R.B.; Webster, S.L.

1994-08-01

The research addressed under this project is the recycling of metallic nuclear-related by-product materials under the direction of Westinghouse Idaho Nuclear Company (WINCO). The program addresses the recycling of radioactive scrap metals (RSM) for beneficial re-use within the DOE complex; in particular, this program addresses the recycling of stainless steel RSM. It is anticipated that various stainless steel components under WINCO control at the Idaho Falls Engineering Laboratory (INEL), such as fuel pool criticality barriers and fuel storage racks will begin to be recycled in FY94-95. The end product of this recycling effort is expected to be waste and overpack canisters for densified high level waste for the Idaho Waste Immobilization Facility and/or the Universal Canister System for dry (interim) storage of spent fuel. The specific components of this problem area that are presently being, or have been, addressed by CAAMSEC are: (1) the melting/remelting of stainless steel RSM into billet form; (2) the melting/remelting initial research focus will be on the use of radioactive surrogates to study; (3) the cost effectiveness of RSM processing oriented towards privatization of RSM reuse and/or resale. Other components of this problem that may be addressed under program extension are: (4) the melting/remelting of carbon steel; (5) the processing of billet material into product form which shall meet all applicable ASTM requirements; and, (6) the fabrication of an actual prototypical product; the present concept of an end product is a low carbon Type 304/316 stainless steel cylindrical container for densified and/or vitrified high level radioactive waste and/or the Universal Canister System for dry (interim) storage of spent fuel. The specific work reported herein covers the melting/remelting of stainless steel open-quotes scrapclose quotes metal into billet form and the study of surrogate material removal effectiveness by various remelting techniques

Allium-test as a tool for toxicity testing of environmental radioactive-chemical mixtures

Science.gov (United States)

Oudalova, A. A.; Geras'kin, S. A.; Dikareva, N. S.; Pyatkova, S. V.

2017-01-01

Bioassay-based approaches have been propagated to assess toxicity of unknown mixtures of environmental contaminants, but it was rarely applied in cases of chemicals with radionuclides combinations. Two Allium-test studies were performed to assess environmental impact from potential sources of combined radioactive-chemical pollution. Study sites were located at nuclear waste storage facilities in European and in Far-Eastern parts of Russia. As environmental media under impact, waters from monitor wells and nearby water bodies were tested. Concentrations of some chemicals and radionuclides in the samples collected enhanced the permitted limits. Cytogenetic and cytotoxic effects were used as biological endpoints, namely, frequency and spectrum of chromosome aberrations and mitotic abnormalities in anatelophase cells as well as mitotic activity in Allium root tips. Sample points were revealed where waters have an enhanced mutagenic potential. The findings obtained could be used to optimize monitoring system and advance decision making on management and rehabilitation of industrial sites. The Allium-test could be recommended and applied as an effective tool for toxicity testing in case of combined contamination of environmental compartments with radionuclides and chemical compounds.

Chemical engineering problems of radioactive waste fixation by vitrification

International Nuclear Information System (INIS)

Taylor, R.F.

1985-01-01

Basic features are reviewed of the chemical engineering problems faced in the vitrification of the high-level radioactive liquid wastes resulting from the reprocessing of nuclear fuel. After an outline of glass solution properties and formation kinetics the constituent elements of the vitrification route are examined in turn: waste feed evaporation and denitration, calcination, offgas treatment, and finally melting and product quality. Plant and experimental data for each stage are discussed with comparison between process routes and with reference to the underlying principles. Attention is drawn to the future need for higher trapping efficiencies and for dealing with a wider range of species in offgas treatments as higher burnup fuels are processed after shorter cooling times from reactor. Two areas of present study where deeper insight into underlying process mechanics is needed are, firstly, the association of waste material with glass formers in the wet or sinter stages and secondly their incorporation and mixing reaction in the melt. Fuller understanding here would bring direct benefit to process performance and handling. The problems discussed are not of a nature to jeopardize the vitrification routes but if product quality does come to rely heavily on process control then demonstrable confidence in the behaviour of the central physico-chemical interactions is indispensable. (author)

Direct conversion of radioactive and chemical waste containing metals, ceramics, amorphous solids, and organics to glass

International Nuclear Information System (INIS)

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1994-01-01

The Glass Material Oxidation and Dissolution System (CMODS) is a new process for direct conversion of radioactive, mixed, and chemical wastes to glass. The wastes can be in the chemical forms of metals, ceramics, amorphous solids, and organics. GMODS destroys organics and it incorporates heavy metals and radionuclides into a glass. Processable wastes may include miscellaneous spent fuels (SF), SF hulls and hardware, plutonium wastes in different forms, high-efficiency particulate air (HEPA) filters, ion-exchange resins, failed equipment, and laboratory wastes. Thermodynamic calculations indicate theoretical feasibility. Small-scale laboratory experiments (< 100 g per test) have demonstrated chemical laboratory feasibility for several metals. Additional work is needed to demonstrate engineering feasibility

Assessing the Idaho Transportation Department's customer service performance.

Science.gov (United States)

2011-10-23

This report assesses customer satisfaction with the Idaho Transportation Department. It also compares and contrasts the results of customer satisfaction surveys conducted for the Idaho Transportation Department with the results from other state trans...

Waste management 86. Volume 1:General interest

International Nuclear Information System (INIS)

Post, R.G.

1986-01-01

This book presents the papers given at a symposium on radioactive waste management. Topics considered at the symposium included the status of radioactive waste disposal, the status of international nuclear waste management, waste management activities at the Idaho National Engineering Laboratory, legal and liability issues, risk perceptions and public involvement, waste transportation, waste processing, remedial action, decontamination, predisposal processing and treatment processes, low-level and mixed waste management, and mixed chemical and radioactive waste disposal

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

The Management Subteam conducted a management assessment of Environment, Safety, and Health (ES ampersand H) programs and their implementation of Idaho National Engineering Laboratory (INEL). The objectives of the assessment were to: (1) evaluate the effectiveness of existing management functions and processes in terms of ensuring environmental compliance, and the health and safety of workers and the general public; and (2) identify probable root causes for ES ampersand H findings and concerns. Organizations reviewed were DOE-Headquarters: DOE Field Offices, Chicago (CH) and Idaho (ID); Argonne Area Offices, East (AAO-E) and West (AAO-W); Radiological and Environmental Sciences Laboratory (RESL); Argonne National Laboratory (ANL); EG ampersand G Idaho, Inc. (EG ampersand G); Westinghouse Idaho Nuclear Company, Inc. (WINCO); Rockwell-INEL; MK-Ferguson of Idaho Company (MK-FIC); and Protection Technology of Idaho, Inc. (PTI). The scope of the assessment covered the following ES ampersand H management issues: policies and procedures; roles, responsibilities, and authorities; management commitment; communication; staff development, training, and certification; recruitment; compliance management; conduct of operations; emergency planning and preparedness; quality assurance; self assessment; oversight activities; and cost plus award fee processes

Transfer of radioactive and chemical pollutants into irrigated rice fields

International Nuclear Information System (INIS)

Myttenaere, C.; Mousny, J.-M.; Dabin, P.; Bittel, R.

1975-01-01

In a general study on the consequences of radioactive and chemical releases in continental waters, flooded rice fields must be considered as a very important ecosystem due to the very large quantities of water used. In order to approach as much as possible to the natural conditions (irrigated rice fields of Northern Italy) ''mini-rice fields'' were built and local practices were respected. The behavior of activation and fission products ( 137 Cs, 60 Co, 65 Zn, 51 Cr...) and heavy metals pollutants (Cd, Cr, Sn) was studied and the transfer from water to soil and plant was followed. Concentration factors were calculated for the different organs of the plant and the impact of rice ingested to the dose delivered to man was evaluated [fr

EG and G Idaho Environmental Protection Implementation Plan (1991)

Energy Technology Data Exchange (ETDEWEB)

Graham, J.F.

1991-11-01

This report describes the EG G Idaho, Inc. strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy -- Field Office Idaho (DOE-ID) Environmental Protection Implementation Plan by detailing EG G Idaho Environmental Protection Program activities. This report describes the current status of the EG G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG G Idaho organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab.

EG and G Idaho Environmental Protection Implementation Plan (1991)

International Nuclear Information System (INIS)

Graham, J.F.

1991-11-01

This report describes the EG ampersand G Idaho, Inc. strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy -- Field Office Idaho (DOE-ID) Environmental Protection Implementation Plan by detailing EG ampersand G Idaho Environmental Protection Program activities. This report describes the current status of the EG ampersand G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG ampersand G Idaho organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab

North Idaho E. coli Infections Linked to Raw Clover Sprouts > Idaho

Science.gov (United States)

About Establishing Legal Fatherhood Genetic Testing Ending Services Fees for Services Child Support and Children's Special Health Program Genetic/Metabolic Services Genetic Condition Information Health Care Healthcare Associated Infections Antibiotic Resistance Epidemiology Idaho Disease Bulletin Data and

Sage grouse on the Idaho National Environmental Research Park

International Nuclear Information System (INIS)

Connelly, J.W.; Ball, I.J.

1983-01-01

A comprehensive study of sage grouse (Centrocercus urophasianus) ecology was conducted on the Idaho National Engineering Laboratory (INEL) site between June 1977 and May 1981. Sage grouse used lawns surrounding INEL facilities for feeding and loafing throughot the summer. Mean summer home range was 406 ha for adult female sage grouse and 94 ha for juveniles. Radionuclide concentrations in grouse summering near a liquid radioactive waste disposal area (N = 29) were significantly higher than those in grouse summering near a solid radioactive waste disposal area (N = 14) or control areas (N = 20). Sage grouse moved from 2 to 83 km during seasonal migration. Fall movements from INEL facilities to winter range were slow and meandering. Spring movements of females from leks to summer range were also slow and meandering but male movements appeared rapid and direct. Sage grouse remained in segregated flocks during early summer but the number of mixed sex flocks increased in late summer. Sage grouse occurred in segregated flocks throughout the winter. Both flock type and habitat influenced winter sage grouse flock size. Mean flock size remained relatively constant as winter weather became more severe. Agricultural aras were an important component of sage grouse summer range and were preferred by all sage grouse sex and age classes. Sage grouse winter range was generally characterized by sagebrush stands with 11 to 30% canopy coverage

Evaluation of Quality-Assurance/Quality-Control Data Collected by the U.S. Geological Survey from Wells and Springs between the Southern Boundary of the Idaho National Engineering and Environmental Laboratory and the Hagerman Area, Idaho, 1989 through 1995

Energy Technology Data Exchange (ETDEWEB)

Williams, L.M.; Bartholomay, R.C.; Campbell, L.J.

1998-10-01

The U.S. Geological (USGS) and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, collected and analyzed water samples to monitor the water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area, Idaho. Concurrently, replicate samples and blank samples were collected and analyzed as part of the quality-assurance/quality-control program. Samples were analyzed from inorganic constituents, gross radioactivity and radionuclides, organic constituents, and stable isotopes. To evaluate the precision of field and laboratory methods, analytical results of the water-quality and replicate samples were compared statistically for equivalence on the basis of the precision associated with each result. Statistical comparisons of the data indicated that 95 percent of the results of the replicate pairs were equivalent. Blank-sample analytical results indicated th at the inorganic blank water and volatile organic compound blank water from the USGS National Water Quality Laboratory and the distilled water from the Idaho Department of Water Resources were suitable for blanks; blank water from other sources was not. Equipment-blank analytical results were evaluated to determine if a bias had been introduced and possible sources of bias. Most equipment blanks were analyzed for trace elements and volatile organic compounds; chloroform was found in one equipment blank. Two of the equipment blanks were prepared after collection and analyses of the water-quality samples to determine whether contamination had been introduced during the sampling process. Results of one blank indicated that a hose used to divert water away from pumps and electrical equipment had contaminated the samples with some volatile organic compounds. Results of the other equipment blank, from the apparatus used to filter dissolved organic carbon samples, indicated that the filtering

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1

International Nuclear Information System (INIS)

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-01-01

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ''Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste'', (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Growing the Idaho economy : moving into the future.

Science.gov (United States)

2010-08-13

A report on transportation and the possible future economy of the State of Idaho from 2010 to 2030, including : current assets to leverage, driving forces shaping the future, long-range economic opportunities for Idaho including : four future scenari...

Electronic tongue - an array of non-specific chemical sensors - for analysis of radioactive solutions

International Nuclear Information System (INIS)

Legin, A.; Rudnitskaya, A.; Babain, V.

2006-01-01

Multisensor systems, combining chemical sensor arrays with multivariate data processing engines (electronic tongue) rapidly and successfully developing in the last years are capable of simultaneous quantitative analysis of several species, e.g. metals, in complex real solutions. The expansion of the metals (metal ions) and species to be detected in radioactive waste requires permanent enhancement of sensing materials and sensors, with seriously different properties from those known earlier. A prospective direction of R and D of novel sensing materials is exploitation of radiochemical extraction systems and application of extraction substances as active components of new sensors. The sensors based on bidentate phosphorous organic compounds and their combinations with chlorinated cobalt dicarbollide displayed high sensitivity and selectivity to rare-earth metal ions La 3+ , Pr 3+ , Nd 3+ , Eu 3+ . The results indicated good promise for the development of novel analytical tools for detection of multivalent metal cations in different media, particularly in corrosive solutions such as radioactive wastes and solutions derived from spent nuclear fuel. The sensors and sensor arrays made on their basis can play an important role in the development of 'electronic tongue' systems for rapid analytical determinations of different components in complex radioactive solutions

Rehabilitation of radioactive objects of Kirovo-Chepetsky chemical plant preliminary program of works

International Nuclear Information System (INIS)

Chesnokov, F.V.; Ivanov, O.P.; Pavlenko, V.I.; Semenov, S.G.; Stepanov, V.E.; Volkov, V.G.; Volkovich, A.G.; Zverkov, Yu.A.

2008-01-01

In 2007, the specialists of RRC Kurchatov Institute, jointly with MosNPO Radon, launched works on the radiation survey of radiation-contaminated objects and areas on the site of Kirovo-Chetetsky Chemical Plant (KCCP). This survey was launched with the object of subsequent development of the rehabilitation program and concept for buildings and storage sites left from shutdown uranium-processing facilities, as well as for sludge storage facilities and repositories of radioactive waste produced as a result of these facilities operation. Besides, radioactive contamination caused by the preceding operations involving radwaste and equipment contaminated at early stages of uranium hexafluoride (UHF) and tetrafluoride (UTF) processing technology mastering was detected in some spots at KCCP site. The radiation survey was performed in order to assess the amount of rehabilitation works, to identify the most critical objects and areas at KCCP site, and to develop the sequence of measures to be implemented in order to enhance the radiation safety of people living in the Kirov Region. (author)

Idaho National Laboratory Cultural Resource Management Plan

Energy Technology Data Exchange (ETDEWEB)

Julie Braun Williams

2013-02-01

As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at Idaho National Laboratory in southeastern Idaho. The Idaho National Laboratory is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable, bear valuable physical and intangible legacies, and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through regular reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of appendices

SRS: Site ranking system for hazardous chemical and radioactive waste

International Nuclear Information System (INIS)

Rechard, R.P.; Chu, M.S.Y.; Brown, S.L.

1988-05-01

This report describes the rationale and presents instructions for a site ranking system (SRS). SRS ranks hazardous chemical and radioactive waste sites by scoring important and readily available factors that influence risk to human health. Using SRS, sites can be ranked for purposes of detailed site investigations. SRS evaluates the relative risk as a combination of potentially exposed population, chemical toxicity, and potential exposure of release from a waste site; hence, SRS uses the same concepts found in a detailed assessment of health risk. Basing SRS on the concepts of risk assessment tends to reduce the distortion of results found in other ranking schemes. More importantly, a clear logic helps ensure the successful application of the ranking procedure and increases its versatility when modifications are necessary for unique situations. Although one can rank sites using a detailed risk assessment, it is potentially costly because of data and resources required. SRS is an efficient approach to provide an order-of-magnitude ranking, requiring only readily available data (often only descriptive) and hand calculations. Worksheets are included to make the system easier to understand and use. 88 refs., 19 figs., 58 tabs

Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

International Nuclear Information System (INIS)

Wyrwas, R. B.

2016-01-01

The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval of actinides in the sludge in the waste tanks, and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.

Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

Energy Technology Data Exchange (ETDEWEB)

Wyrwas, R. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-09-01

The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval of actinides in the sludge in the waste tanks, and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.

Aerial gamma ray and magnetic survey: Idaho Project, Elk City quadrangle of Idaho/Montana. Final report

International Nuclear Information System (INIS)

1979-11-01

The Elk City quadrangle in north central Idaho and western Montana lies within the Northern Rocky Mountain province. The area is dominated by instrusives of the Idaho and Sawtooth Batholiths, but contains significant exposures of Precambrian metamorphics and Tertiary volcanics. Magnetic data apparently show some expression of the intrusives of the Idaho Batholith. Areas of faulted Precambrian and Tertiary rocks appear to express themselves as well defined regions of high frequency and high amplitudes wavelengths. The Elk City quadrangle has been unproductive in terms of uranium mining, though it contains significant exposures of the Challis Formation, which has been productive in other areas south of the quadrangle. A total of 238 anomalies are valid according to the criteria set forth in Volume I of this report. These anomalies are scattered throughout the quadrangle. The most distinctive group of anomalies with peak apparent uranium concentrations of 10.0 ppM eU or greater

Chemical toxicity and radioactivity of depleted uranium: The evidence from in vivo and in vitro studies.

Science.gov (United States)

Asic, Adna; Kurtovic-Kozaric, Amina; Besic, Larisa; Mehinovic, Lejla; Hasic, Azra; Kozaric, Mirza; Hukic, Mirsada; Marjanovic, Damir

2017-07-01

The main aim of this review is to summarize and discuss the current state of knowledge on chemical toxicity and radioactivity of depleted uranium (DU) and their effect on living systems and cell lines. This was done by presenting a summary of previous investigations conducted on different mammalian body systems and cell cultures in terms of potential changes caused by either chemical toxicity or radioactivity of DU. In addition, the authors aimed to point out the limitations of those studies and possible future directions. The majority of both in vitro and in vivo studies performed using animal models regarding possible effects caused by acute or chronic DU exposure has been reviewed. Furthermore, exposure time and dose, DU particle solubility, and uranium isotopes as factors affecting the extent of DU effects have been discussed. Special attention has been dedicated to chromosomal aberrations, DNA damage and DNA breaks, as well as micronuclei formation and epigenetic changes, as DU has recently been considered a possible causative factor of all these processes. Therefore, this approach might represent a novel area of study of DU-related irradiation effects on health. Since different studies offer contradictory results, the main aim of this review is to summarize and briefly discuss previously obtained results in order to identify the current opinion on DU toxicity and radioactivity effects in relation to exposure type and duration, as well as DU properties. Copyright © 2017 Elsevier Inc. All rights reserved.

