Sample records for ineel

  1. Air Emission Inventory for the INEEL -- 1999 Emission Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Zohner, Steven K

    2000-05-01

    This report presents the 1999 calendar year update of the Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL Air Emission Inventory documents sources and emissions of nonradionuclide pollutants from operations at the INEEL. The report describes the emission inventory process and all of the sources at the INEEL, and provides nonradionuclide emissions estimates for stationary sources.

  2. Development of the INEEL Site Wide Vadose Zone Roadmap

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Yonk, Alan Keith

    2001-09-01

    The INEEL Vadose Zone Roadmap was developed to identify inadquacies in current knowledge, to assist in contaminant management capabilities relative to the INEEL vadose zone, and to ensure that ongoing and planned Science and Technology developments will meet the risk management challenges facing the INEEL in coming years. The primary objective of the Roadmap is to determine the S&T needs that will facilitate monitoring, characterization, prediction, and assessment activities necessary to support INEEL risk management decisions and to ensure that long-term stewardship of contaminated sites at the INEEL is achieved. The mission of the Roadmap is to insure that themore » long-term S&T strategy is aligned with site programs, that it takes advantage of progress made to date, and that it can assist in meeting the milestones and budgets of operations.« less

  3. Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory - Calendar Year 1999 Emission Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Zohner, S.K.

    2000-05-30

    This report presents the 1999 calendar year update of the Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL Air Emission Inventory documents sources and emissions of nonradionuclide pollutants from operations at the INEEL. The report describes the emission inventory process and all of the sources at the INEEL, and provides nonradionuclide emissions estimates for stationary sources.

  4. Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory - Calendar Year 1998 Emissions Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    S. K. Zohner

    1999-10-01

    This report presents the 1998 calendar year update of the Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL Air Emission Inventory documents sources and emissions of nonradionuclide pollutants from operations at the INEEL. The report describes the emission inventory process and all of the sources at the INEEL, and provides nonradiological emissions estimates for stationary sources.

  5. INEEL Subregional Conceptual Model Report Volume 2: Summary of Existing Knowledge of Geochemical Influences on the Fate and Transport of Contaminants in the Subsurface at the INEEL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Paul L. Wichlacz; Robert C. Starr; Brennon Orr

    2003-09-01

    This document summarizes previous descriptions of geochemical system conceptual models for the vadose zone and groundwater zone (aquifer) beneath the Idaho National Engineering and Environmental Laboratory (INEEL). The primary focus is on groundwater because contaminants derived from wastes disposed at INEEL are present in groundwater, groundwater provides a pathway for potential migration to receptors, and because geochemical characteristics in and processes in the aquifer can substantially affect the movement, attenuation, and toxicity of contaminants. The secondary emphasis is perched water bodies in the vadose zone. Perched water eventually reaches the regional groundwater system, and thus processes that affect contaminants inmore » the perched water bodies are important relative to the migration of contaminants into groundwater. Similarly, processes that affect solutes during transport from nearsurface disposal facilities downward through the vadose zone to the aquifer are relevant. Sediments in the vadose zone can affect both water and solute transport by restricting the downward migration of water sufficiently that a perched water body forms, and by retarding solute migration via ion exchange. Geochemical conceptual models have been prepared by a variety of researchers for different purposes. They have been published in documents prepared by INEEL contractors, the United States Geological Survey (USGS), academic researchers, and others. The documents themselves are INEEL and USGS reports, and articles in technical journals. The documents reviewed were selected from citation lists generated by searching the INEEL Technical Library, the INEEL Environmental Restoration Optical Imaging System, and the ISI Web of Science databases. The citation lists were generated using the keywords ground water, groundwater, chemistry, geochemistry, contaminant, INEL, INEEL, and Idaho. In addition, a list of USGS documents that pertain to the INEEL was obtained and manually searched. The documents that appeared to be the most pertinent were selected from further review. These documents are tabulated in the citation list. This report summarizes existing geochemical conceptual models, but does not attempt to generate a new conceptual model or select the ''right'' model. This document is organized as follows. Geochemical models are described in general in Section 2. Geochemical processes that control the transport and fate of contaminants introduced into groundwater are described in Section 3. The natural geochemistry of the Eastern Snake River Plain Aquifer (SRPA) is described in Section 4. The effect of waste disposal on the INEEL subsurface is described in Section 5. The geochemical behavior of the major contaminants is described in Section 6. Section 7 describes the site-specific geochemical models developed for various INEEL facilities.« less

  6. Risk perception, future land use and stewardship: comparison of attitudes about Hanford Site and Idaho National Engineering and Environmental Laboratory.

    PubMed

    Burger, J; Sanchez, J; Roush, D; Gochfeld, M

    2001-04-01

    With the ending of the Cold War, the Department of Energy (DOE) is evaluating mission, future land use and stewardship of departmental facilities. This paper compares the environmental concerns and future use preferences of 351 people interviewed at Lewiston, Idaho, about the Hanford Site and Idaho National Engineering and Environmental Laboratory (INEEL), two of DOE's largest sites. Although most subjects lived closer to Hanford than INEEL, most resided in the same state as INEEL. Therefore their economic interests might be more closely allied with INEEL, while their health concerns might be more related to Hanford. Few lived close enough to either site to be directly affected economically. We test the null hypotheses that there are no differences in environmental concerns and future land-use preferences as a function of DOE site, sex, age and education. When asked to list their major concerns about the sites, more people listed human health and safety, and environmental concerns about Hanford compared to INEEL. When asked to list their preferred future land uses, 49% of subjects did not have any for INEEL, whereas only 35% did not know for Hanford. The highest preferred land uses for both sites were as a National Environmental Research Park (NERP), and for camping, hunting, hiking, and fishing. Except for returning the land to the tribes and increased nuclear storage, subjects rated all future uses as more preferred at INEEL than Hanford. Taken together, these data suggest that the people interviewed know more about Hanford, are more concerned about Hanford, rate recreational uses and NERP as their highest preferred land use, and feel that INEEL is more suited for most land uses than Handford. Overall rankings for future land uses were remarkably similar between the sites, indicating that for these stakeholders, DOE lands should be preserved for research and recreation. These preferences should be taken into account when planning for long-term stewardship at these two DOE sites.

  7. The Idaho National Engineering and Environmental Laboratory Source Water Assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sehlke, G.

    2003-03-17

    The Idaho National Engineering and Environmental Laboratory (INEEL) covers approximately 890 square miles and includes 12 public water systems that must be evaluated for Source water protection purposes under the Safe Drinking Water Act. Because of its size and location, six watersheds and five aquifers could potentially affect the INEEL's drinking water sources. Based on a preliminary evaluation of the available information, it was determined that the Big Lost River, Birch Creek, and Little Lost River Watersheds and the eastern Snake River Plain Aquifer needed to be assessed. These watersheds were delineated using the United States Geologic Survey's Hydrological Unitmore » scheme. Well capture zones were originally estimated using the RESSQC module of the Environmental Protection Agency's Well Head Protection Area model, and the initial modeling assumptions and results were checked by running several scenarios using Modflow modeling. After a technical review, the resulting capture zones were expanded to account for the uncertainties associated with changing groundwater flow directions, a this vadose zone, and other data uncertainties. Finally, all well capture zones at a given facility were merged to a single wellhead protection area at each facility. A contaminant source inventory was conducted, and the results were integrated with the well capture zones, watershed and aquifer information, and facility information using geographic information system technology to complete the INEEL's Source Water Assessment. Of the INEEL's 12 public water systems, three systems rated as low susceptibility (EBR-1, Main Gate, and Gun Range), and the remainder rated as moderate susceptibility. No INEEL public water system rated as high susceptibility. We are using this information to develop a source water management plan from which we will subsequently implement an INEEL-wide source water management program. The results are a very robust set of wellhead protection areas that will protect the INEEL's public water systems yet not too conservative to inhibit the INEEL from carrying out its missions.« less

  8. INEEL Subregional Conceptual Model Report; Volume 1 - Summary of Existing Knowledge of Natural and Anthropogenic Influences Governing Subsurface Contaminant Transport in the INEEL Subregion of the Eastern Snake River Plain

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wichlacz, Paul Louis; Orr, Brennan

    2002-08-01

    The National Research Council has defined a conceptual model as ''an evolving hypothesis identifying the important features, processes, and events controlling fluid flow and contaminant transport of consequence at a specific field site in the context of a recognized problem''. Presently, several subregional conceptual models are under development at the Idaho National Engineering and Environmental Laboratory (INEEL). Additionally, facility-specific conceptual models have been described as part of INEEL environmental restoration activities. Compilation of these models is required to develop a comprehensive conceptual model that can be used to strategically plan for future groundwater research activities at the INEEL. Conceptual modelsmore » of groundwater flow and contaminant transport at the INEEL include the description of the geologic framework, matrix hydraulic properties, and inflows and outflows. They also include definitions of the contaminant source term and contaminant transport mechanisms. The geologic framework of the INEEL subregion is described by the geometry of the system, stratigraphic units within the system, and structural features that affect groundwater flow and contaminant transport. These elements define geohydrologic units that make up the Snake River Plain Aquifer (SRPA). The United States Geological Survey (USGS) conceptual model encompasses approximately 1,920 mi2 of the eastern Snake River Plain. The Waste Area Group (WAG)-10 model includes the USGS area and additional areas to the northeast and southeast. Both conceptual models are bounded to the northwest by the Pioneer Mountains, Lost River Range, and Lemhi Mountains. They are bounded to the southeast by groundwater flow paths determined from aquifer water-level contours. The upgradient extent of the USGS model is a water-level contour that includes the northeastern boundary of the INEEL. The WAG-10 model includes more of the Mud Lake area to utilize previous estimates of underflow into the subregion. Both conceptual models extend approximately 25 miles to the southwest of the INEEL, a distance sufficient to include known concentrations of contaminant tracers. Several hypotheses have been developed concerning the effective thickness of the SRPA at the INEEL. The USGS model has defined the effective thickness from electrical resistivity and borehole data to be as much as 2,500 ft in the eastern part of the subregion and as much as 4,000 ft in the southwestern part. The WAG-10 model has developed two alternatives using aquifer-temperature and electrical resistivity data. The ''thick'' aquifer interpretation utilizes colder temperature data and includes a northtrending zone in which the thickness exceeds 1,300 ft and with a maximum thickness of 1,700 ft. The ''thin'' aquifer interpretation minimizes aquifer thickness, with thickness ranging from 328 to 1,300 ft. Facility-specific models generally have focused efforts on the upper 250 ft of saturation. Conceptual models have utilized a stratigraphic data set to define geohydrologic units within the INEEL subregion. This data set, compiled from geophysical logs and cores from boreholes, correlates the thick, complex stack of basalt flows across the subregion. Conceptual models generally concur that the upper geohydrologic unit consists of a section of highly fractured, multiple, thin basalt flows and sedimentary interbeds. Beneath this unit is an areally extensive, thick, unfractured basalt flow that rises above the water table southwest of the INEEL. The bottom unit consists of a thick section of slightly- to moderately-altered basalt. A key objective of the DOE water-integration project at the INEEL is to coordinate development of a subregional conceptual model of groundwater flow and contaminant transport that is based on the best available understanding of geologic and hydrologic features. The first step in this process is to compile and summarize the current conceptual models of groundwater flow and contaminant transport at the INEEL that have been developed from extensive geohydrologic studies conducted during the last 50 years.« less