Mission Need Statement: Idaho Spent Fuel Facility Project

Energy Technology Data Exchange (ETDEWEB)

Barbara Beller

2007-09-01

Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

EG and G Idaho environmental protection implementation plan

International Nuclear Information System (INIS)

Stump, R.C.

1989-11-01

This report describes the EG ampersand G Idaho strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.0 Additionally, this report is intended to supplement the Department of Energy -- Idaho Operations Office (DOE-ID) Environmental Protection Implementation Plan by detailing EG ampersand G Idaho Environmental Protection Program activities. This report describes the current status of the EG ampersand G Idaho Program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG ampersand G organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 3 figs., 1 tab

Sediment cores and chemistry for the Kootenai River White Sturgeon Habitat Restoration Project, Boundary County, Idaho

Science.gov (United States)

Barton, Gary J.; Weakland, Rhonda J.; Fosness, Ryan L.; Cox, Stephen E.; Williams, Marshall L.

2012-01-01

The Kootenai Tribe of Idaho, in cooperation with local, State, Federal, and Canadian agency co-managers and scientists, is assessing the feasibility of a Kootenai River habitat restoration project in Boundary County, Idaho. This project is oriented toward recovery of the endangered Kootenai River white sturgeon (Acipenser transmontanus) population, and simultaneously targets habitat-based recovery of other native river biota. Projects currently (2010) under consideration include modifying the channel and flood plain, installing in-stream structures, and creating wetlands to improve the physical and biological functions of the ecosystem. River restoration is a complex undertaking that requires a thorough understanding of the river. To assist in evaluating the feasibility of this endeavor, the U.S. Geological Survey collected and analyzed the physical and chemical nature of sediment cores collected at 24 locations in the river. Core depths ranged from 4.6 to 15.2 meters; 21 cores reached a depth of 15.2 meters. The sediment was screened for the presence of chemical constituents that could have harmful effects if released during restoration activities. The analysis shows that concentrations of harmful chemical constituents do not exceed guideline limits that were published by the U.S. Army Corps of Engineers in 2006.

Supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1992-01-01

This document reports on the status of supplemental investigations in support of environmental assessments by the Idaho INEL Oversight Program at the Idaho National Engineering Laboratory. Included is information on hydrology studies in wells open through large intervals, unsaturated zone contamination and transport processes, surface water-groundwater interactions, regional groundwater flow, and independent testing of air quality data

Allium -test as a tool for toxicity testing of environmental radioactive-chemical mixtures

International Nuclear Information System (INIS)

Oudalova, A A; Pyatkova, S V; Geras’kin, S A; Dikareva, N S

2017-01-01

Bioassay-based approaches have been propagated to assess toxicity of unknown mixtures of environmental contaminants, but it was rarely applied in cases of chemicals with radionuclides combinations. Two Allium -test studies were performed to assess environmental impact from potential sources of combined radioactive-chemical pollution. Study sites were located at nuclear waste storage facilities in European and in Far-Eastern parts of Russia. As environmental media under impact, waters from monitor wells and nearby water bodies were tested. Concentrations of some chemicals and radionuclides in the samples collected enhanced the permitted limits. Cytogenetic and cytotoxic effects were used as biological endpoints, namely, frequency and spectrum of chromosome aberrations and mitotic abnormalities in anatelophase cells as well as mitotic activity in Allium root tips. Sample points were revealed where waters have an enhanced mutagenic potential. The findings obtained could be used to optimize monitoring system and advance decision making on management and rehabilitation of industrial sites. The Allium -test could be recommended and applied as an effective tool for toxicity testing in case of combined contamination of environmental compartments with radionuclides and chemical compounds. (paper)

Decommissioning of the MTR-605 process water building at the Idaho National Engineering Laboratory. Final report

International Nuclear Information System (INIS)

Browder, J.H.; Wills, E.L.

1985-01-01

Decontamination and decommissioning (D and D) of the unused radioactively contaminated portions of the MTR-605 building at the Test Reactor Area of the Idaho National Engineering Laboratory has been completed; this final report describes the D and D project. The building is a two-story concrete structure that was used to house piping systems to channel and control coolant water flow for the Materials Testing Reactor (MTR), a 40 MW (thermal) light water test reactor that was operated from 1952 until 1970 and then deactivated. D and D project objectives were to reduce potential environmental and radioactive contamination hazards to levels as low a reasonably achievable. Primary tasks of the D and D project were: to remove contaminated piping (about 400 linear ft of 36- and 30-in.-dia stainless steel pipe) and valves from the primary coolant pipe tunnels, to remove a primary coolant pump and piping, and to remove the three 8-ft-dia by 25-ft-long evaporators from the building second floor

Hazardous chemical tracking system (HAZ-TRAC)

International Nuclear Information System (INIS)

Bramlette, J.D.; Ewart, S.M.; Jones, C.E.

1990-07-01

Westinghouse Idaho Nuclear Company, Inc. (WINCO) developed and implemented a computerized hazardous chemical tracking system, referred to as Haz-Trac, for use at the Idaho Chemical Processing Plant (ICPP). Haz-Trac is designed to provide a means to improve the accuracy and reliability of chemical information, which enhances the overall quality and safety of ICPP operations. The system tracks all chemicals and chemical components from the time they enter the ICPP until the chemical changes form, is used, or becomes a waste. The system runs on a Hewlett-Packard (HP) 3000 Series 70 computer. The system is written in COBOL and uses VIEW/3000, TurboIMAGE/DBMS 3000, OMNIDEX, and SPEEDWARE. The HP 3000 may be accessed throughout the ICPP, and from remote locations, using data communication lines. Haz-Trac went into production in October, 1989. Currently, over 1910 chemicals and chemical components are tracked on the system. More than 2500 personnel hours were saved during the first six months of operation. Cost savings have been realized by reducing the time needed to collect and compile reporting information, identifying and disposing of unneeded chemicals, and eliminating duplicate inventories. Haz-Trac maintains information required by the Superfund Amendment Reauthorization Act (SARA), the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the Occupational Safety and Health Administration (OSHA)

Hazardous chemical tracking system (HAZ-TRAC)

Energy Technology Data Exchange (ETDEWEB)

Bramlette, J D; Ewart, S M; Jones, C E

1990-07-01

Westinghouse Idaho Nuclear Company, Inc. (WINCO) developed and implemented a computerized hazardous chemical tracking system, referred to as Haz-Trac, for use at the Idaho Chemical Processing Plant (ICPP). Haz-Trac is designed to provide a means to improve the accuracy and reliability of chemical information, which enhances the overall quality and safety of ICPP operations. The system tracks all chemicals and chemical components from the time they enter the ICPP until the chemical changes form, is used, or becomes a waste. The system runs on a Hewlett-Packard (HP) 3000 Series 70 computer. The system is written in COBOL and uses VIEW/3000, TurboIMAGE/DBMS 3000, OMNIDEX, and SPEEDWARE. The HP 3000 may be accessed throughout the ICPP, and from remote locations, using data communication lines. Haz-Trac went into production in October, 1989. Currently, over 1910 chemicals and chemical components are tracked on the system. More than 2500 personnel hours were saved during the first six months of operation. Cost savings have been realized by reducing the time needed to collect and compile reporting information, identifying and disposing of unneeded chemicals, and eliminating duplicate inventories. Haz-Trac maintains information required by the Superfund Amendment Reauthorization Act (SARA), the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the Occupational Safety and Health Administration (OSHA).

77 FR 54557 - Eastern Idaho Resource Advisory Committee

Science.gov (United States)

2012-09-05

... DEPARTMENT OF AGRICULTURE Forest Service Eastern Idaho Resource Advisory Committee AGENCY: Forest Service, USDA. ACTION: Notice of meeting. SUMMARY: The Easern Idaho Resource Advisory Committee will meet... between 8 a.m. and 8 p.m., Eastern Standard Time, Monday through Friday. SUPPLEMENTARY INFORMATION: The...

Historical fuel reprocessing and HLW management in Idaho

International Nuclear Information System (INIS)

Knecht, D.A.; Staiger, M.D.; Christian, J.D.

1997-01-01

This article review some of the key decision points in the historical development of spent fuel reprocessing and waste management practices at the Idaho Chemical Processing Plant that have helped ICPP to successfully accomplish its mission safely and with minimal impact on the environment. Topics include ICPP reprocessing development; batch aluminum-uranium dissolution; continuous aluminum uranium dissolution; batch zirconium dissolution; batch stainless steel dissolution; semicontinuous zirconium dissolution with soluble poison; electrolytic dissolution of stainless steel-clad fuel; graphite-based rover fuel processing; fluorinel fuel processing; ICPP waste management consideration and design decisions; calcination technology development; ICPP calcination demonstration and hot operations; NWCF design, construction, and operation; HLW immobilization technology development. 80 refs., 4 figs

Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL

International Nuclear Information System (INIS)

1991-09-01

In part one of this document the Governing Documents and Definitions sections provide general guidelines and regulations applying to the handling of hazardous chemical wastes. The remaining sections provide details on how you can prepare your waste properly for transport and disposal. They are correlated with the steps you must take to properly prepare your waste for pickup. The purpose of the second part of this document is to provide the acceptance criteria for the transfer of radioactive and mixed waste to LBL's Hazardous Waste Handling Facility (HWHF). These guidelines describe how you, as a generator of radioactive or mixed waste, can meet LBL's acceptance criteria for radioactive and mixed waste

Mixed waste treatment options for wastes generated at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Garcia, E.C.

1991-01-01

The Idaho National Engineering Laboratory has generated mixed wastes (MWs) during its daily operations. MWs contain both radioactive and hazardous components, as defined by the Department of Energy and the Environmental Protection Agency. Treatment and disposal of stored MWs, as well as future generated MWs, are required to meet all regulations specified by the regulating agencies. This report reviews proven and emerging technologies that can treat MWs. It also provides a method for selection of the appropriate technology for treatment of a particular waste stream. The report selects for further consideration various treatments that can be used to treat MWs that fall under Land Disposal Restrictions. The selection methodology was used to arrive at these treatments. 63 refs., 7 figs., 23 tabs

Hot isostatic press waste option study report

International Nuclear Information System (INIS)

Russell, N.E.; Taylor, D.D.

1998-02-01

A Settlement Agreement between the Department of Energy and the State of Idaho mandates that all high-level radioactive waste now stored at the Idaho Chemical Processing Plant be treated so that it is ready to move out of Idaho for disposal by the target date of 2035. This study investigates the immobilization of all Idaho Chemical Processing Plant calcine, including calcined sodium bearing waste, via the process known as hot isostatic press, which produces compact solid waste forms by means of high temperature and pressure (1,050 C and 20,000 psi), as the treatment method for complying with the settlement agreement. The final waste product would be contained in stainless-steel canisters, the same type used at the Savannah River Site for vitrified waste, and stored at the Idaho National Engineering and Environmental Laboratory until a national geological repository becomes available for its disposal. The waste processing period is from 2013 through 2032, and disposal at the High Level Waste repository will probably begin sometime after 2065

Hot isostatic press waste option study report

Energy Technology Data Exchange (ETDEWEB)

Russell, N.E.; Taylor, D.D.

1998-02-01

A Settlement Agreement between the Department of Energy and the State of Idaho mandates that all high-level radioactive waste now stored at the Idaho Chemical Processing Plant be treated so that it is ready to move out of Idaho for disposal by the target date of 2035. This study investigates the immobilization of all Idaho Chemical Processing Plant calcine, including calcined sodium bearing waste, via the process known as hot isostatic press, which produces compact solid waste forms by means of high temperature and pressure (1,050 C and 20,000 psi), as the treatment method for complying with the settlement agreement. The final waste product would be contained in stainless-steel canisters, the same type used at the Savannah River Site for vitrified waste, and stored at the Idaho National Engineering and Environmental Laboratory until a national geological repository becomes available for its disposal. The waste processing period is from 2013 through 2032, and disposal at the High Level Waste repository will probably begin sometime after 2065.

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

McKenzie, Barbara J.; West, Stephanie G.; Jones, Olga G.; Kerr, Dorothy A.; Bieri, Rita A.; Sanderson, Nancy L.

1991-08-01

The purpose of the Safety and Health (S H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG G Idaho, Inc. (EG G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety.

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES ampersand H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES ampersand H/quality assurance programs was conducted

Tiger Team assessment of the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

1991-08-01

This report documents the Tiger Team Assessment of the Idaho National Engineering Laboratory (INEL) located in Idaho Falls, Idaho. INEL is a multiprogram, laboratory site of the US Department of Energy (DOE). Overall site management is provided by the DOE Field Office, Idaho; however, the DOE Field Office, Chicago has responsibility for the Argonne National Laboratory-West facilities and operations through the Argonne Area Office. In addition, the Idaho Branch Office of the Pittsburgh Naval Reactors Office has responsibility for the Naval Reactor Facility (NRF) at the INEL. The assessment included all DOE elements having ongoing program activities at the site except for the NRF. In addition, the Safety and Health Subteam did not review the Westinghouse Idaho Nuclear Company, Inc. facilities and operations. The Tiger Team Assessment was conducted from June 17 to August 2, 1991, under the auspices of the Office of Special Projects, Office of the Assistant Secretary for Environment, Safety and Health, Headquarters, DOE. The assessment was comprehensive, encompassing environmental, safety, and health (ES H) disciplines; management; and contractor and DOE self-assessments. Compliance with applicable federal, state, and local regulations; applicable DOE Orders; best management practices; and internal INEL site requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of the DOE and the site contractors management of ES H/quality assurance programs was conducted.

Tiger Team assessment of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1991-08-01

The purpose of the Safety and Health (S ampersand H) Subteam assessment was to determine the effectiveness of representative safety and health programs at the Idaho National Engineering Laboratory (INEL) site. Four Technical Safety Appraisal (TSA) Teams were assembled for this purpose by the US Department of Energy (DOE), Deputy Assistant Secretary for Safety and Quality Assurance, Office of Safety Appraisals (OSA). Team No. 1 reviewed EG ampersand G Idaho, Inc. (EG ampersand G Idaho) and the Department of Energy Field Office, Idaho (ID) Fire Department. Team No. 2 reviewed Argonne National Laboratory-West (ANL-W). Team No. 3 reviewed selected contractors at the INEL; specifically, Morrison Knudsen-Ferguson of Idaho Company (MK-FIC), Protection Technology of Idaho, Inc. (PTI), Radiological and Environmental Sciences Laboratory (RESL), and Rockwell-INEL. Team No. 4 provided an Occupational Safety and Health Act (OSHA)-type compliance sitewide assessment of INEL. The S ampersand H Subteam assessment was performed concurrently with assessments conducted by Environmental and Management Subteams. Performance was appraised in the following technical areas: Organization and Administration, Quality Verification, Operations, Maintenance, Training and Certification, Auxiliary Systems, Emergency Preparedness, Technical Support, Packaging and Transportation, Nuclear Criticality Safety, Security/Safety Interface, Experimental Activities, Site/Facility Safety Review, Radiological Protection, Personnel Protection, Worker Safety and Health (OSHA) Compliance, Fire Protection, Aviation Safety, Medical Services, and Firearms Safety

Environmental surveillance for the INEL Radioactive-Waste-Management complex. Annual report 1981

International Nuclear Information System (INIS)

Janke, D.H.; Zahn, T.P.

1982-09-01

The 1981 environmental surveillance report for the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory contains data and discussions about routine radiological monitoring of the atmospheric, hydrologic, and geologic environments of the RWMC. Additional discussions include results of routine monitoring of two surplus facilities, the Stationary Low-Power Reactor No. 1 Surplus Area and the Organic Moderated Reactor Experiment. Each area has produced localized effects on the environment, but containment is well within the INEL site boundary

Small mammal density and movement on the SL-1 disposal area, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Filipovich, M.A.; Keller, B.L.

1983-01-01

This study was initiated to examine the population composition, density and food habits of small mammals on a radioactive waste disposal area. Population parameters of small mammals were studied at 3-month intervals on and adjacent to the SL-1 radioactive waste disposal area (1.4 ha) and a 0.3 ha control area between August 1981 and February 1982 with mark-release methods. Both areas have crested wheatgrass (Agropyron cristatum) stands surrounded by sagebrush steppe. Species composition on the SL-1 and control area was similar to that found on the Subsurface Disposal Area at the Idaho National Engineering Laboratory. Considerable use by small mammals of the perimeter of the crested wheatgrass stands was found on both the SL-1 and control area. Additionally, deer mice (Peromyscus maniculatus) and Ord's kangaroo rats (Dipodomys ordii) that frequent the crested wheatgrass stands of the SL-1 and control area were often captured over 100 m from the crested wheatgrass stands. Thus, future research efforts will focus on examining the intensity of perimeter use and food habits of rodents residing on and adjacent to the SL-1. Results of this study will be used to evaluate ecological conditions that affect small mammal use of radioactive waste disposal areas

Idaho National Engineering Laboratory Waste Management Operations Roadmap Document

International Nuclear Information System (INIS)

Bullock, M.

1992-04-01

At the direction of the Department of Energy-Headquarters (DOE-HQ), the DOE Idaho Field Office (DOE-ID) is developing roadmaps for Environmental Restoration and Waste Management (ER ampersand WM) activities at Idaho National Engineering Laboratory (INEL). DOE-ID has convened a select group of contractor personnel from EG ampersand G Idaho, Inc. to assist DOE-ID personnel with the roadmapping project. This document is a report on the initial stages of the first phase of the INEL's roadmapping efforts

Removal of some Fission Products from Low Level Liquid Radioactive Waste by Chemical Precipitation liquid/Co-precipitation / Phosphate Coagulant

International Nuclear Information System (INIS)

Borai, E.H.; Attallah, M.F.; Hilal, M.A.; Abo-Aly, M.M.; Shehata, F.A.

2008-01-01

In Egypt radioactive waste has been generated from various uses of radioactive materials. Presence of cesium demonstrated a major problem from the removal point of view even by conventional and advanced technologies. Selective chemical precipitation has been oriented for removal of some fission products including 137 Cs from low level liquid radioactive waste (LLLRW). The aim of the present study was focused to investigate the effectiveness of various phosphate compounds that improved the precipitation process and hence the decontamination factor. The results showed that, maximum removal of 137 Cs reaching 46.4 % using di-sodium hydrogen phosphate as a selective coagulant. It was found that significant enhancement of co-precipitation of 137 Cs (62.5 %) was obtained due to presence of Nd 3+ in the LLLRW

Classification of radioactive waste

International Nuclear Information System (INIS)

1994-01-01

Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. To simplify their management, a number of schemes have evolved for classifying radioactive waste according to the physical, chemical and radiological properties of significance to those facilities managing this waste. These schemes have led to a variety of terminologies, differing from country to country and even between facilities in the same country. This situation makes it difficult for those concerned to communicate with one another regarding waste management practices. This document revises and updates earlier IAEA references on radioactive waste classification systems given in IAEA Technical Reports Series and Safety Series. Guidance regarding exemption of materials from regulatory control is consistent with IAEA Safety Series and the RADWASS documents published under IAEA Safety Series. 11 refs, 2 figs, 2 tab

Idaho Explosives Detection System

International Nuclear Information System (INIS)

Reber, Edward L.; Blackwood, Larry G.; Edwards, Andrew J.; Jewell, J. Keith; Rohde, Kenneth W.; Seabury, Edward H.; Klinger, Jeffery B.