  9. 24. CONSTRUCTION PROGRESS VIEW TO NORTHWEST, SHOWING BLOWER BUILDING. INEEL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    24. CONSTRUCTION PROGRESS VIEW TO NORTHWEST, SHOWING BLOWER BUILDING. INEEL PHOTO NUMBER NRTS-60-4407. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  10. 35. MISCELLANEOUS ARCHITECTURAL AND STRUCTURAL DETAILS. INEEL DRAWING NUMBER 200063300287106359. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    35. MISCELLANEOUS ARCHITECTURAL AND STRUCTURAL DETAILS. INEEL DRAWING NUMBER 200-0633-00-287-106359. FLUOR NUMBER 5775-CPP-633-A-9. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  11. 34. DOOR AND WINDOW DETAILS. INEEL DRAWING NUMBER 200063300287106358. FLUOR ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    34. DOOR AND WINDOW DETAILS. INEEL DRAWING NUMBER 200-0633-00-287-106358. FLUOR NUMBER 5775-CPP-633-A-8. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  12. 33. ROOF PLAN AND DETAILS. INEEL DRAWING NUMBER 200063300287106357. FLUOR ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    33. ROOF PLAN AND DETAILS. INEEL DRAWING NUMBER 200-0633-00-287-106357. FLUOR NUMBER 5775-CPP-633-A-7. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  13. 27. ELEVATIONS OF EAST AND WEST SIDES. INEEL DRAWING NUMBER ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    27. ELEVATIONS OF EAST AND WEST SIDES. INEEL DRAWING NUMBER 200-0633-00-287-106355. FLUOR NUMBER 5775-CPP-633-A-5. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  14. 28. NORTH AND SOUTH ELEVATIONS AND TWO SECTIONS. INEEL DRAWING ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    28. NORTH AND SOUTH ELEVATIONS AND TWO SECTIONS. INEEL DRAWING NUMBER 200-0633-00-287-106356. FLUOR NUMBER 5775-CPP-633-A-6. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  15. Several organic parameters on underlying hazardous constituents list can not be measured at the universal treatment standards

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Johnson, H.C.

    1998-07-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) has several permitted treatment, storage and disposal facilities. The INEEL Sample Management Office (SMO) conducts all analysis subcontracting activities for Department of Energy Environmental Management programs at the INEEL. In this role, the INEEL SMO has had the opportunity to subcontract the analyses of various wastes (including ash from an interim status incinerator) requesting a target analyte list equivalent to the constituents listed in 40 Code of Federal Regulations. These analyses are required to ensure that treated wastes do not contain underlying hazardous constituents (UHC) at concentrations greater than the universal treatmentmore » standards (UTS) prior to land disposal. The INEEL SMO has conducted a good-faith effort by negotiating with several commercial laboratories to identify the lowest possible quantitation and detection limits that can be achieved for the organic UHC analytes. The results of this negotiating effort has been the discovery that no single laboratory (currently under subcontract with the INEEL SMO) can achieve a detection level that is within an order of magnitude of the UTS for all organic parameters on a clean sample matrix (e.g., sand). This does not mean that there is no laboratory that can achieve the order of magnitude requirements for all organic UHCs on a clean sample matrix. The negotiations held to date indicate that it is likely that no laboratory can achieve the order of magnitude requirements for a difficult sample matrix (e.g., an incinerator ash). The authors suggest that the regulation needs to be revised to address the disparity between what is achievable in the laboratory and the regulatory levels required by the UTS.« less

  16. DOE Office of Scientific and Technical Information (OSTI.GOV)

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

    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 themore » 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 person-rem (437 person-Sv) population dose from background radioactivity.« less

  17. Technical Status Report: Preliminary Glass Formulation Report for INEEL HAW

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Peeler, D.; Reamer, I.; Vienna, J.

    1998-03-01

    This study was performed by a team comprising experts in glass chemistry, glass technology, and statistics at both SRTC and PNNL. This joint effort combined the strengths of each discipline and site to quickly develop a glass formulation for specific INEEL HAW.

  18. INEEL Subregional Conceptual Model Report Volume 3: Summary of Existing Knowledge of Natural and Anthropogenic Influences on the Release of Contaminants to the Subsurface Environment from Waste Source Terms at the INEEL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Paul L. Wichlacz

    2003-09-01

    This source-term summary document is intended to describe the current understanding of contaminant source terms and the conceptual model for potential source-term release to the environment at the Idaho National Engineering and Environmental Laboratory (INEEL), as presented in published INEEL reports. The document presents a generalized conceptual model of the sources of contamination and describes the general categories of source terms, primary waste forms, and factors that affect the release of contaminants from the waste form into the vadose zone and Snake River Plain Aquifer. Where the information has previously been published and is readily available, summaries of the inventorymore » of contaminants are also included. Uncertainties that affect the estimation of the source term release are also discussed where they have been identified by the Source Term Technical Advisory Group. Areas in which additional information are needed (i.e., research needs) are also identified.« less