2005-01-01

The Idaho Explosives Detection System was developed at the Idaho National Laboratory (INL) to respond to threats imposed by delivery trucks potentially carrying explosives into military bases. A full-scale prototype system has been built and is currently undergoing testing. The system consists of two racks, one on each side of a subject vehicle. Each rack includes a neutron generator and an array of NaI detectors. The two neutron generators are pulsed and synchronized. A laptop computer controls the entire system. The control software is easily operable by minimally trained staff. The system was developed to detect explosives in a medium size truck within a 5-min measurement time. System performance was successfully demonstrated with explosives at the INL in June 2004 and at Andrews Air Force Base in July 2004

Idaho Explosives Detection System

Energy Technology Data Exchange (ETDEWEB)

Reber, Edward L. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States)]. E-mail: reber@inel.gov; Blackwood, Larry G. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Edwards, Andrew J. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Jewell, J. Keith [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Rohde, Kenneth W. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Seabury, Edward H. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States); Klinger, Jeffery B. [Idaho National Laboratory, 2525 N. Freemont Ave., Idaho Falls, ID 83415-2114 (United States)

2005-12-15

The Idaho Explosives Detection System was developed at the Idaho National Laboratory (INL) to respond to threats imposed by delivery trucks potentially carrying explosives into military bases. A full-scale prototype system has been built and is currently undergoing testing. The system consists of two racks, one on each side of a subject vehicle. Each rack includes a neutron generator and an array of NaI detectors. The two neutron generators are pulsed and synchronized. A laptop computer controls the entire system. The control software is easily operable by minimally trained staff. The system was developed to detect explosives in a medium size truck within a 5-min measurement time. System performance was successfully demonstrated with explosives at the INL in June 2004 and at Andrews Air Force Base in July 2004.

Managing low-level radioactive waste in Massachusetts. Final report

International Nuclear Information System (INIS)

Bander, S.R.; Goldstein, M.E.

1983-12-01

As one of the country's largest generators of low-level radioactive waste, Massachusetts has begun independently seeking solutions to the questions surrounding low-level waste management issues. The Massachusetts Department of Public Health, Radiation Control Program, obtained funding from the U.S. Department ofEnergy through EG and G, Idaho, Inc. to develop a low-level waste management strategy for the Commonwealth. The Working Group was made up of individuals from various waste generating industries, environmental and public interest groups, medical and academic institutions, and affected state agencies. This final report document contains the following staff project reports: Proposed Low-Level Radioactive Waste Management Plan for The Commonwealth of Massachusetts, February 1983 and Low-Level Radioactive Waste Management in Massachusetts - Actions to be Considered for Implementation in 1984-1986, December 1983. These two staff reports represent the completion of the Massachusetts Low-Level Radioactive Waste Management Project. The first report provides some of the background material to the issues and some of the alternative courses of action which can be considered by state policy-makers. The second report provides the next phase in the process by delineating specific steps which may be taken before 1986 in order to address the low-level waste problem, and the estimated amount of time needed to complete each step

Analysis of determination modalities concerning the exposure and emission limits values of chemical and radioactive substances; Analyse des modalites de fixation des valeurs limites d'exposition et d'emission pour les substances chimiques et radioactives

Energy Technology Data Exchange (ETDEWEB)

Schieber, C.; Schneider, T

2002-08-01

This document presents the generic approach adopted by various organizations for the determination of the public exposure limits values to chemical and radioactive substances and for the determination of limits values of chemical products emissions by some installations. (A.L.B.)

Idaho National Laboratory Site Pollution Prevention Plan

International Nuclear Information System (INIS)

E. D. Sellers

2007-01-01

It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively

Idaho National Laboratory Site Pollution Prevention Plan

Energy Technology Data Exchange (ETDEWEB)

E. D. Sellers

2007-03-01

It is the policy of the Department of Energy (DOE) that pollution prevention and sustainable environmental stewardship will be integrated into DOE operations as a good business practice to reduce environmental hazards, protect environmental resources, avoid pollution control costs, and improve operational efficiency and mission sustainability. In furtherance of this policy, DOE established five strategic, performance-based Pollution Prevention (P2) and Sustainable Environmental Stewardship goals and included them as an attachment to DOE O 450.1, Environmental Protection Program. These goals and accompanying strategies are to be implemented by DOE sites through the integration of Pollution Prevention into each site's Environmental Management System (EMS). This document presents a P2 and Sustainability Program and corresponding plan pursuant to DOE Order 450.1 and DOE O 435.1, Radioactive Waste Management. This plan is also required by the state of Idaho, pursuant to the Resource Conservation and Recovery Act (RCRA) partial permit. The objective of this document is to describe the Idaho National Laboratory (INL) Site P2 and Sustainability Program. The purpose of the program is to decrease the environmental footprint of the INL Site while providing enhanced support of its mission. The success of the program is dependent on financial and management support. The signatures on the previous page indicate INL, ICP, and AMWTP Contractor management support and dedication to the program. P2 requirements have been integrated into working procedures to ensure an effective EMS as part of an Integrated Safety Management System (ISMS). This plan focuses on programmatic functions which include environmentally preferable procurement, sustainable design, P2 and Sustainability awareness, waste generation and reduction, source reduction and recycling, energy management, and pollution prevention opportunity assessments. The INL Site P2 and Sustainability Program is administratively

New Nutrition Standards for Idaho School Meals. Nourishing News. Volume 4, Issue 1

Science.gov (United States)

Idaho State Department of Education, 2009

2009-01-01

Idaho Child Nutrition Programs (CNP) released the New Nutrition Standards for Idaho School Meals in January 2009 with the recommendation that all School Food Authorities fully implement the New Nutrition Standards for Idaho School Meals into their programs starting August 2009. Along with the release of the New Nutrition Standards for Idaho School…

Ergonomic assessments of three Idaho National Engineering Laboratory cafeterias

Energy Technology Data Exchange (ETDEWEB)

Ostrom, L.T.; Romero, H.A.; Gilbert, B.G.; Wilhelmsen, C.A.

1993-01-01

The Idaho National Engineering Laboratory is a Department of Energy facility that performs a variety of engineering and research projects. EG G Idaho is the prime contractor for the laboratory and, as such, performs the support functions in addition to technical, research, and development functions. As a part of the EG G Idaho Industrial Hygiene Initiative, ergonomic assessments were conducted at three Idaho National Engineering Laboratory Cafeterias. The purposes of the assessments were to determine whether ergonomic problems existed in the work places and, if so, to make recommendations to improve the work place and task designs. The study showed there were ergonomic problems in all three cafeterias assessed. The primary ergonomic stresses observed included wrist and shoulder stress in the dish washing task, postural stress in the dish washing and food preparation tasks, and back stress in the food handling tasks.

Ergonomic assessments of three Idaho National Engineering Laboratory cafeterias

Energy Technology Data Exchange (ETDEWEB)

Ostrom, L.T.; Romero, H.A.; Gilbert, B.G.; Wilhelmsen, C.A.

1993-05-01

The Idaho National Engineering Laboratory is a Department of Energy facility that performs a variety of engineering and research projects. EG&G Idaho is the prime contractor for the laboratory and, as such, performs the support functions in addition to technical, research, and development functions. As a part of the EG&G Idaho Industrial Hygiene Initiative, ergonomic assessments were conducted at three Idaho National Engineering Laboratory Cafeterias. The purposes of the assessments were to determine whether ergonomic problems existed in the work places and, if so, to make recommendations to improve the work place and task designs. The study showed there were ergonomic problems in all three cafeterias assessed. The primary ergonomic stresses observed included wrist and shoulder stress in the dish washing task, postural stress in the dish washing and food preparation tasks, and back stress in the food handling tasks.

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

Petrophysical characteristics of basalt in the vadose zone, Idaho National Engineering Laboratory, Eastern Snake River Plain, Idaho

International Nuclear Information System (INIS)

Knutson, C.F.; Harrison, W.E.; Smith, R.P.

1989-01-01

We have used a core characterization system to measure bulk densities, porosities, and permeabilities of basalt lavas from the vadose zone at the Idaho National Engineering Laboratory (INEL). At the INEL, basalt lava flows with intercalated alluvial, aeolian, and lacustrine sediments extend to depths of one kilometer or more. Individual lava flows are generally less than 15 meters thick and commonly have vesicular tops and bottoms with massive basalt in their interiors. Petrophysical characterization is essential to an understanding of fluid movement in the vadose zone and in the saturated zone. Many hundreds of closely spaced permeability/porosity/bulk density measurements have defined the variability of these parameters within and between individual basalt flows. Based on geological logging and porosity/permeability measurements made on many hundred feet of core, we feel that a rather sophisticated and rigorous logging program is necessary to characterize these complex and highly variable basaltic flow units. This paper endeavors to provide a petrophysical/geological conceptual model of the Snake River Plain basalts from the vadose zone under the Radioactive Waste Management Complex area at the INEL. We hope that this model will aid in subsequent geotechnical logging in this portion of the Eastern Snake River Plain. 8 refs., 14 figs., 2 tabs

DPC loading feasibility study report

International Nuclear Information System (INIS)

Dafoe, R.E.; Lopez, D.A.; Williams, K.L.

1997-11-01

Disposal of radioactive wastes now stored at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory is mandated under a ''Settlement Agreement'' between the Department of Energy and the State of Idaho. This study investigates the feasibility of using the Dry Transfer Cell facility to package waste into Dual Purpose Canisters for interim storage at the adjacent Dry Storage System comprised of an interim storage pad with NUHOMS reg-sign storage modules. The wastes would then be road-ready for eventual disposal in a permanent repository. The operating period for these activities is expected to be from 2015 to 2035

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

International Nuclear Information System (INIS)

1994-09-01

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG ampersand G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG&G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report.

Idaho Safety Manual.

Science.gov (United States)

Idaho State Dept. of Education, Boise. Div. of Vocational Education.

This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

Logging utilization in Idaho: Current and past trends

Science.gov (United States)

Eric A. Simmons; Todd A. Morgan; Erik C. Berg; Stanley J. Zarnoch; Steven W. Hayes; Mike T. Thompson

2014-01-01

A study of commercial timber-harvesting activities in Idaho was conducted during 2008 and 2011 to characterize current tree utilization, logging operations, and changes from previous Idaho logging utilization studies. A two-stage simple random sampling design was used to select sites and felled trees for measurement within active logging sites. Thirty-three logging...

A comparative evaluation of conceptual models for the Snake River Plain aquifer at the Idaho Chemical Processing Plant, INEL

International Nuclear Information System (INIS)

Prahl, C.J.

1992-01-01

Geologic and hydrologic data collected by the United States Geological Survey (USGS) are used to evaluate the existing ground water monitoring well network completed in the upper portion of the Snake River Plain aquifer (SRPA) beneath the Idaho Chemical Processing Plant (ICPP). The USGS data analyzed and compared in this study include: (a) lithologic, geophysical, and stratigraphic information, including the conceptual geologic models intrawell, ground water flow measurement (Tracejector tests) and (c) dedicated, submersible, sampling group elevations. Qualitative evaluation of these data indicate that the upper portion of the SRPA is both heterogeneous and anisotropic at the scale of the ICPP monitoring well network. Tracejector test results indicate that the hydraulic interconnection and spatial configuration of water-producing zones is extremely complex within the upper portion of the SRPA. The majority of ICPP monitoring wells currently are equipped to sample ground water only the upper lithostratigraphic intervals of the SRPA, primarily basalt flow groups E, EF, and F. Depth-specific hydrogeochemical sampling and analysis are necessary to determine if ground water quality varies significantly between the various lithostratigraphic units adjacent to individual sampling pumps

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

Energy Technology Data Exchange (ETDEWEB)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

International Nuclear Information System (INIS)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

Idaho's forest products industry and timber harvest, 2011

Science.gov (United States)

Eric A. Simmons; Steven W. Hayes; Todd A. Morgan; Charles E. Keegan; Chris Witt

2014-01-01

This report traces the flow of Idaho’s 2011 timber harvest through the primary industries; provides a description of the structure, capacity, and condition of Idaho’s industry; and quantifies volumes and uses of wood fiber. Historical wood products industry trends are discussed, as well as changes in harvest, production, employment, and sales.

EG and G Idaho Environmental Protection Implementation Plan (1990)

Energy Technology Data Exchange (ETDEWEB)

Wickham, L.E.

1990-11-01

This report describes the EG G Idaho strategy for implementation of the Department of Energy (DOE) Order 5400.1 (a DOE-Headquarters directive establishing environmental protection program requirements, authorities, and responsibilities). Preparation of this Environmental Protection Implementation Plan is a requirement of DOE Order 5400.1. Additionally, this report is intended to supplement the Department of Energy--Idaho Operations Office (DOE-ID) Environmental Protection Implementation Plan by detailing EG G Idaho Environmental Protection Program activities. This report describes the current status of the EG G Idaho program, and the strategies for enhancing, as necessary, the current program to meet the requirements of DOE Order 5400.1. Aspects of the Environmental Protection Program included in this report are the assignment of responsibilities to specific EG G organizations, a schedule for completion of enhancements, if necessary, and requirements for documentation and reporting. 4 figs., 1 tab.

Idaho's Energy Options

Energy Technology Data Exchange (ETDEWEB)

Robert M. Neilson

2006-03-01

This report, developed by the Idaho National Laboratory, is provided as an introduction to and an update of the status of technologies for the generation and use of energy. Its purpose is to provide information useful for identifying and evaluating Idaho’s energy options, and for developing and implementing Idaho’s energy direction and policies.

The Status of Physical Activity Opportunities in Idaho Schools

Science.gov (United States)

Berei, Catherine P.; Karp, Grace Goc; Kauffman, Katie

2018-01-01

Recent literature indicates that low percentages of Idaho adolescents report being physically active on a daily basis. Research examines school PA, however, little focuses on Comprehensive School Physical Activity Programs (CSPAPs) from the perspectives of physical educators. This study explored Idaho physical educators' perceptions and…

Method and techniques of radioactive waste treatment

International Nuclear Information System (INIS)

Ghafar, M.; Aasi, N.

2002-04-01

This study illustrates the characterization of radioactive wastes produced by the application of radioisotopes in industry and research. The treatment methods of such radioactive wastes, chemical co-precipitation and ion exchange depending on the technical state of radioactive waste management facility in Syria were described. The disposal of conditioned radioactive wastes, in a safe way, has been discussed including the disposal of the radioactive sources. The characterizations of the repository to stock conditioned radioactive wastes were mentioned. (author)

New facility for processing and storage of radioactive and toxic chemical waste

International Nuclear Information System (INIS)

Gallagher, F.E. III

1976-01-01

A new facility for the processing and storage of radioactive and toxic chemical waste is described. The facility is located in the science and engineering complex of the Santa Barbara campus of the University of California, near the Pacific Ocean. It is designed to provide a safe and secure processing and storage area for hazardous wastes, while meeting the high aesthetic standards and ecological requirements of campus and community regulatory boards. The ventilation system and fire prevention features will be described in detail. During the design phase, a small laboratory was added to provide an area for the radiation protection and industrial hygiene programs. Operational experience with this new facility is discussed

Idaho National Laboratory Cultural Resource Management Plan

Energy Technology Data Exchange (ETDEWEB)

Lowrey, Diana Lee

2009-02-01

As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at the Idaho National Laboratory. This Laboratory, which is located in southeastern Idaho, is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable; bear valuable physical and intangible legacies; and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through annual reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of

Idaho National Laboratory Cultural Resource Management Plan

Energy Technology Data Exchange (ETDEWEB)

Lowrey, Diana Lee

2011-02-01

As a federal agency, the U.S. Department of Energy has been directed by Congress, the U.S. president, and the American public to provide leadership in the preservation of prehistoric, historic, and other cultural resources on the lands it administers. This mandate to preserve cultural resources in a spirit of stewardship for the future is outlined in various federal preservation laws, regulations, and guidelines such as the National Historic Preservation Act, the Archaeological Resources Protection Act, and the National Environmental Policy Act. The purpose of this Cultural Resource Management Plan is to describe how the Department of Energy, Idaho Operations Office will meet these responsibilities at the Idaho National Laboratory. This Laboratory, which is located in southeastern Idaho, is home to a wide variety of important cultural resources representing at least 13,500 years of human occupation in the southeastern Idaho area. These resources are nonrenewable; bear valuable physical and intangible legacies; and yield important information about the past, present, and perhaps the future. There are special challenges associated with balancing the preservation of these sites with the management and ongoing operation of an active scientific laboratory. The Department of Energy, Idaho Operations Office is committed to a cultural resource management program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative mandates. This document is designed for multiple uses and is intended to be flexible and responsive to future changes in law or mission. Document flexibility and responsiveness will be assured through annual reviews and as-needed updates. Document content includes summaries of Laboratory cultural resource philosophy and overall Department of Energy policy; brief contextual overviews of Laboratory missions, environment, and cultural history; and an overview of cultural resource management practices. A series of

Combustible radioactive waste treatment by incineration and chemical digestion

International Nuclear Information System (INIS)

Stretz, L.A.; Crippen, M.D.; Allen, C.R.

1980-01-01

A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste

Spent fuel storage cask testing and operational experience at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Eslinger, L.E.; Schmitt, R.C.

1989-01-01

Spent-fuel storage cask research, development, and demonstration activities are being performed for the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) as a part of the storage cask testing program. The cask testing program at federal sites and other locations supports the Nuclear Waste Policy Act (NWPA) and DOE objectives for cooperative demonstrations with the cask vendors and utilities for development of at-reactor dry cask storage capabilities for spent nuclear fuel assemblies. One research and development program for the storage cask performance testing of metal storage cask was initiated through a cooperative agreement between Virginia Power and DOE in 1984. The performance testing was conducted for the DOE and the Electric Power Research Institute by the Pacific Northwest laboratory, operated for DOE by Battelle Memorial Institute, and the Idaho National Engineering Laboratory (INEL), operated for DOE by EG ampersand G Idaho, Inc. In 1988 a cooperative agreement was entered into by DOE with Pacific Sierra Nuclear Associates (PSN) for performance testing of the PSN concrete Ventilated Storage Cask. Another closely related activity involving INEL is a transportable storage cask project identified as the Nuclear Fuel Services Spent-Fuel Shipping/Storage Cask Demonstration Project. The purpose of this project is to demonstrate the feasibility of packing, transporting, and storing commercial spent fuel in dual-purpose transport/storage casks

Distributed Wind Energy in Idaho

Energy Technology Data Exchange (ETDEWEB)

Gardner, John [Boise State Univ., ID (United States); Johnson, Kathryn [Colorado School of Mines, Golden, CO (United States); Haynes, Todd [Boise State Univ., ID (United States); Seifert, Gary [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2009-01-31

This project is a research and development program aimed at furthering distributed wind technology. In particular, this project addresses some of the barriers to distributed wind energy utilization in Idaho.