  19. IET area plot and utilities plan. Includes drainage. Ralph M. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET area plot and utilities plan. Includes drainage. Ralph M. Parsons 902-4-ANP-U-310. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL code no. 035-0100-00-693-106898 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. ADM. Service Building (TAN603). Floor plan. Names of functional areas. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Service Building (TAN-603). Floor plan. Names of functional areas. Ralph M. Parsons 902-2-ANY-603-A 43. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 033-0603-00-693-106718 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. FET. Control and equipment building (TAN630). Sections. Ralph M. Parsons ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Control and equipment building (TAN-630). Sections. Ralph M. Parsons 1229-2 ANP/GE-5-630-A-4. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0630-00-693-107083 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  2. ADM. Warehouse (TAN604). Elevations and sections. Ralph M. Parsons 9022ANP604A ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Warehouse (TAN-604). Elevations and sections. Ralph M. Parsons 902-2-ANP-604-A 56. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0604-00-693-106728 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. ADM. Change House (TAN606). Elevations and floor plan. Room Names. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Change House (TAN-606). Elevations and floor plan. Room Names. Ralph M. Parsons 902-2-ANP-606-A 65. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0606-00-693-106733 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. FET. Exhaust duct and stack. Plan, elevation, foundation, details. Ralph ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Exhaust duct and stack. Plan, elevation, foundation, details. Ralph M. Parsons 1480-10 ANP/GE-5-716-S-3. Date: February 1959. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0716-00-693-107474 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. FET. Chlorination building, TAN637. Elevations, section. Ralph M. Parsons 12292 ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Chlorination building, TAN-637. Elevations, section. Ralph M. Parsons 1229-2 ANP/GE-5-637-A-S-H&V-1. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0637-00-693-107148 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. ADM. Warehouse (TAN604) Floor plan. General warehouse and chemical storage. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Warehouse (TAN-604) Floor plan. General warehouse and chemical storage. Ralph M. Parsons 902-2-ANP-604-A 55. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0604-00-693-106727 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. ADM. Water System Pump House (TAN610). Elevations, plan, and sections. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Water System Pump House (TAN-610). Elevations, plan, and sections. Ralph M. Parsons 902-2-ANP-610-A 74. Date: February 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0610-00-693-106739 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. IET. Control and equipment building (TAN620). Blast roof details. Ralph ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Control and equipment building (TAN-620). Blast roof details. Ralph M. Parsons 902-4-ANP-620-A-323. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-620-00-693-106908 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. IET. Control and equipment building (TAN620). Details and room finish ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Control and equipment building (TAN-620). Details and room finish schedule. Ralph M. Parsons 902-4-ANP-620-A 322. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0629-00-693-106907 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. ADM. Administration Building (TAN602). Early room layout, door and room ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Administration Building (TAN-602). Early room layout, door and room schedules. Ralph M. Parsons 902-2-ANP-602-A 31. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 033-0602-00-693-106710 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. IET. Periscope shielding and installation details. Shows range of scanning ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Periscope shielding and installation details. Shows range of scanning head, removable concrete cap, concrete shielding. Ralph M. Parsons 902-4-ANP-620-A 324. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL Index code no. 035-0620-00-693-106909 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. LPT. Shield test facility (TAN645 and 646). Calibration lab shield ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645 and -646). Calibration lab shield door. Ralph M. Parsons 1229-17 ANP/GE-6-645-MS-1. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-0645-40-693-107369 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. LPT. Shield test facility (TAN645 and 646). Floor plan and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645 and -646). Floor plan and room names. Ralph M. Parsons 1229-17 ANP/GE-6-645-A-1. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-0645/0646-00-693-107347 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. FET. Tank Building, TAN631. Elevations, sections, details. Tank pads and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Tank Building, TAN-631. Elevations, sections, details. Tank pads and saddles. RAlph M. Parsons 1229-2 ANP/GE-5-631-A-1. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0631-00-693-107142 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. LPT. Guard House (TAN642). Elevations, floor plan, sections, details. Ralph ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Guard House (TAN-642). Elevations, floor plan, sections, details. Ralph M. Parsons 1229-12 ANP/GE-7-642-A-S-H7V-1. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0642-00-693-107306 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. A&M. Demineralization plant, TAN649. Floor plan, elevation details. Ralph M. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Demineralization plant, TAN-649. Floor plan, elevation details. Ralph M. Parsons 1480-4-ANP/GE-3-649-A-1. Date: October 1958. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0649-00-693-107439 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. IET. Control and equipment building (TAN620) floor plan. Schedule of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Control and equipment building (TAN-620) floor plan. Schedule of furniture and equipment. Ralph M. Parsons 902-4-ANP-A 320. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0620-00-693-106905 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. A&M. Radioactive parts security storage area, heat removal storage casks. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Radioactive parts security storage area, heat removal storage casks. Plan, section, and details. Ralph M. Parsons 1480-7 ANP/GE-3-720-S-1. Date: November 1958. Approved by INEEL Classification Office for public release. INEEL index no. 034-0720-60-693-107459 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. IET exhaust gas stack. Section, west elevation, foundation plan, access ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET exhaust gas stack. Section, west elevation, foundation plan, access ladder, airplane warning light. Ralph M. Parsons 902-5-ANP-712-S 433. Date: May 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0712-60-693-106984 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. LPT. Shield test facility (TAN646). Sections and details of water ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-646). Sections and details of water management areas. Ralph M. Parsons 1229-17 ANP/GE-6-646-P-3. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-0646-51-693-107388 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. Landowner and permit-holder perceptions of wildlife damage around the Idaho National Engineering and Environmental Laboratory. A survey of INEEL neighbors about elk, mule deer, pronghorn antelope, and depredation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Roush, D.E. Jr.; Beaver, D.E.

    1998-06-01

    Property-owners (N = 220) around the Idaho National Engineering and Environmental Laboratory (INEEL) in southeastern Idaho were surveyed about depredation, control methods and economic issues related to use of the area by elk (Cervus elaphus), mule deer (Odocoileus hemionus), and pronghorn antelope (Antilocapra americana). Depredation was defined as damage to privately-owned crops, forage, and fences and irrigation equipment by these animals. The focus on the three ungulate species was prompted by concerns that elk, which had recolonized the INEEL since 1984, were responsible for an inordinate amount of unprecedented damage to agricultural operations. As the INEEL is a US Departmentmore » of Energy (DOE) reserve with little public hunting access, there have been calls for removal of elk from this land. This study`s objective was to quantify the wildlife damage occurring on agricultural operations adjacent to the INEEL and to characterize the damage attributed to each big game species. Responses from 70.2% of the target population indicate an evenness of opinion, by which the authors mean that various opinions were represented equitably, toward these animals and wildlife damage Total estimated wildlife damage in 1996 was between $140,000 and $180,000 It was attributed foremost to elk, although pronghorn antelope were viewed nearly as damaging. Respondents placed high values in big game animals and wished to see them continue to inhabit these lands. For managing depredation, adjusting hunting seasons was preferred.« less

  2. Radioactive waste management complex low-level waste radiological composite analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consistsmore » of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.« less

  3. FET. Control and equipment building (TAN630). Basement floor plan. Tunnel ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Control and equipment building (TAN-630). Basement floor plan. Tunnel to hangar (TAN-629). Electrical and chemical services. Ralph M. Parsons 1229-2 ANP/GE-630-A-1. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0630-00-693-107080 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. ADM. Fuel Pump House (TAN611). Elevations, floor plan. Drawing includes ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Fuel Pump House (TAN-611). Elevations, floor plan. Drawing includes elevation and plans for "H.M." structures (Hose Storage?). Ralph M. Parsons 902-2-ANP-611-A 78 Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0611-00-693-106741 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. IET. Fuel transfer pumping building (TAN625). Elevations, foundation. Detail of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Fuel transfer pumping building (TAN-625). Elevations, foundation. Detail of access stairway to coupling station. Ralph M. Parsons 902-a-ANY-620-625-A&S 414. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0625-00-693-106971 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. LPT. Shield test facility (TAN645 and 646). Basement and subbasement ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645 and -646). Basement and sub-basement plan. Stairway plans and details. Ralph M. Parsons 1229-17 ANP/GE-6-645-A-2. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-0645/0646-00-693-107348 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. FET. Control and equipment building (TAN630). East elevation and section. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Control and equipment building (TAN-630). East elevation and section. Shielded roadway and personnel entrances. Ralph M. Parsons 1229-2 ANP/GE-5-630-A-5. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0630-00-693-107084 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. FET. Control and equipment building, TAN630. Main floor plan. Control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Control and equipment building, TAN-630. Main floor plan. Control room. Room numbers and functions. Ralph M. Parsons. 1229-2-ANP/GE-5-630-A-2. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0630-00-693-107081 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. ADM. Water well pump houses (TAN612 and TAN613). Plans, elevations, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Water well pump houses (TAN-612 and TAN-613). Plans, elevations, floor and other details. Ralph M. Parsons 902-2-ANP-612-613-A S & P 82. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0612-00-693-106743 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. A&M. TAN607. Foundation plan for hot shop floor and pool. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Foundation plan for hot shop floor and pool. Tunnels to turntable. Motor pit. Ralph M. Parsons 902-3-ANP-607-S128. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-62-693-160722 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. FET. Control and equipment building (TAN630). Sections. Earth cover. Shielded ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Control and equipment building (TAN-630). Sections. Earth cover. Shielded access entries for personnel and vehicles. Ralph M. Parsons 1229-2 ANP/GE-5-630-A-3. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0630-00-693-107082 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. IET exhaust gas duct, system layout, plan, and section. shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET exhaust gas duct, system layout, plan, and section. shows mounting brackets, concrete braces, divided portion of duct, other details. Ralph M. Parsons 902-5-ANP-712-S 429. Date: May 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0712-60-693-106980 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. ADM. Administration Building (TAN602). Elevations, sections, details. Shows areas that ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Administration Building (TAN-602). Elevations, sections, details. Shows areas that were soon remodeled or added onto. Ralph M. Parsons 902-2-ANP-602-A 32 Date: August 1955. Approved by INEEL Classification Office for public release. INEEL index code no. 033-0602-00-693-106711 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. A&M. TAN607. Special service cubicle (hot cell). Details include Zpipe ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Special service cubicle (hot cell). Details include Z-pipe and stepped plug penetrations through shielding wall. Ralph M. Parsons 902-3-ANP-607-A116. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-693-106767 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. A&M. TAN607. Structural supports for biparting door on east wall ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Structural supports for biparting door on east wall of hot shop. Special services cubicle shielding. Ralph M. Parsons 902-3-ANP-607-S141. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-60-693-106785 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. IET. Tank building (TAN627). Plans, elevation, details. shows position of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Tank building (TAN-627). Plans, elevation, details. shows position of tanks within building and concrete supports. Ralph M. Parsons 902-4-ANP-627-A&S 420. Date: Fabruary 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0627-00-693-106975 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. A&M. Demineralization plant (TAN649). Steel door. Ralph M. Parsons 1480L/ANP/GA3649MS1. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Demineralization plant (TAN-649). Steel door. Ralph M. Parsons 1480-L/ANP/GA-3-649-MS-1. Date: October 1958. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0649-40-693-107443 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. A&M. TAN607 second floor plan for cold assembly area. Metallurgical ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 second floor plan for cold assembly area. Metallurgical lab, chemistry lab, nuclear instrument lab, equipment rooms. Ralph M. Parsons 902-ANP-607-A 102. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-693-106754 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. Technical Review of Retrieval and Closure Plans for the INEEL INTEC Tank Farm Facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bamberger, Judith A; Burks, Barry L; Quigley, Keith D

    2001-09-28

    The purpose of this report is to document the conclusions of a technical review of retrieval and closure plans for the Idaho National Energy and Environmental Laboratory (INEEL) Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility. In addition to reviewing retrieval and closure plans for these tanks, the review process served as an information exchange mechanism so that staff in the INEEL High Level Waste (HLW) Program could become more familiar with retrieval and closure approaches that have been completed or are planned for underground storage tanks at the Oak Ridge National Laboratory (ORNL) and Hanford sites. Thismore » review focused not only on evaluation of the technical feasibility and appropriateness of the approach selected by INEEL but also on technology gaps that could be addressed through utilization of technologies or performance data available at other DOE sites and in the private sector. The reviewers, Judith Bamberger of Pacific Northwest National Laboratory (PNNL) and Dr. Barry Burks of The Providence Group Applied Technology, have extensive experience in the development and application of tank waste retrieval technologies for nuclear waste remediation.« less

  20. TAN HOT SHOP AND SUPPORT FACILITY UTILIZATION STUDY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Phillips, Ken Crawforth

    2001-11-01

    Impacts to the U.S. Department of Energy (DOE) complex caused by early closure (prior to 2018) and Demolition and Dismantlement (D&D) of the Test Area North (TAN) hot shop and its support facilities are explored in this report. Various possible conditions, such as Standby, Safe Store and Lay-up, that the facility may be placed in prior to eventually being turned over to D&D are addressed. The requirements, impacts, and implications to the facility and to the DOE Complex are discussed for each condition presented in the report. Some details of the report reference the Idaho National Engineering and Environmental Laboratorymore » (INEEL) Spent Nuclear Fuel Life Cycle Baseline Plan, the INEEL 2000 Infrastructure Long Range Plan, and other internal INEEL reports.« less

  1. TAN Hot Shop and Support Facility Utilization Study

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Picker, B.A.