Chemical Gel for Surface Decontamination

International Nuclear Information System (INIS)

Jung, Chong Hun; Moon, J. K.; Won, H. J.; Lee, K. W.; Kim, C. K.

2010-01-01

Many chemical decontamination processes operate by immersing components in aggressive chemical solutions. In these applications chemical decontamination technique produce large amounts of radioactive liquid waste. Therefore it is necessary to develop processes using chemical gels instead of chemical solutions, to avoid the well-known disadvantages of chemical decontamination techniques while retaining their high efficiency. Chemical gels decontamination process consists of applying the gel by spraying it onto the surface of large area components (floors, walls, etc) to be decontaminated. The gel adheres to any vertical or complex surface due to their thixotropic properties and operates by dissolving the radioactive deposit, along with a thin layer of the gel support, so that the radioactivity trapped at the surface can be removed. Important aspects of the gels are that small quantities can be used and they show thixitropic properties : liquid during spraying, and solid when stationary, allowing for strong adherence to surfaces. This work investigates the decontamination behaviors of organic-based chemical gel for SS 304 metallic surfaces contaminated with radioactive materials

Cost-Effectiveness Analysis of the Residential Provisions of the 2015 IECC for Idaho

Energy Technology Data Exchange (ETDEWEB)

Mendon, Vrushali V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhao, Mingjie [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Taylor, Zachary T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Poehlman, Eric A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-02-15

The 2015 IECC provides cost-effective savings for residential buildings in Idaho. Moving to the 2015 IECC from the 2015 Idaho State Code base code is cost-effective for residential buildings in all climate zones in Idaho.

A conceptual chemical solidification/stabilization system to remediate radioactive raffinate sludge

International Nuclear Information System (INIS)

Carpenter, D.J.; Ansted, J.P.; Foldyna, J.T.

1994-01-01

Past operations at the U.S. Department of Energy's (DOE) Weldon Spring, Missouri, Superfund Site included the manufacture of nitroaromatic-based munitions and the production of uranium and thorium metal from ore concentrates. These operations generated a large quantity of diverse contaminated waste media including raffinate sludge, soil, sediment, and building debris. These various waste media are contaminated with varying amounts of radionuclides nitroaromatics, metals, metalloids, non-metals, polychlorinated biphenyls (PCBs) and asbestos. The volumes and diversity of contaminants and waste media pose significant challenges in identifying applicable remedial technologies, particularly for the excavation and treatment of the water-rich raffinate sludge. This paper presents the results of comprehensive efforts to develop a conceptual chemical solidification/stabilization (CSS) system to treat a variety of waste media. The emphasis of this paper is the treatment of a water-rich refractory raffinate sludge and site contaminated soils both radioactive and nonradioactive. The conceptual system design includes raffinate sludge excavation, dewatering, and CSS processing (reagent selection and formulation, reagent and waste storage and metering, and product mixing). Many innovations were incorporated into the design, producing a system that can process the various waste types. Additionally, the radioactive and hazardous constituents are sufficiently immobilized to allow the secured disposal in a waste cell of the treated product. The conceptual CSS system can also produce a variety of treated product types, ranging from a monolithic form to a compactible soil-like medium. The advantages of this system flexibility are also presented

Separation technologies for the treatment of Idaho National Engineering Laboratory wastes

Energy Technology Data Exchange (ETDEWEB)

Todd, T.A. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-10-01

Currently about 6.8 million L of acidic, radioactive liquid waste that is not amenable to calcination, and about 3800 m{sup 3} of calcine exist at the ICPP. Legal drivers (court orders) and agreements between the state of Idaho, the U.S. Navy, and DOE exist that obligate INEL to develop, demonstrate, and implement technologies for treatment and interim storage of the radioactive liquid and calcine wastes. Per these agreements, all tank waste must be removed from the underground liquid storage tanks by the year 2012, and high-level radioactive waste must be treated and removed from INEL by 2035. Separation of the radionuclides from the wastes, followed by immobilization of the high-activity and low-activity fractions in glass and grout, respectively, is the approach preferred by INEL. Technologies to remove actinides (U, Np, Pu, and Am), Cs, Sr, and possibly Tc from highly acidic solutions are required to process INEL wastes. Decontamination of the wastes to NRC Class A low-level waste (LLW) is planned. Separation and isolation of Resource Conservation and Recovery Act (RCRA) metals (Hg, Pb, Cd, and Cr) from the highly radioactive waste streams may also be required. Remediation efforts will begin in FY 1997 to remove volatile organic compounds (VOCs) and radionuclides (Cs and Sr) from groundwater located at the Test Area North facility at INEL. A plume of VOCs and radionuclides has spread from the former TSF-05 injection well, and a Comprehensive Environmental Response, Conservation, and Liability Act (CERCLA) remediation action is under way. A Record of Decision was signed in August 1995 that commits INEL to remediate the plume from TSF-05. Removal of Sr and Cs from the groundwater using commercially available ion-exchange resins has been unsuccessful at meeting maximum contaminant levels, which are 119 pCi/L and 8 pCi/L for Cs and Sr, respectively. Cesium and Sr are the major contaminants that must be removed from the groundwater.

Idaho National Engineering Laboratory installation roadmap assumptions document

International Nuclear Information System (INIS)

1993-05-01

This document is a composite of roadmap assumptions developed for the Idaho National Engineering Laboratory (INEL) by the US Department of Energy Idaho Field Office and subcontractor personnel as a key element in the implementation of the Roadmap Methodology for the INEL Site. The development and identification of these assumptions in an important factor in planning basis development and establishes the planning baseline for all subsequent roadmap analysis at the INEL

Idaho Operations Office: Technology summary, June 1994

International Nuclear Information System (INIS)

1994-06-01

This document has been prepared by the Department of Energy's (DOE) Environmental Management (EM) Office of Technology Development (OTD) in order to highlight research, development, demonstration, testing, and evaluation (RDDT ampersand E) activities funded through the Idaho Operations Office. Technologies and processes described have the potential to enhance DOE's cleanup and waste management efforts, as well as improve US industry's competitiveness in global environmental markets. OTD programs are designed to make new, innovative, and more cost-effective technologies available for transfer to DOE environmental restoration and waste management end-users. Projects are demonstrated, tested, and evaluated to produce solutions to current problems. Transition of technologies into more advanced stages of development is based upon technological, regulatory, economic, and institutional criteria. New technologies are made available for use in eliminating radioactive, hazardous, and other wastes in compliance with regulatory mandates. The primary goal is to protect human health and prevent further contamination. OTD's technology development programs address three major problem areas: (1) groundwater and soils cleanup; (2) waste retrieval and processing; and (3) pollution prevention. These problems are not unique to DOE, but are associated with other Federal agency and industry sites as well. Thus, technical solutions developed within OTD programs will benefit DOE, and should have direct applications in outside markets

Idaho Operations Office: Technology summary, June 1994

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This document has been prepared by the Department of Energy`s (DOE) Environmental Management (EM) Office of Technology Development (OTD) in order to highlight research, development, demonstration, testing, and evaluation (RDDT&E) activities funded through the Idaho Operations Office. Technologies and processes described have the potential to enhance DOE`s cleanup and waste management efforts, as well as improve US industry`s competitiveness in global environmental markets. OTD programs are designed to make new, innovative, and more cost-effective technologies available for transfer to DOE environmental restoration and waste management end-users. Projects are demonstrated, tested, and evaluated to produce solutions to current problems. Transition of technologies into more advanced stages of development is based upon technological, regulatory, economic, and institutional criteria. New technologies are made available for use in eliminating radioactive, hazardous, and other wastes in compliance with regulatory mandates. The primary goal is to protect human health and prevent further contamination. OTD`s technology development programs address three major problem areas: (1) groundwater and soils cleanup; (2) waste retrieval and processing; and (3) pollution prevention. These problems are not unique to DOE, but are associated with other Federal agency and industry sites as well. Thus, technical solutions developed within OTD programs will benefit DOE, and should have direct applications in outside markets.

Using proven, cost-effective chemical stabilization to remediate radioactive and heavy metal contaminated sites

International Nuclear Information System (INIS)

Jensen, R.; Sogue, A.

1999-01-01

Rocky Mountain Remediation Services, L.L.C. (RMRS) has deployed a cost-effective metals stabilization method which can be used to reduce the cost of remediation projects where radioactivity and heavy metals are the contaminants of concern. The Envirobond TM process employs the use of a proprietary chemical process to stabilize metals in many waste forms, and provides an excellent binding system that can easily be compacted to reduce the waste into a shippable brick called Envirobric TM . The advantages of using chemical stabilization are: (1) Low cost, due to the simplicity of the process design and inexpensive reagents. (2) Chemical stabilization is easily deployed in field applications, which limit the amount of shielding and other protective measures. (3) The process does not add volume and bulk to the treated waste; after treatment the materials may be able to remain on-site, or if transportation and disposal is required the cost will be reduced due to lower volumes. (4) No secondary waste. The simplicity of this process creates a safe environment while treating the residues, and the long-term effectiveness of this type of chemical stabilization lowers the risk of future release of hazardous elements associated with the residues. (author)

Pyrochemical separation of radioactive components from inert materials in ICPP high-level calcined waste

International Nuclear Information System (INIS)

Del Debbio, J.A.; Nelson, L.O.; Todd, T.A.

1995-05-01

Since 1963, calcination of aqueous wastes from reprocessing of DOE-owned spent nuclear fuels has resulted in the accumulation of approximately 3800 m 3 of high-level waste (HLW) at the Idaho Chemical Processing Plant (ICPP). The waste is in the form of a granular solid called calcine and is stored on site in stainless steel bins which are encased in concrete. Due to the leachability of 137 Cs and 90 Sr and possibly other radioactive components, the calcine is not suitable for final disposal. Hence, a process to immobilize calcine in glass is being developed. Since radioactive components represent less than 1 wt % of the calcine, separation of actinides and fission products from inert components is being considered to reduce the volume of HLW requiring final disposal. Current estimates indicate that compared to direct vitrification, a volume reduction factor of 10 could result in significant cost savings. Aqueous processes, which involve calcine dissolution in nitric acid followed by separation of actinide and fission products by solvent extraction and ion exchange methods, are being developed. Pyrochemical separation methods, which generate small volumes of aqueous wastes and do not require calcine dissolution, have been evaluated as alternatives to aqueous processes. This report describes three proposed pyrochemical flowsheets and presents the results of experimental studies conducted to evaluate their feasibility. The information presented is a consolidation of three reports, which should be consulted for experimental details

Comparative analysis of DOE Order 5820.2A, NRC, and EPA radioactive and mixed waste management requirements

International Nuclear Information System (INIS)

1991-07-01

As directed by DOE-Headquarters and DOE-Idaho, the Radioactive Waste Technical Support Program (TSP) drafted an analysis of DOE Order 5820. 2A on ''Radioactive Waste Management'' to develop guidelines and criteria for revising the Order. This comparative matrix is a follow up to the earlier analysis. This matrix comparing the requirements of DOE Order 5820.2A with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) regulations was prepared at the request of EM-30. The matrix compares DOE Order 5820.2A with the following: NRC regulations in 10 CFR Part 61 on ''Licensing Requirements for Land Disposal of Radioactive Waste''; NRC regulations in 10 CFR Part 60 on ''Disposal of High-Level Radioactive Waste in Geologic Repositories''; EPA regulations in 40 CFR Part 191 on ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste''; EPA regulations in 40 FR Part 192 on ''Health and Environmental Protection Standards for Uranium and Thorium Mill Tailing''; and EPA regulations under the Resource Conservation and Recovery Act

Chemical reactivity of precursor materials during synthesis of glasses used for conditioning high-level radioactive waste: Experiments and models

International Nuclear Information System (INIS)

Monteiro, A.

2012-01-01

The glass used to store high-level radioactive waste is produced by reaction of a solid waste residue and a glassy precursor (glass frit). The waste residue is first dried and calcined (to lose water and nitrogen respectively), then mixed with the glass frit to enable vitrification at high temperature. In order to obtain a good quality glass of constant composition upon cooling, the chemical reactions between the solid precursors must be complete while in the liquid state, to enable incorporation of the radioactive elements into the glassy matrix. The physical and chemical conditions during glass synthesis (e.g. temperature, relative proportions of frit and calcine, amount of radioactive charge) are typically empirically adjusted to obtain a satisfactory final product. The aim of this work is to provide new insights into the chemical and physical interactions that take place during vitrification and to provide data for a mathematical model that has been developed to simulate the chemical reactions. The consequences of the different chemical reactions that involve solid, liquid and gaseous phases are described (thermal effects, changes in crystal morphology and composition, variations in melt properties and structure). In a first series of experiments, a simplified analogue of the calcine (NaNO 3 -Al 2 O 3 ± MoO 3 /Nd 2 O 3 ) has been studied. In a second series of experiments, the simplified calcines have been reacted with a simplified glass frit (SiO 2 -Na 2 O-B 2 O 3 -Al 2 O 3 ) at high temperature. The results show that crystallization of the calcine may take place before interaction with the glass frit, but that the reactivity with the glass at high temperature is a function of the nature and stoichiometry of the crystalline phases which form at low temperature. The results also highlight how the mixing of the starting materials, the physical properties of the frit (viscosity, glass transition temperature) and the Na 2 O/Al 2 O 3 of the calcine but also its

Radioactive sedimentary deposits concerning the coasts of the Camargue

International Nuclear Information System (INIS)

2000-01-01

CRII-RAD has detected abnormal levels of radioactivity on some beaches situated near the Espiguette lighthouse in the south-east coast of France. This document presents the in-situ measurements performed by IPSN. These results confirm a relevant increase of gamma radiation in sedimentary deposits. Chemical analyses have shown that this radioactivity is due to potassium 40 and radionuclides from thorium and uranium series. There is no doubt about the natural origin of this radioactivity but thorough geo-chemical studies are necessary to see whether these radioactive sands are a consequence of nearby industrial activities concerning ore dressing. (A.C.)

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

International Nuclear Information System (INIS)

Connolly, M.J.; Sayer, D.L.

1993-11-01

EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

Environmental radioactivity and chemical composition of different types of bee honeys produced at in-house area, egypt

International Nuclear Information System (INIS)

Ramadan, A.B.

2005-01-01

Environmental radioactivity and chemical composition of bee honey varies with the surrounding environment (major floral and soil contamination), which reflects the nutritional value of honey. 23SU, 232Th, 40K, >37Cs, major elements Na, K, Mg and Cl and trace elements Mn, Fe, Zn, F, I, Cu, Co, Ni and Sr as well as toxic elements Cd and Pb -were all determined in different types of bee honey, which include non-floral honey with artificial feeding (syrup-feed honey) and mono-floral honeys (clover honey or sesame honey or orange honey). These elements were also determined in the bee feeds, which include flowers (clover, sesame and orange) and syrup. The results revealed that of all types of honeys and syrup-feed honey exhibited higher natural radioactivity and higher concentrations ofNa, K, Mg, Cl, oMn, Fe, Co, Cd and Pb than in the other honeys. Orange honey contained the lowest natural radioactivity and element concentrations. Clover honey had the lowest toxic element Cd and Pb concentrations (0.02 and 4.2/xg/g, respectively) while sesame honey contained the highest levels of Cd and F (0.7 and 12.9 /ig/g, respectively). Statistical analysis revealed significant correlation between honey and the feed (R= 0.745 to 0.921). Environmental radioactivity and element concentrations in the honey under study were in the safety baseline levels for human consumption

Idaho National Laboratory FY12 Greenhouse Gas Report

Energy Technology Data Exchange (ETDEWEB)

Kimberly Frerichs

2013-03-01

A greenhouse gas (GHG) inventory is a systematic approach to account for the production and release of certain gases generated by an institution from various emission sources. The gases of interest are those that climate science has identified as related to anthropogenic global climate change. This document presents an inventory of GHGs generated during Fiscal Year (FY) 2012 by Idaho National Laboratory (INL), a Department of Energy (DOE) sponsored entity, located in southeastern Idaho.

Geochemistry Sampling for Traditional and Multicomponent Equilibrium Geothermometry in Southeast Idaho

International Nuclear Information System (INIS)

Cannon, Cody; Dobson, Patrick; Conrad, Mark

2014-01-01

The Eastern Snake River Plain (ESRP) is an area of high regional heat flux due the movement of the North American Plate over the Yellowstone Hotspot beginning ca.16 Ma. Temperature gradients between 45-60 °C/km (up to double the global average) have been calculated from deep wells that penetrate the upper aquifer system (Blackwell 1989). Despite the high geothermal potential, thermal signatures from hot springs and wells are effectively masked by the rapid flow of cold groundwater through the highly permeable basalts of the Eastern Snake River Plain aquifer (ESRPA) (up to 500+ m thick). This preliminary study is part of an effort to more accurately predict temperatures of the ESRP deep thermal reservoir while accounting for the effects of the prolific cold water aquifer system above. This study combines the use of traditional geothermometry, mixing models, and a multicomponent equilibrium geothermometry (MEG) tool to investigate the geothermal potential of the ESRP. In March, 2014, a collaborative team including members of the University of Idaho, the Idaho National Laboratory, and the Lawrence Berkeley National Laboratory collected 14 thermal water samples from and adjacent to the Eastern Snake River Plain. The preliminary results of chemical analyses and geothermometry applied to these samples are presented herein.

Geochemistry Sampling for Traditional and Multicomponent Equilibrium Geothermometry in Southeast Idaho

Energy Technology Data Exchange (ETDEWEB)

Cannon, Cody [Univ. of Idaho, Idaho Falls, ID (United States). Center for Advanced Studies; Wood, Thomas [Univ. of Idaho, Idaho Falls, ID (United States). Center for Advanced Studies; Neupane, Ghanashyam [Idaho National Lab. (INL), Idaho Falls, ID (United States). Center for Advanced Studies; McLing, Travis [Idaho National Lab. (INL), Idaho Falls, ID (United States). Center for Advanced Studies; Mattson, Earl [Idaho National Lab. (INL), Idaho Falls, ID (United States); Dobson, Patrick [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Conrad, Mark [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2014-10-01

The Eastern Snake River Plain (ESRP) is an area of high regional heat flux due the movement of the North American Plate over the Yellowstone Hotspot beginning ca.16 Ma. Temperature gradients between 45-60 °C/km (up to double the global average) have been calculated from deep wells that penetrate the upper aquifer system (Blackwell 1989). Despite the high geothermal potential, thermal signatures from hot springs and wells are effectively masked by the rapid flow of cold groundwater through the highly permeable basalts of the Eastern Snake River Plain aquifer (ESRPA) (up to 500+ m thick). This preliminary study is part of an effort to more accurately predict temperatures of the ESRP deep thermal reservoir while accounting for the effects of the prolific cold water aquifer system above. This study combines the use of traditional geothermometry, mixing models, and a multicomponent equilibrium geothermometry (MEG) tool to investigate the geothermal potential of the ESRP. In March, 2014, a collaborative team including members of the University of Idaho, the Idaho National Laboratory, and the Lawrence Berkeley National Laboratory collected 14 thermal water samples from and adjacent to the Eastern Snake River Plain. The preliminary results of chemical analyses and geothermometry applied to these samples are presented herein.