    2001-11-16

    Impacts to the U.S. Department of Energy (DOE) complex caused by early closure (prior to 2018) and Demolition and Dismantlement (D and D) of the Test Area North (TAN) hot shop and its support facilities are explored in this report. Various possible conditions, such as Standby, Safe Store and Lay-up, that the facility may be placed in prior to eventually being turned over to D and D are addressed. The requirements, impacts, and implications to the facility and to the DOE Complex are discussed for each condition presented in the report. Some details of the report reference the Idaho Nationalmore » Engineering and Environmental Laboratory (INEEL) Spent Nuclear Fuel Life Cycle Baseline Plan, the INEEL 2000 Infrastructure Long Range Plan, and other internal INEEL reports.« less

  2. LPT. Shield test facility (TAN645 and 646). Elevations show three ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645 and -646). Elevations show three types of siding: Asbestos cement, pumice block, concrete. Ralph M. Parsons 1229-17 ANP/GE-6-6445-A-3. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-06445/0646-00-693-107349 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. IET. Exclusion guard house (TAN621) and unit substation (TAN622). Elevations ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Exclusion guard house (TAN-621) and unit substation (TAN-622). Elevations and floor plan. Also show concrete pad for substation. Ralph M. Parsons 902-4-ANP-621-622-A&S 411. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0621-60-693-106968 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. A&M. Liquid waste treatment plant, TAN616. Plan, elevations, sections, and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Liquid waste treatment plant, TAN-616. Plan, elevations, sections, and details. Evaporator pit. Pump room. Room names and numbers. Ralph M. Parsons 902-3-ANP-616-A 297. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index no. 034-0616-00-693-106889 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. A&M. Radioactive parts security storage area, TAN647 and TAN648. Plot ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Radioactive parts security storage area, TAN-647 and TAN-648. Plot plan, fencing details. Relationship to hot shop and railroad turntable. Ralph M. Parsons 1480-7-ANP/GE-3-102. Date: November 19958. Approved by INEEL Classification Office for public release. INEEL index no. 034-0100-00-693-107447 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. LPT. Chlorination building (TAN643) and water well pumphouse (TAN644). Plans, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Chlorination building (TAN-643) and water well pumphouse (TAN-644). Plans, elevations, sections, and details. Ralph M. Parsons 1229-12 ANP/GE-7-643-A-S-H&V-1. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0643/0644-00-693-107307 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. IET. Coupling station (TAN620) and service room section and details. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Coupling station (TAN-620) and service room section and details. Interior electrical features inside coupling station. Cable terminal assembly for patch panel for plug. Ralph M. Parsons 902-4-ANP-620-E 401. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0620-10-693-106958 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. IET. Coupling station (TAN620), plans and sections. Concrete shielding walls ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Coupling station (TAN-620), plans and sections. Concrete shielding walls and boron surface treatment. Elevation shows two floor levels, position of periscopes, and stairways. Ralph M. Parsons 902-4-ANP-602-A 325. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0620-00-693-106910 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. A&M. TAN607 third floor plan for hot shop. Crane control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 third floor plan for hot shop. Crane control rooms and their shielding windows. Plenum. Wall rack for manipulators in hot shop. Ralph M. Parsons 902-3-ANP-607-A 103. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106755 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. LPT. Shield test facility (TAN645 and 646). Sections show relationships ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645 and -646). Sections show relationships among control rooms, coupling station, counting rooms, pools, equipment rooms, data room and other areas. Ralph M. Parsons 1229-17 ANP/GE-6-645-A-4. April 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 037-0645/0646-00-693-107350 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. A&M. Grading and drainage plan. Shows natural ground elevation of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Grading and drainage plan. Shows natural ground elevation of the (presumed) dry lake-bed shore and berm shielding the administrative area from the hot shop area. Ralph M. Parsons 902-2&3-ANP-U 4. Date: December 1953. Approved by INEEL Classification Office for public release. INEEL code no. 032-0000-00-693-106691 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. TRU waste absorbent addition project at the Idaho National Engineering and Environmental Laboratory.

    PubMed

    Colson, R Griff; Auman, Laurence E

    2003-08-01

    ABSTRACT In order to meet a commitment to ship 3,100 m3 of transuranic waste to the Waste Isolation Pilot Plant (WIPP), the Idaho National Engineering and Environmental Laboratory (INEEL) developed a process to add absorbent to TRU waste drums that did not meet WIPP waste acceptance criteria. The development, implementation, and safe completion of this project contributed to the INEEL's success in meeting the commitment three months early.

  13. ADM. Service Building (TAN603). Elevations of all facades with door ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Service Building (TAN-603). Elevations of all facades with door details and detail of kitchen. Section through garage area shows second level of steel decking. Equipment and laboratory furniture schedule. Ralph M. Parsons 902-2-ANP-603-A 44. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 033-0603-00-693-106719 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. A&M. TAN607 second floor plan for hot shop. Roof of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 second floor plan for hot shop. Roof of pool. Viewing window locations. Special equipment room. This drawing was re-drawn to show conditions in 1994. Ralph M. Parsons 902-3-ANP-607-A 101. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-060-00-693-106753 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. A&M. TAN607. Sections for second phase expansion: engine maintenance, machine, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Sections for second phase expansion: engine maintenance, machine, and welding shops; high bay assembly shop, chemical cleaning room (decontamination). Details of sliding door hoods. Approved by INEEL Classification Office for public release. Ralph M. Parsons 1299-5-ANP/GE-3-607-A 109. Date: August 1956. INEEL index code no. 034-0607-00-693-107169 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. LPT. Low power test (TAN640 and 641) floor plan. Cells ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-640 and -641) floor plan. Cells 101 and 102, control rooms, shielded counting room, generator room, list of room numbers and names. Door details. Ralph M. Parsons 1229-12 ANP/GE-7-640-A-1. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0640-00-693-107274 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. LPT. Low power test (TAN640 and641) sections. Referent drawing is ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-640 and-641) sections. Referent drawing is HAER ID-33-E-292. Section A shows cable tunnel between reactor cells and control room. Bridge crane, roof, ladder details. Ralph M. Parsons 1229-12 ANP/GE-7-640-A-3. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0640-00-693-107276 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. A&M. TAN607. Elevation for secondphase expansion of A&M Building. Work ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Elevation for second-phase expansion of A&M Building. Work areas south of the Carpentry Shop. High-bay shop, decontamination room at south-most end. Approved by INEEL Classification Office for public release. Ralph M. Parsons 1299-5-ANP/GE-3-607-A 106. Date: August 1956. INEEL index code no. 034-0607-00-693-107166 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. A&M. Hot cell addition (TAN633). Floor plan, elevations. Arrangement of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot cell addition (TAN-633). Floor plan, elevations. Arrangement of monorail along corridor, four hot cells, plug access openings, viewing windows, photo darkroom. Ralph M. Parsons 1229-13-ANP/GE-3-633-A-1. Date: December 1956 as redrawn in August 1998. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0633-00-693-107315 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. American Indians, hunting and fishing rates, risk, and the Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Burger, J.

    1999-05-01

    Hunting, fishing, and recreational rates of 276 American Indians attending a festival at Fort Hall, near the Idaho National Engineering and Environmental Laboratory (INEEL), were examined. Nearly half of the sample lived on the Fort Hall Reservation, and half were American Indians from elsewhere in the western United States. An additional 44 White people attending the festival were also interviewed. The hypothesis that there are differences in hunting, fishing, and recreational rates as a function of tribal affiliation, educational level, gender, and age was examined. Information on hunting and fishing rates are central for understanding potential exposure scenarios for Americanmore » Indians if the Department of Energy`s INEEL lands are ever opened to public access, and the data are important because of the existence of tribal treaties that govern the legal and cultural rights of the Shoshone-Bannock regarding INEEL lands. Variations in hunting, fishing, and photography rates were explained by tribal affiliation (except fishing), gender, age, and schooling. Hunting rates were significantly higher for Indians (both those living on Fort Hall and others) than Whites. Men engaged in significantly higher rates of outdoor activities than women (except for photography). Potential and current hunting and fishing on and adjacent to INEEL was more similar among the local Whites and Fort Hall Indians than between these two groups and other American Indians.« less

  1. Chlorofluorocarbons, sulfur hexafluoride, and dissolved permanent gases in ground water from selected sites in and near the Idaho National Engineering and Environmental Laboratory, Idaho, 1994-97

    USGS Publications Warehouse

    Busenberg, Eurybiades; Plummer, Niel; Bartholomay, Roy C.; Wayland, Julian E.

    1998-01-01

    From July 1994 through May 1997, the U.S. Geological Survey in cooperation with the Department of Energy, sampled 86 wells completed in the Snake River Plain aquifer at and near the Idaho N ationa1 Engineering and Environmental Laboratory (INEEL). The wells were sampled for a variety of constituents including one- and two-carbon halocarbons. Concentrations of dichlorodifluoromethane (CFC-12), trichlorofluoromethane (CFC-11) and trichlorotrifluororoethane (CFC-113) were determined. The samples for halocarbon analysis were collected in 62-milliliter flame sealed borosilicate glass ampoules in the field. The data will be used to evaluate the ages of ground waters at INEEL. The ages of the ground water will be used to determine recharge rates, residence time, and travel time of water in the Snake River Plain aquifer in and near INEEL. The chromatograms of 139 ground waters are presented showing a large number of halomethanes, haloethanes, and haloethenes present in the ground waters underlying the INEEL. The chromatograms can be used to qualitatively evaluate a large number of contaminants at parts per trillion to parts per billion concentrations. The data can be used to study temporal and spatial distribution of contaminants in the Snake River Plain aquifer. Representative compressed chromatograms for all ground waters sampled in this study are available on two 3.5-inch high density computer disks. The data and the program required to decompress the data can be obtained from the U.S. Geological Survey office at Idaho Falls, Idaho. Sulfur hexafluoride (SF6) concentrations were measured in selected wells to determine the feasibility of using this environmental tracer as an age dating tool of ground water. Concentrations of dissolved nitrogen, argon, carbon dioxide, oxygen, and methane were measured in 79 ground waters. Concentrations of dissolved permanent gases are tabulated and will be used to evaluate the temperature of recharge of ground water in and near the INEEL.

  2. INEEL Source Water Assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sehlke, Gerald

    2003-03-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) covers approximately 890 mi2 and includes 12 public water systems that must be evaluated for Source water protection purposes under the Safe Drinking Water Act. Because of its size and location, six watersheds and five aquifers could potentially affect the INEEL’s drinking water sources. Based on a preliminary evaluation of the available information, it was determined that the Big Lost River, Birch Creek, and Little Lost River Watersheds and the eastern Snake River Plain Aquifer needed to be assessed. These watersheds were delineated using the United States Geologic Survey’s Hydrological Unit scheme.more » Well capture zones were originally estimated using the RESSQC module of the Environmental Protection Agency’s Well Head Protection Area model, and the initial modeling assumptions and results were checked by running several scenarios using Modflow modeling. After a technical review, the resulting capture zones were expanded to account for the uncertainties associated with changing groundwater flow directions, a thick vadose zone, and other data uncertainties. Finally, all well capture zones at a given facility were merged to a single wellhead protection area at each facility. A contaminant source inventory was conducted, and the results were integrated with the well capture zones, watershed and aquifer information, and facility information using geographic information system technology to complete the INEEL’s Source Water Assessment. Of the INEEL’s 12 public water systems, three systems rated as low susceptibility (EBR-I, Main Gate, and Gun Range), and the remainder rated as moderate susceptibility. No INEEL public water system rated as high susceptibility. We are using this information to develop a source water management plan from which we will subsequently implement an INEEL-wide source water management program. The results are a very robust set of wellhead protection areas that will protect the INEEL’s public water systems yet not too conservative to inhibit the INEEL from carrying out its missions.« less

  3. INEEL BNCT research program. Annual report, January 1, 1996--December 31, 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Venhuizen, J.R.