The Implementation of Pay for Performance in Idaho Schools: A Case Study of Teacher Perceptions

Science.gov (United States)

Staniec, Shelly Ann

2013-01-01

This is a qualitative narrative case study set in an Idaho high school where twelve educators offered their viewpoints on the implementation of Idaho's pay-for-performance legislation. In the spring of 2011, Idaho legislators passed laws aimed at increasing student performance and college or career readiness. These laws, known as Idaho's Students…

Use of radioactive tracers in chemical reactions

International Nuclear Information System (INIS)

Paci, B.

1979-01-01

A method for the determination of small quantities of nickel using radioactive tracers is presented. An analytical application of the displacement reaction between nickel and zinc ethylenediaminetetraacetate labeled with zinc-65 is pursued. This method is based on the extraction of radioactive zinc displaced by nickel from the zinc chelate into a dithizone-carbon tetracloride solution and the subsequent measurement of the activity of an aliquot of the extract. The method is very sensitive and nickel can be measured in concentrations as small as 0.1μg/ml or even less, depending on the specific activity of the radioreagent used. The precision and the accuracy of the method are determined. The problem of interferences, trying to eliminate them by using masking agents or by means of a previous separation between nickel and other interfering metals, is also investigated [pt

Study of commercial chemical additives for cementation of radioactive waste

International Nuclear Information System (INIS)

Mota Vieira, V.; Oliveira, C.C. de

2015-01-01

In this research it has been studied the effects of chemical additives (admixtures) in the cementation process of radioactive wastes, which are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market, then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 23. The measured parameters were the viscosity, the setting time, the paste and product density and the compressive strength. In this study we performed comparative analyzes of the results of compressive strength at age of 28 and 90 days and between the densities of the samples at the same ages. The compressive strength test at age of 28 days is considered a parameter essential issues related to security handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented product, but presented lower values density products. (authors)

Development of a comprehensive source term model for the Subsurface Disposal Area at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

1997-01-01

The first detailed comprehensive simulation study to evaluate fate and transport of wastes disposed in the Subsurface Disposal Area (SDA), at the Radioactive Waste Management Complex (RWMC), Idaho National Engineering and Environmental Laboratory (INEEL) has recently been conducted. One of the most crucial parts of this modeling was the source term or release model. The current study used information collected over the last five years defining contaminant specific information including: the amount disposed, the waste form (physical and chemical properties) and the type of container used for each contaminant disposed. This information was used to simulate the release of contaminants disposed in the shallow subsurface at the SDA. The DUST-MS model was used to simulate the release. Modifications were made to allow the yearly disposal information to be incorporated. The modeling includes unique container and release rate information for each of the 42 years of disposal. The results from this simulation effort are used for both a groundwater and a biotic uptake evaluation. As part of this modeling exercise, inadequacies in the available data relating to the release of contaminants have been identified. The results from this modeling study have been used to guide additional data collection activities at the SDA for purposes of increasing confidence in the appropriateness of model predictions

Compilation and analysis of multiple groundwater-quality datasets for Idaho

Science.gov (United States)

Hundt, Stephen A.; Hopkins, Candice B.

2018-05-09

Groundwater is an important source of drinking and irrigation water throughout Idaho, and groundwater quality is monitored by various Federal, State, and local agencies. The historical, multi-agency records of groundwater quality include a valuable dataset that has yet to be compiled or analyzed on a statewide level. The purpose of this study is to combine groundwater-quality data from multiple sources into a single database, to summarize this dataset, and to perform bulk analyses to reveal spatial and temporal patterns of water quality throughout Idaho. Data were retrieved from the Water Quality Portal (https://www.waterqualitydata.us/), the Idaho Department of Environmental Quality, and the Idaho Department of Water Resources. Analyses included counting the number of times a sample location had concentrations above Maximum Contaminant Levels (MCL), performing trends tests, and calculating correlations between water-quality analytes. The water-quality database and the analysis results are available through USGS ScienceBase (https://doi.org/10.5066/F72V2FBG).

Residential Energy Efficiency Potential: Idaho

Energy Technology Data Exchange (ETDEWEB)

Wilson, Eric J [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

2017-11-02

Energy used by Idaho single-family homes that can be saved through cost-effective improvements. Prepared by Eric Wilson and Noel Merket, NREL, and Erin Boyd, U.S. Department of Energy Office of Energy Policy and Systems Analysis.

Industrial application of geothermal energy in Southeast Idaho

Energy Technology Data Exchange (ETDEWEB)

Batdorf, J.A.; McClain, D.W.; Gross, M.; Simmons, G.M.

1980-02-01

Those phosphate related and food processing industries in Southeastern Idaho are identified which require large energy inputs and the potential for direct application of geothermal energy is assessed. The total energy demand is given along with that fractional demand that can be satisfied by a geothermal source of known temperature. The potential for geothermal resource development is analyzed by examining the location of known thermal springs and wells, the location of state and federal geothermal exploration leases, and the location of federal and state oil and gas leasing activity in Southeast Idaho. Information is also presented regarding the location of geothermal, oil, and gas exploration wells in Southeast Idaho. The location of state and federal phosphate mining leases is also presented. This information is presented in table and map formats to show the proximity of exploration and development activities to current food and phosphate processing facilities and phosphate mining activities. (MHR)

The Idaho Spent Fuel Project Update-January, 2003

International Nuclear Information System (INIS)

Roberts, R.; Tulberg, D.; Carter, C.

2003-01-01

The Department of Energy awarded a privatized contract to Foster Wheeler Environmental Corporation in May 2000 for the design, licensing, construction and operation of a spent nuclear fuel repackaging and storage facility. The Foster Wheeler Environmental Team consists of Foster Wheeler Environmental Corp. (the primary contractor), Alstec, RWE-Nukem, RIO Technical Services, Winston and Strawn, and Utility Engineering. The Idaho Spent Fuel (ISF) facility is an integral part of the DOE-EM approach to accelerating SNF disposition at the Idaho National Engineering and Environmental Laboratory (INEEL). Construction of this facility is also important in helping DOE to meet the provisions of the Idaho Settlement Agreement. The ISF Facility is a substantial facility with heavy shielding walls in the repackaging and storage bays and state-of-the-art features required to meet the provisions of 10 CFR 72 requirements. The facility is designed for a 40-year life

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. 2. ed.; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Derakshani, Nahid; Drobig, Matthias; Koenig, Mario; Mentfewitz, Joachim; Prast, Hartmut; Uelpenich, Gerhard; Vidmayer, Marc; Wilbert, Stefan; Wolf, Manfred

2016-07-01

The recommendations for sampling for prevention of hazards in civil defense (analytics of chemical, biological and radioactive contaminations) cover the following topics: Requirements for sampling, description of the materials (chemical, biological and radioactive contaminated materials), decontamination, sample transport and protocol documents.

studies on the fixation of chemical and radioactive contaminants by natural and artificial compounds

International Nuclear Information System (INIS)

Mourad, G.A.M.

2006-01-01

the main objective of the work presented in this is to study the adsorption of U(VI), Cr(VI) and Gd (lll) from aqueous medium using modified sorel's cement as artificial adsorbents. the thesis is classified into three chapters; namely ,introduction ,experimental and results and discussion. the first chapter, i ntroduction , includes chemical and radioactive contaminant, some aspects of the properties and aqueous chemistry of uranium, chromium and gadolinium . the separation of different pollutant and their methods of separation based on the types of adsorbents, and the theoretical background of adsorption isotherms, kinetics and ion diffusion as well as literature survey which is related to the present work are given.the second chapter, e xperimental , contains the different materials employed, their chemical purity, and a detailed description for instruments used are given.the third chapter. r esults and discussion i ncludes the experimental results obtained and their interpretation .this chapter is classified into three main parts; namely, characterization, equilibrium and kinetic investigations

Use of radioactive tracers in chemical reactions

International Nuclear Information System (INIS)

Paci, B.; Saiki, M.

1979-01-01

A method for the determination of small quantities of nickel by using radioactive tracers is presented. An analytical application of the displacement reaction between and zinc-ethylenediaminetetraacetate, (Zn-EDTA), labelled with 65 Zn is investigated. This method is based on the extraction of radioactive zinc, displaced by nickel from the zinc chelate, into a dithizone-carbon tetrachloride solution and the subsequent measurement of the activity of an aliquot of the extract. It is shown that the method is very sentitive and nickel can be measured in concentrations as small as 0,1μg/ml or even less, depending on the specific activity of the radioreagent used. The precision and accuracy of the method are determined. An attempt to eliminate the problem of interference by using masking agents or by means of a previous separation of nickel and other interfereing metals, is also made. (Author) [pt

Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

Energy Technology Data Exchange (ETDEWEB)

Stirrup, T.S.

1993-06-01

This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory.

Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

International Nuclear Information System (INIS)

Stirrup, T.S.

1993-06-01

This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory

Heat transfer in high-level waste management

International Nuclear Information System (INIS)

Dickey, B.R.; Hogg, G.W.

1979-01-01

Heat transfer in the storage of high-level liquid wastes, calcining of radioactive wastes, and storage of solidified wastes are discussed. Processing and storage experience at the Idaho Chemical Processing Plant are summarized for defense high-level wastes; heat transfer in power reactor high-level waste processing and storage is also discussed

[Microbiological Aspects of Radioactive Waste Storage].

Science.gov (United States)

Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

2015-01-01

The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

Development of the chemical stabilization and solidification process for the treatment of radioactive raffinate sludges at the DOE Weldon Spring Site Remedial Action Project

International Nuclear Information System (INIS)

Cole, P.M.; Kakaria, V.; Enger, J.

1996-01-01

Chemical Solidification and Stabilization (CSS) is the mixing of chemical reagents with waste to solidify and chemically stabilize the contaminated material. The resulting product is resistant to leaching of certain contaminants. CSS treatment using Class C fly ash and Portland cement was chosen as the most feasible method for treatment of the chemically and radioactively contaminated sludge (raffinate) contained in raffinate pits on the Weldon Spring Site Remedial Action Project (WSSRAP) located outside of St. Louis, Missouri. Due to the uniqueness of the material, substantial bench-scale testing was performed on the raffinate to better understand its properties. Similarly, due to mixed results in the application of CSS treatment to radioactive materials, a pilot-scale testing facility was built to verify bench testing results and to establish and quantify design parameters for the full-scale CSS production facility. This paper discusses the development of the pilot-scale testing facility, the testing plan, and the results of the testing activities. Particular attention has been given to the applicability of the CSS treatment method and to the value of pilot-scale testing

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Echinococcus granulosus in gray wolves and ungulates in Idaho and Montana, USA.

Science.gov (United States)

Foreyt, William J; Drew, Mark L; Atkinson, Mark; McCauley, Deborah

2009-10-01

We evaluated the small intestines of 123 gray wolves (Canis lupus) that were collected from Idaho, USA (n=63), and Montana, USA (n=60), between 2006 and 2008 for the tapeworm Echinococcus granulosus. The tapeworm was detected in 39 of 63 wolves (62%) in Idaho, USA, and 38 of 60 wolves (63%) in Montana, USA. The detection of thousands of tapeworms per wolf was a common finding. In Idaho, USA, hydatid cysts, the intermediate form of E. granulosus, were detected in elk (Cervus elaphus), mule deer (Odocoileus hemionus), and a mountain goat (Oreamnos americanus). In Montana, USA, hydatid cysts were detected in elk. To our knowledge, this is the first report of adult E. granulosus in Idaho, USA, or Montana, USA. It is unknown whether the parasite was introduced into Idaho, USA, and southwestern Montana, USA, with the importation of wolves from Alberta, Canada, or British Columbia, Canada, into Yellowstone National Park, Wyoming, USA, and central Idaho, USA, in 1995 and 1996, or whether the parasite has always been present in other carnivore hosts, and wolves became a new definitive host. Based on our results, the parasite is now well established in wolves in these states and is documented in elk, mule deer, and a mountain goat as intermediate hosts.

Significance of chemotoxic admixtures in radioactive wastes

International Nuclear Information System (INIS)

Merz, E.R.

1989-01-01

The double hazard potential of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, in flammability, corrosiveness as well as chemical reactivity on the other. The author argues that mixed wastes assigned for ultimate disposal should therefore be thoroughly detoxified, inertized, or mineralized, prior to conditioning and packaging. Strategies and techniques are presented which ensure the elimination of hazardous organic chemicals and minimizing waste volumes to be disposed of. Advantage can be taken of mixing mineralized filter dusts, arising in the combustion of hazardous chemical wastes with low-activity inertized radioactive wastes as a solidifying reagent. Simultaneous geological disposal of such mixed waste is feasible without any drawbacks

Physico-chemical and radioactive characterization of TiO2 undissolved mud for its valorization

International Nuclear Information System (INIS)

Gazquez, M.J.; Mantero, J.; Bolivar, J.P.; Garcia-Tenorio, R.; Vaca, F.; Lozano, R.L.

2011-01-01

In order to find a potential valorization of a waste generated in the industrial process devoted to the production of TiO 2 pigments, and as an essential and basic step, this waste must firstly be physically and chemically characterized. Moreover, the content of radioactivity is taken in to account due to it comes from a NORM (Naturally Occurring Radioactive Material) industry. With this end, microscopic studies were performed by applying scanning electron microscopy with X-ray microanalysis (SEM-XRMA), while the mineralogical compositions were carried out by means of the X-ray diffraction (XRD) technique. The concentrations of its major elements were determined by X-ray fluorescence (XRF), while heavy metals and other trace elements were ascertained through Inductively Coupled Plasma Mass Spectrometry (ICP-MS). The results obtained for this waste have revealed several lines of research into potential applications. Firstly, with the refractory properties of mineral phases observed leading to a possible use in the ceramics industry or in thermal isolators. And secondly, attending to the characteristic particle-size spectra can be used as an additive in the manufacture of cement and finally, its high concentration of titanium may be used as a bactericide in brick production.

Insects of the Idaho National Laboratory: A compilation and review

Science.gov (United States)

Nancy Hampton

2005-01-01

Large tracts of important sagebrush (Artemisia L.) habitat in southeastern Idaho, including thousands of acres at the Idaho National Laboratory (INL), continue to be lost and degraded through wildland fire and other disturbances. The roles of most insects in sagebrush ecosystems are not well understood, and the effects of habitat loss and alteration...

Laboratory testing of glasses for Lockheed Idaho Technology Co. - fiscal year 1994 report

International Nuclear Information System (INIS)

Ellison, A.J.G.; Wolf, S.F.; Bates, J.K.

1995-04-01

The purpose of this project is to measure the intermediate and long-term durability of vitrified waste forms developed by Lockheed Idaho Technology Co. (LITCO) for the immobilization of calcined radioactive wastes at Idaho National Engineering Laboratory. Two vitreous materials referred to as Formula 127 and Formula 532, have been subjected to accelerated durability tests to measure their long-term performance. Formula 127 consists of a glass matrix containing 5-10 vol % fluorite (CaF 2 ) as a primary crystalline phase. It shows low releases of glass components to solution in 7-, 28-, 70-, and 140-day Product Consistency Tests performed at 2000 m -1 at 90 degrees C. In these tests, release rates for glass-forming components were similar to those found for durable waste glasses. The Ca and F released by the glass as it corrodes appear to reprecipitate as fluorite. Formula 532 consists of a glass matrix containing 5-10 vol % of an Al-Si-rich primary crystalline phase. The release rates for components other than aluminum are relatively low, but aluminum is released at a much higher rate than is typical for durable waste glasses. Secondary crystalline phases form relatively early during the corrosion of Formula 532 and appear to consist almost entirely of the Al-Si-rich primary phase (or a crystal with the same Al:Si ratio) and a sodium-bearing zeolite. Future test results are expected to highlight the relative importance of primary and secondary crystalline phases to the rate of corrosion of Formula 127 and Formula 532

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

76 FR 10018 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

Science.gov (United States)

2011-02-23

... Idaho's 2015 Cleanup Vision Government Budget Cycle American Recovery and Reinvestment Act Idaho Cleanup.... The Deputy Designated Federal Officer is empowered to conduct the meeting in a fashion that will...

Baseline Flowsheet Generation for the Treatment and Disposal of Idaho National Engineering and Environmental Laboratory Sodium Bearing Waste

International Nuclear Information System (INIS)

Barnes, C.M.; Lauerhass, L.; Olson, A.L.; Taylor, D.D.; Valentine, J.H.; Lockie, K.A.

2002-01-01

The High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL) must implement technologies and processes to treat and qualify radioactive wastes located at the Idaho Nuclear Technology and Engineering Center (INTEC) for permanent disposal. This paper describes the approach and accomplishments to date for completing development of a baseline vitrification treatment flowsheet for sodium-bearing waste (SBW), including development of a relational database used to manage the associated process assumptions. A process baseline has been developed that includes process requirements, basis and assumptions, process flow diagrams, a process description, and a mass balance. In the absence of actual process or experimental results, mass and energy balance data for certain process steps are based on assumptions. Identification, documentation, validation, and overall management of the flowsheet assumptions are critical to ensuring an integrated, focused program. The INEEL HLW Program initially used a roadmapping methodology, developed through the INEEL Environmental Management Integration Program, to identify, document, and assess the uncertainty and risk associated with the SBW flowsheet process assumptions. However, the mass balance assumptions, process configuration and requirements should be accessible to all program participants. This need resulted in the creation of a relational database that provides formal documentation and tracking of the programmatic uncertainties related to the SBW flowsheet

Chemical species of plutonium in Hanford radioactive tank waste

International Nuclear Information System (INIS)

Barney, G.S.

1997-01-01

Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

BioRadBase: A database for bioremediation of radioactive waste ...

African Journals Online (AJOL)

Radioactive waste from different sectors such as nuclear energy, health care and food has become a discernible part of our environment. Several dumping methods are in routine practice to dispose radioactive wastes. Huge chemical and energy input in various skillful physico-chemical methods has limited their use while ...

Influence of non-radioactive payload parameters on radioactive shipping packages

International Nuclear Information System (INIS)

Drez, P.E.; Murthy, D.V.S.; Temus, C.J.; Quinn, G.J.; Ozaki, C.

1989-01-01

The transport of radioactive waste materials in radioactive material (RAM) packages involves two components: the packaging used for transportation, and the waste which forms the payload. The payload is usually comprised of non-radioactive materials contaminated with radionuclides. The non-radionuclide payload characteristics can often be a controlling factor in determining the restrictions imposed on the certification of the package. This paper describes these package/payload interactions and the limiting parameters for the Transuranic Package Transporter-II (TRUPACT-II), designed for the transportation of Contact Handled Transuranic (CH-TRU) waste. The parameters discussed include the physical and chemical form of the payload, the configuration of the waste, and resulting gas generation and gas release phenomena. Brief descriptions of the TRUPACT-II package and its payload are presented initially

Ventilation of radioactive enclosures

International Nuclear Information System (INIS)

Caminade, F.; Laurent, H.

1957-01-01

Mechanical, physical and chemical manipulations on radioactive products must be carried out in properly ventilated enclosed places. The air extracted can only be discharged into the atmosphere after a correct filtration. The power of the ventilation systems is a function of the dimensions and purpose of the enclosure? The choice of types of filter is determined by the physical state and chemical nature of the radioactive materials to be manipulated. This study deals with the individual equipment of small installations: glove boxes, manipulation boxes with outside control and, if necessary, production chambers (maximum useful volume: 5 m 3 ). The performances of three types of 'ventilators', and the modifications provided by the addition of filters, are measured and compared. (author) [fr

Radioactive Waste Management Complex performance assessment: Draft

Energy Technology Data Exchange (ETDEWEB)

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Radioactive Waste Management Complex performance assessment: Draft

International Nuclear Information System (INIS)

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations

Disposal method of radioactive wastes

International Nuclear Information System (INIS)

Uetake, Naoto; Fukazawa, Tetsuo.

1986-01-01

Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

Measurement of Radioactivity in Some Croatian Regions

International Nuclear Information System (INIS)

Orehovec, Z.; Ilijas, B.; Bokan, S.

2001-01-01

Full text: After Government of Canada expressed its suspicion that Canadian soldiers who were included in UNPROFOR mission in Croatia were exposed to increased radioactivity and possible some chemical influences, a large action of measuring and sampling was undertaken. Canadian and Croatian experts were working together and a very large number of samples was collected. Measurements of alpha, beta and gamma radioactivity on terrain, as well as later analysis of samples showed no increased radioactivity or any other signs of radioactive contamination. The conclusion is that any possible diseases of Canadian soldiers can not originate from radiation or radioactive contamination in Croatia. (author)

After Action Report: Idaho National Laboratory Annual Exercise June 10, 2015

Energy Technology Data Exchange (ETDEWEB)

Barnes, Vernon Scott [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-07-01

On June 10, 2015, Idaho National Laboratory (INL), in coordination with the State of Idaho, local jurisdictions, Department of Energy Idaho Operations Office (DOE-ID), and DOE Headquarters (DOE HQ), conducted the annual emergency exercise to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System.” The INL contractor, Battelle Energy Alliance, LLC (BEA), in coordination with other INL contractors, conducted operations and demonstrated appropriate response measures to mitigate an event and protect the health and safety of personnel, the environment, and property. Offsite response organizations participated to demonstrate appropriate response measures.

Special study for the manual transfer of process samples from CPP [Chemical Processing Plant] 601 to RAL [Remote Analytical Laboratory

International Nuclear Information System (INIS)

Marts, D.J.

1987-05-01

A study of alternate methods to manually transport radioactive samples from their glove boxes to the Remote Analytical Laboratory (RAL) was conducted at the Idaho National Engineering Laboratory. The study was performed to mitigate the effects of a potential loss of sampling capabilities that could take place if a malfunction in the Pneumatic Transfer System (PTS) occurred. Samples are required to be taken from the cell glove boxes and analyzed at the RAL regardless of the operational status of the PTS. This paper documents the conclusions of the study and how a decision was reached that determined the best handling scenarios for manually transporting 15 mL vials of liquid process samples from the K, W, U, WG, or WH cell glove boxes in the Chemical Processing Plant (CPP) 601 to the RAL. This study of methods to manually remove the samples from the glove boxes, package them for safe shipment, transport them by the safest route, receive them at the RAL, and safely unload them was conducted by EG and G Idaho, Inc., for Westinghouse Idaho Nuclear Company as part of the Glove Box Sampling and Transfer System Project for the Fuel Processing Facilities Upgrade, Task 10, Subtask 2. The study focused on the safest and most reliable scenarios that could be implemented using existing equipment. Hardware modifications and new hardware proposals were identified, and their impact on the handling scenario has been evaluated. A conclusion was reached that by utilizing the existing facility hardware, these samples can be safely transported manually from the sample stations in CPP 601 to the RAL, and that additional hardware could facilitate the transportation process even further

Idaho Marketing Education Core Curriculum. Career Sustaining Level, Specialist Level, Supervisory Level, Entrepreneurial Level.

Science.gov (United States)

Miller, Linda Wise; Winn, Richard

This document contains Idaho's marketing education (ME) core curriculum. Presented first are a list of 22 ME strategies that are aligned with the Idaho State Division of Vocational-Technical Education's strategic plan and a chart detailing the career pathways of ME in Idaho (arts and communication, business and management, health services, human…

Data for radioactive waste management and nuclear applications

International Nuclear Information System (INIS)

Stewart, D.C.

1985-01-01

This book is a specialized handbook on the management of radioactive waste, including information applicable to related applications. It consolidates information from many sources to develop techniques for dealing with radioactive waste management and features reports and other specialized data not available in libraries. It covers physical data, chemical data, types of radioactive wastes, and data for different operations

Idaho National Engineering and Environmental Laboratory institutional plan -- FY 2000--2004

Energy Technology Data Exchange (ETDEWEB)

Enge, R.S.

1999-12-01

In this first institutional plan prepared by Bechtel BWXT Idaho, LLC, for the Idaho National Engineering and Environmental Laboratory, the INEEL will focus its efforts on three strategic thrusts: (1) Environmental Management stewardship for DOE-EM, (2) Nuclear reactor technology for DOE-Nuclear Energy (NE), and (3) Energy R and D, demonstration, and deployment (initial focus on biofuels and chemicals from biomass). The first strategic thrust focuses on meeting DOE-EMs environmental cleanup and long-term stewardship needs in a manner that is safe, cost-effective, science-based, and approved by key stakeholders. The science base at the INEEL will be further used to address a grand challenge for the INEEL and the DOE complex--the development of a fundamental scientific understanding of the migration of subsurface contaminants. The second strategic thrust is directed at DOE-NEs needs for safe, economical, waste-minimized, and proliferation-resistant nuclear technologies. As NE lead laboratories, the INEEL and ANL will pursue specific priorities. The third strategic thrust focuses on DOE's needs for clean, efficient, and renewable energy technology. As an initial effort, the INEEL will enhance its capability in biofuels, bioprocessing, and biochemicals. The content of this institutional plan is designed to meet basic DOE requirements for content and structure and reflect the key INEEL strategic thrusts. Updates to this institutional plan will offer additional content and resource refinements.

Abstracts and parameter index database for reports pertaining to the unsaturated zone and surface water-ground water interactions at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bloomsburg, G.; Finnie, J.; Horn, D.; King, B.; Liou, J.

1993-05-01

This report is a product generated by faculty at the University of Idaho in support of research and development projects on Unsaturated Zone Contamination and Transport Processes, and on Surface Water-Groundwater Interactions and Regional Groundwater Flow at the Idaho National Engineering Laboratory. These projects are managed by the State of Idaho's INEL Oversight Program under a grant from the US Department of Energy. In particular, this report meets project objectives to produce a site-wide summary of hydrological information based on a literature search and review of field, laboratory and modeling studies at INEL, including a cross-referenced index to site-specific physical, chemical, mineralogic, geologic and hydrologic parameters determined from these studies. This report includes abstracts of 149 reports with hydrological information. For reports which focus on hydrological issues, the abstracts are taken directly from those reports; for reports dealing with a variety of issues beside hydrology, the abstracts were generated by the University of Idaho authors concentrating on hydrology-related issues. Each abstract is followed by a ''Data'' section which identifies types of technical information included in a given report, such as information on parameters or chemistry, mineralogy, stream flows, water levels. The ''Data'' section does not include actual values or data

Chemical Effects of Nuclear Transformations Vol. I. Proceedings of the Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations

International Nuclear Information System (INIS)

1965-01-01

The study of the chemical changes consequent upon the nuclear transformation of an atom that is linked with other atoms in a molecule and surrounded by other similar or dissimilar molecules has intrigued chemists for a number of years. This interest is certainly not static but if anything is increasing. The main theme of this meeting was a discussion of the suggestions and theories that have been advanced to explain the wealth of experimental observations on the behaviour of atoms at energies and in situations not normally accessible in the laboratory. Though the subject has some practical implications in the preparation of radioisotopes, this was not an important consideration at this Symposium. The first Symposium on hot-atom chemistry organized by the Agency was held in Prague in October 1960. Comparison of the past and the present state of the subject shows that a greater variety and sophistication of techniques are now being applied as the simpler approaches used in the past have been shown to be inadequate. Progress has been made in the understanding of the simpler gas system, but in liquids and solids there is still much to clarify. It is also of interest that for the majority of the work reported in these Proceedings a reactor was the radiation source, and in this field much experimental work still remains to be done. The Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations was held from 7 to 11 December 1964 in Vienna, and was attended by 136 participants from 29 countries and 4 international organizations. It was organized by the International Atomic Energy Agency in co-operation with the Joint Commission on Applied Radioactivity. The publication of these Proceedings makes the content of the papers and discussion available to a wider audience than was possible at the meeting in Vienna

Treatment and conditioning of radioactive organic liquids

International Nuclear Information System (INIS)

1992-07-01

Liquid organic radioactive wastes are generated from the use of radioisotopes in nuclear research centres and in medical and industrial applications. The volume of these wastes is small by comparison with aqueous radioactive wastes, for example; nevertheless, a strategy for the effective management of these wastes is necessary in order to ensure their safe handling, processing, storage and disposal. A aqueous radioactive wastes may be discharged to the environment after the radioactivity has decayed or been removed. By contrast, organic radioactive wastes require management steps that not only take account of their radioactivity, but also of their chemical content. This is because both the radioactivity and the organic chemical nature can have detrimental effects on health and the environment. Liquid radioactive wastes from these applications typically include vacuum pump oil, lubricating oil and hydraulic fluids, scintillation cocktails from analytical laboratories, solvents from solvent extraction research and uranium refining, and miscellaneous organic solvents. The report describes the factors which should be considered in the development of appropriate strategies for managing this class of wastes from generation to final disposal. Waste sources and characterization, treatment and conditioning processes, packaging, interim storage and the required quality assurance are all discussed. The report is intended to provide guidance to developing Member States which do not have nuclear power generation. A range of processes and procedures is presented, though emphasis is given to simple, easy-to-operate processes requiring less sophisticated and relatively inexpensive equipment. 31 refs, 16 figs, 3 tabs

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Estimated Perennial Streams of Idaho and Related Geospatial Datasets

Science.gov (United States)

Rea, Alan; Skinner, Kenneth D.

2009-01-01

The perennial or intermittent status of a stream has bearing on many regulatory requirements. Because of changing technologies over time, cartographic representation of perennial/intermittent status of streams on U.S. Geological Survey (USGS) topographic maps is not always accurate and (or) consistent from one map sheet to another. Idaho Administrative Code defines an intermittent stream as one having a 7-day, 2-year low flow (7Q2) less than 0.1 cubic feet per second. To establish consistency with the Idaho Administrative Code, the USGS developed regional regression equations for Idaho streams for several low-flow statistics, including 7Q2. Using these regression equations, the 7Q2 streamflow may be estimated for naturally flowing streams anywhere in Idaho to help determine perennial/intermittent status of streams. Using these equations in conjunction with a Geographic Information System (GIS) technique known as weighted flow accumulation allows for an automated and continuous estimation of 7Q2 streamflow at all points along a stream, which in turn can be used to determine if a stream is intermittent or perennial according to the Idaho Administrative Code operational definition. The selected regression equations were applied to create continuous grids of 7Q2 estimates for the eight low-flow regression regions of Idaho. By applying the 0.1 ft3/s criterion, the perennial streams have been estimated in each low-flow region. Uncertainty in the estimates is shown by identifying a 'transitional' zone, corresponding to flow estimates of 0.1 ft3/s plus and minus one standard error. Considerable additional uncertainty exists in the model of perennial streams presented in this report. The regression models provide overall estimates based on general trends within each regression region. These models do not include local factors such as a large spring or a losing reach that may greatly affect flows at any given point. Site-specific flow data, assuming a sufficient period of

Evaporation Basin Test Reactor Area, Idaho National Engineering Laboratory: Environmental assessment

International Nuclear Information System (INIS)

1991-12-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0501, on the construction and operation of the proposed Evaporation Basin at the Test Reactor Area (TRA) at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact

75 FR 7440 - Notice of Idaho Panhandle Resource Advisory Committee Meeting

Science.gov (United States)

2010-02-19

... Self-Determination Act of 2000 (Public Law 110-343) the Idaho Panhandle National Forest's Idaho... for a business meeting. The business meeting is open to the public. DATES: February 19, 2010... business meeting. The public forum begins at 11 a.m. Dated: February 10, 2010. Ranotta K. McNair, Forest...

Idaho National Engineering Laboratory installation roadmap document

International Nuclear Information System (INIS)

1993-01-01

The roadmapping process was initiated by the US Department of Energy's office of Environmental Restoration and Waste Management (EM) to improve its Five-Year Plan and budget allocation process. Roadmap documents will provide the technical baseline for this planning process and help EM develop more effective strategies and program plans for achieving its long-term goals. This document is a composite of roadmap assumptions and issues developed for the Idaho National Engineering Laboratory (INEL) by US Department of Energy Idaho Field Office and subcontractor personnel. The installation roadmap discusses activities, issues, and installation commitments that affect waste management and environmental restoration activities at the INEL. The High-Level Waste, Land Disposal Restriction, and Environmental Restoration Roadmaps are also included

Idaho National Engineering Laboratory hazardous and radioactive mixed waste identification and characterization report for CY 1986

International Nuclear Information System (INIS)

Nishimoto, D.D.

1987-05-01

This report provides updated tabulations of the hazardous and radioactive mixed wastes generated and/or handled during CY 1986 at each INEL facility operated by EG and G, or any other operating contractor at the Site. These wastes are described in tabular form, providing information such as composition, generating process, contact person, EPA hazardous waste designation, quantity shipped off site (if applicable), and quantity in storage. Waste generation projections for the next ten years are also included for all INEL facilities. Finally, since many of EG and G's inactive disposal sites may prove to be significant sources of either hazardous or radioactive mixed wastes as remedial action activities under RCRA or CERCLA progress, information on these sites is provided. 2 refs., 1 fig., 8 tabs

Paleomagnetic correlation of surface and subsurface basaltic lava flows and flow groups in the southern part of the Idaho National Laboratory, Idaho, with paleomagnetic data tables for drill cores

Science.gov (United States)

Champion, Duane E.; Hodges, Mary K.V.; Davis, Linda C.; Lanphere, Marvin A.

2011-01-01

found in the subsurface at coreholes ARA-COR-005 and STF-AQ-01. The high K20 flow group erupted from a vent that may now be buried south of U.S. Highway 20 near Middle Butte, flowed north, and is found in the subsurface in coreholes USGS 131, USGS 127, USGS 130, USGS 128, USGS 123, STF-AQ-01, and ARA-COR-005 ending near the Idaho Nuclear Technology and Engineering Center. The vent 5252 flow group erupted just south of U.S. Highway 20 near Middle and East Buttes, flowed northwest, and is found in the subsurface in coreholes ARA-COR-005, STF-AQ-01, USGS 130, USGS 128, ICPP 214, USGS 123, ICPP 023, USGS 121, USGS 127, and USGS 131. The Big Lost flow group erupted from a now-buried vent near the Radioactive Waste Management Complex, flowed southwest to corehole USGS 135, and northeast to coreholes USGS 132, USGS 129, USGS 131, USGS 127, USGS 130, STF-AQ-01, and ARA-COR-005. The AEC Butte flow group erupted from AEC Butte near the Advanced Test Reactor Complex and flowed south to corehole Middle 1823, northwest to corehole USGS 134, northeast to coreholes USGS 133 and NRF 7P, and south to coreholes USGS 121, ICPP 023, USGS 123, and USGS 128. Evidence of progressive subsidence of the axial zone of the ESRP is shown in these cross-sections, distorting the original attitudes of the lava flow groups and interbedded sediments. A deeper cross-section, C-C- (oriented west to east), spanning the entire southern Idaho National Laboratory shows correlations of the lava flow groups in the saturated part of the ESRP aquifer. Areally extensive flow groups in the deep subsurface (from about 100-800 meters below land surface) can be traced over long distances. In cross-section C-C-, the flow group labeled "Matuyama" can be correlated from corehole USGS 135 to corehole NPR Test/W-02, a distance of about 28 kilometers (17 miles). The flow group labeled "Matuyama 1.21 Ma" can be correlated from corehole Middle 1823 to corehole ANL-OBS-A-001, a distance of 26 kilometers (16 miles). Other flo

Labelled radioactive adenosinphosphates for the determination of toxic action

International Nuclear Information System (INIS)

Tahbaz, Z.

1983-01-01

Normal house-flies had been fed with carrier free radiophosphate (phosphorus). Many phosphorous containing substances in the tissue of the housefly are labelled with radiophosphorus by this procedure. Radiophosphorus is also found in the nucleotides of the housefly after applying radioactive phosphate. Suitable methods for processing and separation had been selected and worked out to isolate 32 P-adenosin-triphosphate 32 P-adenosin-diphosphate, 32 P-adenosin-monophosphate and 32 P-phosphate. Working at low temperature prevents chemical changes of the nucleotides. Extraction and thin layer chromatorgraphy turned out to be effective separation procedures for preparing samples for radioactivity measurement of the nucleotides. Autoradiographic techniques, scanning and liquid scitillation counting had been used for radioactivity measurements of the radioactive zones at the chromatograms. The results of these measurements provide information concerning the normal composition of adenosin-phosphates in the tissues of the housefly. If the animals are exposed to toxic chemicals, to insecticides, the composition of the phosphate containing compounds is changing. The concentration of adenosin-triphosphate is decreasing and the concentration of phosphate is increasing. This can be very easily shown by scanning the chromatograms of the extracts of the muscles of houseflies after feeding the animals with radioactive phosphate. Using this method, it is possible to show the toxic action of insecticides upon the metabolism of adenosin-phosphates. The decrease of the radioactivity at the zone of the adenosin-triphosphate and the increase of the radioactivity at the phosphate zone corresponds to the toxic action of foreign chemicals like insecticides. By using this tracer technique, it may be possible to investigate the toxic action of several toxic chemicals, if they are applied at the same time, thus investigating synergetic actions of environmental poisons. (Author)

Thermal treatment of organic radioactive waste

International Nuclear Information System (INIS)

Chrubasik, A.; Stich, W.

1993-01-01

The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste

Geothermal energy in Idaho: site data base and development status

Energy Technology Data Exchange (ETDEWEB)

McClain, D.V.

1979-07-01

A summary of known information about the nature of the resource, its potential for development, and the infrastructure of government which will guide future development is presented. Detailed site specific data regarding the commercialization potential of the proven, potential, and inferred geothermal resource areas in Idaho are included. Leasing and development status, institutional parameters, and a legal overview of geothermal resources in Idaho are given. (MHR)

Idaho Transportation Department 2009 partnership survey.

Science.gov (United States)

2010-06-01

The report discusses the results of an electronic survey of 1,500 individual stakeholders of the Idaho Transportation Department (ITD). The purpose of this survey, which was conducted in August and September 2009, was to gauge stakeholders satisfa...

New radioactive tracers can help find cause of jaundice

International Nuclear Information System (INIS)

Carrard, G.

1987-01-01

Radioactive tracers for the investigation of a condition known as persistent jaundice of the newborn, have been designed, prepared and tested at ANSTO. The tracers are chemical compounds of the radioactive elements gallium-67 and indium-111. They given lower radiation doses than the conventional radioactive tracer, iodine-131, used in these studies

Chemical and radioactivity study of sea alga distribution along the Syrian coast

International Nuclear Information System (INIS)

Al-Masri, M. S.; Mamish, S.; Budeir, Y.

2001-11-01

Three types of sea alga distributed along the Syrian coast have been studied from the chemical and radioactivity point of view. Results have shown the metals that red alga contains the highest levels of Ca and Mg while brown alga were found to contain relatively high concentrations of other elements and non metals such as Cl, I and Br. In addition, 137 Cs concentrations in all the analyzed sample were low while the levels of naturally occurring radionuclides such as 210 Po, 210 Pb and radium isotopes were found to be high in red alga which indicates their selectivity to these isotopes. On the other hand, brown alga and especially Cysteseira has shown a clear selectivity for some trace elements such as As, Cr, Cd, Cu and Co, this selectivity may encourage the use of brown alga as biological indicator for trace elements pollution. (author)

Study of chemical additives in the cementation of radioactive waste of PWR reactors

International Nuclear Information System (INIS)

Vieira, Vanessa Mota; Tello, Cledola Cassia Oliveira de

2011-01-01

Cementation is a very useful process to solidify radioactive wastes. Depending on the waste it can be necessary to use of chemical additives (admixtures) to improve the cementation process and its product. Admixtures are materials, other than cement, aggregate and water, that are added either before or during the mixing to alter some properties, such as workability, curing temperature range, and setting time. However there are a large variety of these materials that are frequently changed or taken out of the market. In this changeable scenario it is essential to know the commercially available materials and their characteristics. In this research the effects of chemical admixtures in the solidification process has been studied. For the tests it was prepared a solution simulating the evaporator concentrate waste, cemented by two different formulations, and three chemical admixtures from two manufacturers. The tested admixtures were accelerators, set retarders and super plasticizers. The experiments were organized by a planning factorial 23 to quantify the effects of formulations, of the admixtures, its quantity and manufacturer in properties of the paste and products. The measured parameters were the density, the viscosity and the setting time of the paste, and the product compressive strength. The parameter evaluated in this study was the compressive strength at age of 28 days, is considered essential security issues relating to the handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented products. (author)

Studies on the remediation of environment contaminated with radioactive pollutants using the chemical separation technique

Energy Technology Data Exchange (ETDEWEB)

Kurotaki, Katsumi; Yonehara, Hidenori; Sahoo, S.K. [National Inst. of Radiological Sciences, Chiba (Japan); Ishii, Toshiaki [National Inst. of Radiological Sciences, Hitachinaka, Ibaraki (Japan). Lab. for Radioecology

2001-12-01

Remediation of soil and drinking water contaminated with radioactive nuclides is important for the mitigation of radiation exposure. Then we attempted to construct the remediation system including the dose estimation system using the chemical separation technique to remove pollutants from the environment. The information on air dose rate is important for assessment of risk from the radiation exposure. Then we measured the air dose rate and analysed the relationship between air dose rate and the contamination of soil at the area in Russia (Bryansk district) contaminated by Chernobyl Nuclear Power Plant accident. Moreover, we analysed the soil of Bryansk district on the concentration of rare earth elements, thorium and uranium and on the isotope ratio of strontium. On the other hand, we tried to develop the rapid measurement method of radioactivity of Sr-90 which is one of the dangerous radionuclides, because the method of radioactivity measurement in the literature is too time-consuming. It was reported recently that the molecules containing SH group form the covalent bond with gold atoms at the surface of gold plate and that crown ether compounds have strong affinity to strontium. Then we attempted to synthesize the crown ether containing SH group. In addition, we search the inorganic elements accumulated to special organisms of fishes and other animals in sea in order to find out new reagent for trace elements. Transition metal such as Co, Fe, Ni, Ti, V and Zn were detected from the intracellular granules in the bronchial heart of octopus. (author)

Radioactive dust from No. 5 Fukuryu Maru

Energy Technology Data Exchange (ETDEWEB)

Yamatera, H

1954-01-01

Analysis of radioactive dust collected on board No. 5 Fukuryu Maru were done by chemical separation and measurement of ..gamma..-ray energy and half-life of each species. Results are summarized as follows, radioactive nuclide and approximate percentage of radioactivity given: /sup 103/Ru, 4.3 to 57; /sup 106/Ru, 1.4; /sup 129/Te, 1.3; /sup 131/I, 4.5; /sup 132/I, 1.0; /sup 132/Te, 1.0; etc.

Chemistry and technology of radioactive waste management - the IAEA perspective

International Nuclear Information System (INIS)

Efremenkov, V.M.; )

2003-01-01

The paper refers the consideration of chemical composition of radioactive waste in selection of particular method and technology for waste treatment and conditioning, importance of physico-chemical parameters of waste processing techniques for optimisation of waste processing to produce waste form of appropriate quality. Consideration of waste chemistry is illustrated by several IAEA activities on radioactive waste management and by outlining the scope of some selected technical reports on different waste management subjects. Different components of the IAEA activities on radioactive waste management and on technology transfer are presented and discussed. (author)

Current Reactor Physics Benchmark Activities at the Idaho National Laboratory

International Nuclear Information System (INIS)

Bess, John D.; Marshall, Margaret A.; Gorham, Mackenzie L.; Christensen, Joseph; Turnbull, James C.; Clark, Kim

2011-01-01

The International Reactor Physics Experiment Evaluation Project (IRPhEP) (1) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) (2) were established to preserve integral reactor physics and criticality experiment data for present and future research. These valuable assets provide the basis for recording, developing, and validating our integral nuclear data, and experimental and computational methods. These projects are managed through the Idaho National Laboratory (INL) and the Organisation for Economic Co-operation and Development Nuclear Energy Agency (OECD-NEA). Staff and students at the Department of Energy - Idaho (DOE-ID) and INL are engaged in the development of benchmarks to support ongoing research activities. These benchmarks include reactors or assemblies that support Next Generation Nuclear Plant (NGNP) research, space nuclear Fission Surface Power System (FSPS) design validation, and currently operational facilities in Southeastern Idaho.

Nuclear activated cw chemical laser

International Nuclear Information System (INIS)

Roberts, T.G.

1982-01-01

A cw chemical laser which uses processed radioactive waste to produce active atoms from a chemically inactive gas before being mixed with another molecule such as hydrogen or deuterium is disclosed. This laser uses no toxic or corrosive fuels and does not require any electrical or other type of auxiliary power supply. The energy released by the radioactive material is used to produce the active atoms such as fluorine. This is accomplished by using the radiation products from processed radioactive waste to dissociate the inert gas in the plenum of the laser. The radioactive material is held in the passageway walls of a device similar to a heat exchanger. The exchanger device may be located in the gas generator section of a chemical laser. The inactive gas is passed through the exchanger device and while passing through it the radiation from the radioactive material dissociates the gas, producing a concentration of free active atoms. This active atom generator then feeds the nozzle bank or mixing section of a laser to produce a lasing action

Methodology development for radioactive waste treatment of CDTN/BR - liquid low-level radioactive wastes

International Nuclear Information System (INIS)

Morais, Carlos Antonio de

1996-01-01

The radioactive liquid wastes generated in Nuclear Technology Development Centre (CDTN) were initially treated by precipitation/filtration and then the resulting wet solid wastes were incorporated in cement. These wastes were composed of different chemicals and different radioactivities and were generated by different sectors. The objective of the waste treatment method was to obtain minimum wet solid waste volume and decontamination and minimum operational cost. The composition of the solid wastes were taken into consideration for compatible cementation process. Approximately 5,400 litres of liquid radioactive wastes were treated by this process during 1992-1995. The volume reduction was 1/24 th and contained 20% solids. (author)

A comparative study of changes in immunological reactivity during prolonged introduction of radioactive and chemical substances into the organism with drinking water

International Nuclear Information System (INIS)

Shubik, V.M.; Nevstrueva, M.A.; Kalnitskij, S.A.; Livshits, R.E.; Merkushev, G.N.; Pilshchik, E.M.; Ponomareva, T.V.

1978-01-01

A comparative study was conducted into the factors of non-specific protection and specific immunity, allergic and autoallergic reactivities during prolonged exposure of experimental animals to 6 different radioactive and 7 harmful chemical substances. Qualitative and quantitative peculiarities were found in the changes in immunological reactivity during the exposure of the organism to radionuclides and stable chemical compounds. Impairment of immunity plays an essential role in the course and the outcome of effects induced by chronic action of the substances examined. (author)

Quality checking of radioactive and hazardous waste

International Nuclear Information System (INIS)

Billington, D.M.; Burgoyne, S.M.J.; Dale, C.J.

1992-01-01

This report describes the work of the HMIP Waste Quality Checking Laboratory (WQCL) for the period September 1989 -August 1991. The WQCL has conducted research and development of procedures for the receipt, sampling and analysis of low level solid radioactive waste (LLW), intermediate level radioactive waste (ILW) and hazardous chemical waste (HW). Operational facilities have been commissioned for quality checking both LLW and HW. Waste quality checking has been completed on LLW packages seized from the UK waste disposal route by HMIP Inspectors. Packages have ranged in size from the 200 litre steel drum to half-height ISO freight container. Development work was continued on methods of sample extraction and radio-chemical analysis for cement encapsulated ILW in the form of magnox, graphite and stainless steel. This work was undertaken on non-radioactive simulants. (author)

Idaho Batholith Study Area Density Grid

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — A 2 kilometer terrace-density grid for the Idaho batholith study area. Number of columns is 331 and number of rows is 285. The order of the data is from the lower...

Technology evaluation report for the Buried Waste Robotics Program Subsurface Mapping Project

International Nuclear Information System (INIS)

Griebenow, B.E.

1992-01-01

This document presents a summary of the work performed in support of the Buried Waste Robotics Program Subsurface Mapping Project. The project objective was to demonstrate the feasibility of remotely characterizing buried waste sites. To fulfill this objective, a remotely-operated vehicle, equipped with several sensors, was deployed at the Idaho National Engineering Laboratory. Descriptions of the equipment and areas involved in the project are included in this report. Additionally, this document provides data that was obtained during characterization operations at the Cold Test Pit and the Subsurface Disposal Area, both at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex, and at the Idaho Chemical Processing Plant. The knowledge gained from the experience, that can be applied to the next generation remote-characterization system, is extensive and is presented in this report

36 CFR 294.23 - Road construction and reconstruction in Idaho Roadless Areas.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Road construction and..., DEPARTMENT OF AGRICULTURE SPECIAL AREAS Idaho Roadless Area Management § 294.23 Road construction and... Significance, or Primitive. Road construction and reconstruction are prohibited in Idaho Roadless Areas...

Laboratory scale vitrification of low-level radioactive nitrate salts and soils from the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Shaw, P.; Anderson, B.

1993-07-01

INEL has radiologically contaminated nitrate salt and soil waste stored above and below ground in Pad A and the Acid Pit at the Radioactive Waste Management Complex. Pad A contain uranium and transuranic contaminated potassium and sodium nitrate salts generated from dewatered waste solutions at the Rocky Flats Plant. The Acid Pit was used to dispose of liquids containing waste mineral acids, uranium, nitrate, chlorinated solvents, and some mercury. Ex situ vitrification is a high temperature destruction of nitrates and organics and immobilizes hazardous and radioactive metals. Laboratory scale melting of actual radionuclides containing INEL Pad A nitrate salts and Acid Pit soils was performed. The salt/soil/additive ratios were varied to determine the range of glass compositions (resulted from melting different wastes); maximize mass and volume reduction, durability, and immobilization of hazardous and radioactive metals; and minimize viscosity and offgas generation for wastes prevalent at INEL and other DOE sites. Some mixtures were spiked with additional hazardous and radioactive metals. Representative glasses were leach tested and showed none. Samples spiked with transuranic showed low nuclide leaching. Wasteforms were two to three times bulk densities of the salt and soil. Thermally co-processing soils and salts is an effective remediation method for destroying nitrate salts while stabilizing the radiological and hazardous metals they contain. The measured durability of these low-level waste glasses approached those of high-level waste glasses. Lab scale vitrification of actual INEL contaminated salts and soils was performed at General Atomics Laboratory as part of the INEL Waste Technology Development and Environmental Restoration within the Buried Waste Integrated Demonstration Program

Lessons to be learned from radioactive waste disposal practices for non-radioactive hazardous waste management

International Nuclear Information System (INIS)

Merz, E.R.

1991-01-01

The criteria to be set up for any kind of hazardous waste disposal must always be put in perspective: 1. what are the waste characteristics? 2. what time period for safe isolation is of interest? 3. which geological disposal alternatives exist? Different approaches may be used in the short- and long-term perspective. In either case, a general procedure is recommended which involves concentrating, containing and isolating the source of toxicity, both radioactive and chemotoxic substances, as far as practicable. Waste characterization of either chemotoxic or radioactive wastes should be performed applying comparable scientifically based principles. The important question which arises is whether their hazard potential can be quantified on the basis of dose comparison regarding the morbidity effects of radiation and of chemical pollutants. Good control over the consequences of hazardous waste disposal requires threat detailed criteria for tolerable contamination of radioactive as well as chemical pollutants should be established, and that compliance with these criteria can be demonstrated. As yet, there are no well developed principles for assessing the detriment from most types of genotoxic waste other than radioactive material. The time horizon discussed for both categories of waste for their proof of safe isolation differs by a factor of about one hundred. (au)

Chemical decontamination of stainless steel

International Nuclear Information System (INIS)

Onuma, Tsutomu; Akimoto, Hidetoshi

1991-01-01

The present invention concerns a method for chemical decontamination of radioactive metal waste materials contaminated with radioactive materials on the surface, generated in radioactive materials-handling facilities. The invention is comprised of a method of chemical decontamination of stainless steel, characterized by comprising a first process of immersing a stainless steel-based metal waste material contaminated by radioactive materials on the surface in a sulfuric acid solution and second process of immersing in an aqueous solution of sulfuric acid and oxidizing metal salt, in which a portion of the surface of the stainless steel to be decontaminated is polished mechanically to expose a portion of the base material before the above first and second processes. 1 figs., 2 tabs

U.S. hydropower resource assessment for Idaho

Energy Technology Data Exchange (ETDEWEB)

Conner, A.M.; Francfort, J.E.

1998-08-01

The US Department of Energy is developing an estimate of the undeveloped hydropower potential in the US. The Hydropower Evaluation Software (HES) is a computer model that was developed by the Idaho National Engineering and Environmental Laboratory for this purpose. HES measures the undeveloped hydropower resources available in the US, using uniform criteria for measurement. The software was developed and tested using hydropower information and data provided by the Southwestern Power Administration. It is a menu-driven program that allows the personal computer user to assign environmental attributes to potential hydropower sites, calculate development suitability factors for each site based on the environmental attributes present, and generate reports based on these suitability factors. This report describes the resource assessment results for the State of Idaho.

Cleaning and Decontamination Using Strippable and Protective Coatings at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

Tripp, J.; Archibald, K.; Lauerhass, L.; Argyle, M.; Demmer, R.

1999-01-01

The Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Liquid Waste Reduction (RLWR) group is conducting a testing and evaluation program on strippable and protective coatings. The purpose of the program is to determine how and where these coatings can be used to aid in the minimization of liquid waste generation. These coatings have become more important in daily operations because of the increased concern of secondary liquid waste generation at the INEEL. Several different strippable and protective coatings were investigated by the RLWR group, including Pentek 604, Bartlett (TLC), and ALARA 1146. During the tests quantitative data was determined, such as effectiveness at reducing contamination levels, or costs, as well as some qualitative data on issues like ease of application or removal. PENTEK 604 and Bartlett TLC are seen as superior products with slightly different uses

Map Showing Geologic Terranes of the Hailey 1°x2° Quadrangle and the western part of the Idaho Falls 1°x2° Quadrangle, south-central Idaho

Data.gov (United States)

Department of the Interior — The paper version of Map Showing Geologic Terranes of the Hailey 1°x2° Quadrangle and the western part of the Idaho Falls 1°x2° Quadrangle, south-central Idaho was...

Idaho National Laboratory Site Environmental Monitoring Plan

Energy Technology Data Exchange (ETDEWEB)

Nordstrom, Jenifer [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-02-01

This plan provides a high-level summary of environmental monitoring performed by various organizations within and around the Idaho National Laboratory (INL) Site as required by U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management, and DOE Order 458.1, Radiation Protection of the Public and the Environment, Guide DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance, and in accordance with 40 Code of Federal Regulations (CFR) 61, National Emission Standards for Hazardous Air Pollutants. The purpose of these orders is to 1) implement sound stewardship practices that protect the air, water, land, and other natural and cultural resources that may be impacted by DOE operations, and 2) to establish standards and requirements for the operations of DOE and DOE contractors with respect to protection of the environment and members of the public against undue risk from radiation. This plan describes the organizations responsible for conducting environmental monitoring across the INL Site, the rationale for monitoring, the types of media being monitored, where the monitoring is conducted, and where monitoring results can be obtained. Detailed monitoring procedures, program plans, or other governing documents used by contractors or agencies to implement requirements are referenced in this plan. This plan covers all planned monitoring and environmental surveillance. Non-routine activities such as special research studies and characterization of individual sites for environmental restoration are outside the scope of this plan.

Analysis of the impacts of the 1984 Resource Conservation and Recovery Act amendments on the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Falconer, K.L.; Davis, K.D.; Johnson, R.D.; Nishimoto, D.D.; Wallace, M.T.

1986-02-01

The November 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) have had, and will continue to have, a significant impact on the management of hazardous and radioactive mixed waste at the Idaho National Engineering Laboratory (INEL). These Amendments include new requirements specific to federal facilities such as the INEL. In this paper, areas of direct impact and associated INEL plans for complying with the 1984 RCRA Amendments will be described. The specific areas to be covered are the following: (1) changes in RCRA Part B permitting, including requirements for addressing past hazardous waste TSD sites; (2) the effects of increased restrictions on land disposal; (3) new requirements for undergrond tanks; (4) requirements for federal facilities; and (5) mandatory minimization of waste generation

Transboundary radioactive and chemical pollution simulation using an atmospheric/marine predicting system

International Nuclear Information System (INIS)

Telenta, B.; Antic, D.

2001-01-01

The atmospheric models can be used to simulate the transport of contaminants in typical accidental cases and for realistic meteorological conditions. Some numerical models for weather forecast can be used for near to real simulations of propagation of radioactive nuclides or classical chemical pollutants to the atmosphere. The various meteorological parameters are taken into account and various meteorological conditions, even complex ones, can be analyzed. The models can be used for very well assessment of the airborne pollution from energy sources and industrial installations, for comparative studies and for safety analysis. This report describes an proposal for a project of the transboundary pollution simulation, that can be used for the East Mediterranean Region. The project is based on the numerical models developed in the in simulating of the Chernobyl accident and similar hypothetical cases. The study is based on an atmospheric models developed in Euro-Mediterranean Centre on Insular Coastal Dynamics (ICoD), Foundation for International Studies, Valeta, Malta

Direct cementitious waste option study report

International Nuclear Information System (INIS)

Dafoe, R.E.; Losinski, S.J.

1998-02-01

A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target data of 2035. This study investigates the direct grouting of all ICPP calcine (including the HLW dry calcine and those resulting from calcining sodium-bearing liquid waste currently residing in the ICPP storage tanks) as the treatment method to comply with the settlement agreement. This method involves grouting the calcined waste and casting the resulting hydroceramic grout into stainless steel canisters. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a national geologic repository. The operating period for grouting treatment will be from 2013 through 2032, and all the HLW will be treated and in interim storage by the end of 2032

Direct cementitious waste option study report

Energy Technology Data Exchange (ETDEWEB)

Dafoe, R.E.; Losinski, S.J.

1998-02-01

A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target data of 2035. This study investigates the direct grouting of all ICPP calcine (including the HLW dry calcine and those resulting from calcining sodium-bearing liquid waste currently residing in the ICPP storage tanks) as the treatment method to comply with the settlement agreement. This method involves grouting the calcined waste and casting the resulting hydroceramic grout into stainless steel canisters. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a national geologic repository. The operating period for grouting treatment will be from 2013 through 2032, and all the HLW will be treated and in interim storage by the end of 2032.

Study of chemical additives in the cementation of radioactive waste of PWR reactors

International Nuclear Information System (INIS)

Vieira, Vanessa Mota; Tello, Cledola Cassia Oliveira de

2012-01-01

In this research it has been studied the effects of chemical admixtures in the cementation process of radioactive wastes. These additives are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market. Then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 23. The measured parameters were: the viscosity, the setting time, the paste and product density and the compressive strength. The parameter evaluated in this study was the compressive strength at age of 28 days, is considered essential security issues relating to the handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented products. (author)

Comparison of actual and predicted routes used in the shipment of radioactive materials

International Nuclear Information System (INIS)

Joy, D.S.; Johnson, P.E.; Harrison, I.G.

1985-01-01

A number of highway controlled shipments of radioactive materials have been made over the past several years. An excellent example showing the variability of actual routes is the transfer of 45 shipments between the Three Mile Island reactor in Pennsylvania and Scoville, Idaho in 1982 and 1983. Six different routes varying between 2273 and 2483 miles were used. Approximately 75% of these shipments followed a common route which passed through ten Urbanized Areas, defined by the Census Bureau as having a population exceeding 100,000 people. Other routes, while shorter in distance, passed through as many as 14 Urbanized Areas. Routes predicted by the Oak Ridge routing model did not exactly duplicate actual routes used. However, the analysis shows that the routing model does make a good estimate of transportation routes actually chosen by shippers of radioactive materials. In actual practice, a number of factors (weather, road conditions, driver preference, etc.) influence the actual route taken. 5 refs., 1 fig., 1 tab

Source, transport and dumping of radioactive waste

International Nuclear Information System (INIS)

1980-03-01

The results of an examination into the problems of radioactive waste are presented, in particular the sources, transport and dumping and the policy considerations in favour of specific methods. The theoretical background of radioactive waste is described, including the physical and chemical, ecological, medical and legal aspects. The practical aspects of radioactive waste in the Netherlands are considered, including the sources, the packaging and transport and dumping in the Atlantic Ocean. The politics and policies involved in this process are outlined. (C.F.)

Action Memorandum for the Engineering Test Reactor under the Idaho Cleanup Project

Energy Technology Data Exchange (ETDEWEB)

A. B. Culp

2007-01-26

This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared adn released for public comment. The scope of this Action Memorandum is to encompass the final end state of the Complex and disposal of the Engineering Test Reactor vessol. The selected removal action includes removing and disposing of the vessel at the Idaho CERCLA Disposal Facility and demolishing the reactor building to ground surface.

Radioactive waste today - an asset tomorrow

Energy Technology Data Exchange (ETDEWEB)

Holmstrand, M. [Norwegian Radiation Protection Authority (Norway)

2014-07-01

Mining of Rare Earth Elements (REE) causes radioactive pollution, as ores which contain REE also contain an elevated concentration of naturally occurring radioactive materials (NORM). Wastes from REE mining are therefore regarded as being inherently radioactive. One of the potential economically viable REE resources in Norway is in the Fensfield area in Telemark County, which is recognized as one of the world's largest thorium resources. If REE was mined in this area, a large volume of radioactive waste would be created. The authorities would then need to know how to regulate the waste so that the environmental impact would be as low as reasonably achievable when societal and economic factors having been accounted for (ALARA). Radioactive pollution from REE tailings could be a threat to the environment, biota and humans. However, naturally occurring thorium is practically not mobile nor bioavailable and has a relatively low specific activity and might therefore safely be deposited in a landfill. An environmental risk assessment should be used to evaluate if it is justifiable to deposit the radioactive tailings in a landfill or if alternative ways of handling, such as extraction of thorium in addition to extraction of REE from the ore, might be better. The risk assessment must start with a source term, the native carbonatite rocks, and an investigation on how the chemical properties of the rock changes when it's milled and treated with chemicals. Changes in the physical and chemical properties and changes in the environment where the processed rock are deposited might mobilize and/or make thorium bioavailable, thus increasing the environmental risk. Removal of thorium from the raw materials or tailings from the REE mining industry prior to deposition could be seen as one form of environmental protection with many benefits, for instance reducing the potential of external and internal radiation in biota and humans. We could also speculate about the

Potential dispositioning flowsheets for ICPP SNF and wastes

Energy Technology Data Exchange (ETDEWEB)

Olson, A.L. [ed.; Anderson, P.A.; Bendixsen, C.L. [and others

1995-11-01

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation`s radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995.

Potential dispositioning flowsheets for ICPP SNF and wastes

International Nuclear Information System (INIS)

Olson, A.L.; Anderson, P.A.; Bendixsen, C.L.

1995-11-01

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation's radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995

An update of hydrologic conditions and distribution of selected constituents in water, eastern Snake River Plain aquifer and perched groundwater zones, Idaho National Laboratory, Idaho, emphasis 2012-15

Science.gov (United States)

Bartholomay, Roy C.; Maimer, Neil V.; Rattray, Gordon W.; Fisher, Jason C.

2017-04-10

Since 1952, wastewater discharged to in ltration ponds (also called percolation ponds) and disposal wells at the Idaho National Laboratory (INL) has affected water quality in the eastern Snake River Plain (ESRP) aquifer and perched groundwater zones underlying the INL. The U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, maintains groundwater-monitoring networks at the INL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer and in perched groundwater zones. This report presents an analysis of water-level and water-quality data collected from the ESRP aquifer, multilevel monitoring system (MLMS) wells in the ESRP aquifer, and perched groundwater wells in the USGS groundwater monitoring networks during 2012-15.

Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

1982-05-01

In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

Treatment, Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant; Traitement et Elimination Future des Dechets Radioactifs a l'Usine de Traitement Chimique de L'Idaho; 0410 041d 0414 ; Tratamiento y Evacuacion de Desechos Radiactivos en la Planta de Tratamiento Quimico de Idaho

Energy Technology Data Exchange (ETDEWEB)

Stevens, James I. [Phillips Petroleum Company, Atomic Energy Division, Idaho Falls (United States)

1960-07-01

Acidic wastes from the recovery of enriched uranium from aluminium, zirconium, and stainless-steel fuels at the Idaho Chemical Processing Plant are stored in underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste-tank farm as well as the methods of environmental disposal of low-level wastes is described. The ''concentrate and contain'' philosophy of waste disposal has as its ultimate aim the production of a solid mass containing the fission products. The disadvantage of increased treatment costs may or may not be offset by reduction in storage costs. The low thermal conductivity of solids makes storage temperature considerations more important than for liquids. The acid aluminium nitrate wastes from the processing of fuels of the Material Testing Reactor type may be converted to granular alumina by calcining in a fluidized bed from 350 Degree-Sign to 550 Degree-Sign C. The major process components are the NaK heated calciner, an off-gas cleaning system and the solids storage vessels. The process design and the research and development programme are reviewed. On the basis of the successful demonstration of fluidized-bed calcining and high-temperature solids storage in conjunction with other considerations, a number of future storage concepts and their environmental connotations are discussed. (author) [French] A l'usine de traitement chimique de l'Idaho, les dechets acides provenant de la recuperation de l'uranium enrichi contenu dans les cartouches de combustible en aluminium, zirconium, et acier inoxydable sont stockes dans des reservoirs souterrains de deux formes differentes et d'une capacite theorique de 30,000 et de 300,000 gallons. L'auteur donne une description du plan et du fonctionnement de l'annexe ou se trouvent les reservoirs a dechets, ainsi que des methodes d'elimination des dechets de faible activite dans le milieu ambiant. Le but meme du systeme qui consiste a concentrer et a

Geothermal Reservoir Temperatures in Southeastern Idaho using Multicomponent Geothermometry

Energy Technology Data Exchange (ETDEWEB)

Neupane, Ghanashyam [Idaho National Lab. (INL) and Center for Advanced Energy Studies, Idaho Falls, ID (United States); Mattson, Earl D. [Idaho National Lab. (INL) and Center for Advanced Energy Studies, Idaho Falls, ID (United States); McLing, Travis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Center for Advanced Energy Studies; Palmer, Carl D. [Univ. of Idaho, Idaho Falls, ID (United States); Smith, Robert W. [Univ. of Idaho and Center for Advanced Energy Studies, Idaho Falls, ID (United States); Wood, Thomas R. [Univ. of Idaho and Center for Advanced Energy Studies, Idaho Falls, ID (United States); Podgorney, Robert K. [Idaho National Lab. (INL) and Center for Advanced Energy Studies, Idaho Falls, ID (United States)

2015-03-01

Southeastern Idaho exhibits numerous warm springs, warm water from shallow wells, and hot water within oil and gas test wells that indicate a potential for geothermal development in the area. Although the area exhibits several thermal expressions, the measured geothermal gradients vary substantially (19 – 61 ºC/km) within this area, potentially suggesting a redistribution of heat in the overlying ground water from deeper geothermal reservoirs. We have estimated reservoir temperatures from measured water compositions using an inverse modeling technique (Reservoir Temperature Estimator, RTEst) that calculates the temperature at which multiple minerals are simultaneously at equilibrium while explicitly accounting for the possible loss of volatile constituents (e.g., CO2), boiling and/or water mixing. Compositions of a selected group of thermal waters representing southeastern Idaho hot/warm springs and wells were used for the development of temperature estimates. The temperature estimates in the the region varied from moderately warm (59 ºC) to over 175 ºC. Specifically, hot springs near Preston, Idaho resulted in the highest temperature estimates in the region.

Geothermal Reservoir Temperatures in Southeastern Idaho using Multicomponent Geothermometry

International Nuclear Information System (INIS)

Neupane, Ghanashyam; Mattson, Earl D.; McLing, Travis L.; Smith, Robert W.; Wood, Thomas R.; Podgorney, Robert K.

2015-01-01

Southeastern Idaho exhibits numerous warm springs, warm water from shallow wells, and hot water within oil and gas test wells that indicate a potential for geothermal development in the area. Although the area exhibits several thermal expressions, the measured geothermal gradients vary substantially (19 - 61 °C/km) within this area, potentially suggesting a redistribution of heat in the overlying ground water from deeper geothermal reservoirs. We have estimated reservoir temperatures from measured water compositions using an inverse modeling technique (Reservoir Temperature Estimator, RTEst) that calculates the temperature at which multiple minerals are simultaneously at equilibrium while explicitly accounting for the possible loss of volatile constituents (e.g., CO2), boiling and/or water mixing. Compositions of a selected group of thermal waters representing southeastern Idaho hot/warm springs and wells were used for the development of temperature estimates. The temperature estimates in the the region varied from moderately warm (59 °C) to over 175 °C. Specifically, hot springs near Preston, Idaho resulted in the highest temperature estimates in the region.

Potential hydrothermal resource temperatures in the Eastern Snake River Plain, Idaho

Energy Technology Data Exchange (ETDEWEB)

Ghanashayam Neupane; Earl D. Mattson; Cody J. Cannon; Trevor A. Atkinson; Travis L. McLing; Thomas R. Wood; Patrick F. Dobson; Mark E. Conrad

2016-02-01

The Eastern Snake River Plain (ESRP) in southern Idaho is a region of high heat flow. Sustained volcanic activities in the wake of the passage of the Yellowstone Hotspot have turned this region into an area with great potential for geothermal resources as evidenced by numerous hot springs scattered along the margins of the plain and several hot-water producing wells and hot springs within the plain. Despite these thermal expressions, it is hypothesized that the pervasive presence of an overlying groundwater aquifer in the region effectively masks thermal signatures of deep-seated geothermal resources. The dilution of deeper thermal water and re-equilibration at lower temperature are significant challenges for the evaluation of potential resource areas in the ESRP. Over the past several years, we collected approximately 100 water samples from springs/wells for chemical analysis as well as assembled existing water chemistry data from literature. We applied several geothermometric and geochemical modeling tools to these chemical compositions of ESRP water samples. Geothermometric calculations based on principles of multicomponent equilibrium geothermometry with inverse geochemical modeling capability (e.g., Reservoir Temperature Estimator, RTEst) have been useful for the evaluation of reservoir temperatures. RTEst geothermometric calculations of ESRP thermal water samples indicated numerous potential geothermal areas with elevated reservoir temperatures. Specifically, areas around southern/southwestern side of the Bennett Hills and within the Camas Prairies in the western-northwestern regions of the ESRP and its margins suggest temperatures in the range of 140-200°C. In the northeastern portions of the ESRP, Lidy Hot Springs, Ashton, Newdale, and areas east of Idaho Falls have expected reservoir temperature =140 °C. In the southern ERSP, areas near Buhl and Twin Falls are found to have elevated temperatures as high as 160 °C. These areas are likely to host

Naturally Occurring Radioactive Materials (NORM)

International Nuclear Information System (INIS)

Gray, P.

1997-01-01

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training)

Naturally Occurring Radioactive Materials (NORM)

Energy Technology Data Exchange (ETDEWEB)

Gray, P. [ed.

1997-02-01

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).

Performance assessment handbook for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Seitz, R.R.; Garcia, R.S.; Kostelnik, K.M.; Starmer, R.J.

1992-02-01

Performance assessments of proposed low-level radioactive waste disposal facilities must be conducted to support licensing. This handbook provides a reference document that can be used as a resource by management and staff responsible for performance assessments. Brief discussions describe the performance assessment process and emphasize selected critical aspects of the process. References are also provided for additional information on many aspects of the performance assessment process. The user's manual for the National Low-Level Waste Management Program's Performance Assessment Center (PAC) on the Idaho National Engineering Laboratory Cray computer is included as Appendix A. The PAC provides users an opportunity to experiment with a number of performance assessment computer codes on a Cray computer. Appendix B describes input data required for 22 performance assessment codes

The variation of organ doses with the particle size and chemical form of an inhaled radioactive aerosol

International Nuclear Information System (INIS)

Hunt, B.W.; Adams, N.; Reissland, J.A.

1979-04-01

In this report, radiation doses to organs are calculated as a function of the particle size of the inhaled radioactive material. Aerosols with an Activity Median Aerodynamic Diameter (AMAD) from 0.1 μm to 20 μm are considered and doses accumulated by various organs in periods ranging from 1 day to 70 years are given for 65 radionuclides. A computer program is used which calculates the transformations taking place in each organ per curie of inhaled nuclide from the basic radioactivity and metabolic data. The program also calculates the resulting doses both for the organ in which the transformations occur and from penetrating radiation emitted as a result of transformations in other organs. The effects of particle size and chemical form of the nuclides on the doses received by organs are discussed. Tables of doses accumulated by 10 specific organs and other organs together with effective whole body doses are given for particle sizes 0.1 μm, 1 μm and 10 μm (AMAD). (author)

Idaho Habitat/Natural Production Monitoring Part I, 1995 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Hall-Griswold, J.A.; Petrosky, C.E. (Idaho Department of Fish and Game, Boise, ID)

1996-12-01

The Idaho Department of Fish and Game (IDFG) has been monitoring trends in juvenile spring and summer chinook salmon, Oncorhynchus tshawytscha, and steelhead trout, O. mykiss, populations in the Salmon, Clearwater, and lower Snake River drainages for the past 12 years. This work is the result of a program to protect, mitigate, and enhance fish and wildlife affected by the development and operation of hydroelectric power plants on the Columbia River. Project 91-73, Idaho Natural Production Monitoring, consists of two subprojects: General Monitoring and Intensive Monitoring. This report updates and summarizes data through 1995 for the General Parr Monitoring (GPM) database to document status and trends of classes of wild and natural chinook salmon and steelhead trout populations. A total of 281 stream sections were sampled in 1995 to monitor trends in spring and summer chinook salmon Oncorhynchus tshawytscha and steelhead trout O. mykiss parr populations in Idaho. Percent carrying capacity and density estimates were summarized for 1985--1995 by different classes of fish: wild A-run steelhead trout, wild B-run steelhead trout, natural A-run steelhead trout, natural B-run steelhead trout, wild spring and summer chinook salmon, and natural spring and summer chinook salmon. The 1995 data were also summarized by subbasins as defined in Idaho Department of Fish and Game`s 1992--1996 Anadromous Fish Management Plan.

Idaho habitat/natural production monitoring: Part 1. Annual report 1995