    1997-04-01

    This report is a summary of the progress and research produced for the Idaho National Engineering and Environmental Laboratory (INEEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1996. Contributions from the individual investigators about their projects are included, specifically, physics: treatment planning software, real-time neutron beam measurement dosimetry, measurement of the Finnish research reactor epithermal neutron spectrum, BNCT accelerator technology; and chemistry: analysis of biological samples and preparation of {sup 10}B enriched decaborane.

  4. A&M. TAN607 first floor plan for cold assembly area. Shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 first floor plan for cold assembly area. Shows special source vaults, X-ray room, instrument shops, and positions of large machines in component test laboratory. This drawing was re-drawn to show conditions in 1994. Ralph M. Parsons 902-3-ANP-607-A 100. Date of original: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-060-00-693-106752 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. LPT. Plot plan and site layout. Includes shield test pool/EBOR ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Plot plan and site layout. Includes shield test pool/EBOR facility. (TAN-645 and -646) low power test building (TAN-640 and -641), water storage tanks, guard house (TAN-642), pump house (TAN-644), driveways, well, chlorination building (TAN-643), septic system. Ralph M. Parsons 1229-12 ANP/GE-7-102. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0102-00-693-107261 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. A&M. TAN607. Shield wall sections and details around hot shop ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Shield wall sections and details around hot shop and special equipment room, showing taper, crane rail elevations, and elevation for biparting door (door no. 301) in wall between hot shop and special equipment room. Ralph M. Parsons 902-3-ANP-607-S 138. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-62-963-106782 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. A&M. TAN607 floor plan for first floor. Shows stepped door ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 floor plan for first floor. Shows stepped door plug design from hot shop into special services cubicle, cubicle windows, and other details. This drawing was re-drawn to show as-built conditions in 1985. Ralph M. Parsons 902-3-ANP-607-A 99. Date of original: January 1955. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106751 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. IET. Movable test cell building (TAN624). Plans, sections, and elevations ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Movable test cell building (TAN-624). Plans, sections, and elevations show trapezoidal shape of front/rear elevations, vertical sliding door panels, wheels, periscope and camera locations, fixed concrete wall, and relationship to coupling station (TAN-620) and rail track. Ralph M. Parson 902-4-ANP-624-A 329. Date: February 1954. Approved by INEEL Classification Office for public release. INEEL Index code no. 035-0624-00-693-106911 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. Mercury accumulation in snow on the Idaho National Engineering and Environmental Laboratory and surrounding region, southeast Idaho, USA

    USGS Publications Warehouse

    Susong, D.D.; Abbott, M.L.; Krabbenhoft, D.P.

    2003-01-01

    Snow was sampled and analyzed for total mercury (THg) on the Idaho National Engineering and Environmental Laboratory (INEEL) and surrounding region prior to the start-up of a large (9-11 g/h) gaseous mercury emission source. The objective was to determine the effects of the source on local and regional atmospheric deposition of mercury. Snow samples collected from 48 points on a polar grid near the source had THg concentrations that ranged from 4.71 to 27.26 ng/L; snow collected from regional background sites had THg concentrations that ranged from 0.89 to 16.61 ng/L. Grid samples had higher concentrations than the regional background sites, which was unexpected because the source was not operating yet. Emission of Hg from soils is a possible source of Hg in snow on the INEEL. Evidence from Hg profiles in snow and from unfiltered/filtered split samples supports this hypothesis. Ongoing work on the INEEL is investigating Hg fluxes from soils and snow.

  10. The Application of System Dynamics to the Integration of National Laboratory Research and K-12 Education

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mills, James Ignatius; Zounar Harbour, Elda D

    2001-08-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is dedicated to finding solutions to problems related to the environment, energy, economic competitiveness, and national security. In an effort to attract and retain the expertise needed to accomplish these challenges, the INEEL is developing a program of broad educational opportunities that makes continuing education readily available to all laboratory employees, beginning in the K–12 environment and progressing through post-graduate education and beyond. One of the most innovative educational approaches being implemented at the laboratory is the application of STELLA© dynamic learning environments, which facilitate captivating K–12 introductions to the complex energymore » and environmental challenges faced by global societies. These simulations are integrated into lesson plans developed by teachers in collaboration with INEEL scientists and engineers. This approach results in an enjoyable and involved learning experience, and an especially positive introduction to the application of science to emerging problems of great social and environmental consequence.« less

  11. Integrating GIS, Archeology, and the Internet.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sera White; Brenda Ringe Pace; Randy Lee

    2004-08-01

    At the Idaho National Engineering and Environmental Laboratory's (INEEL) Cultural Resource Management Office, a newly developed Data Management Tool (DMT) is improving management and long-term stewardship of cultural resources. The fully integrated system links an archaeological database, a historical database, and a research database to spatial data through a customized user interface using ArcIMS and Active Server Pages. Components of the new DMT are tailored specifically to the INEEL and include automated data entry forms for historic and prehistoric archaeological sites, specialized queries and reports that address both yearly and project-specific documentation requirements, and unique field recording forms. The predictivemore » modeling component increases the DMT’s value for land use planning and long-term stewardship. The DMT enhances the efficiency of archive searches, improving customer service, oversight, and management of the large INEEL cultural resource inventory. In the future, the DMT will facilitate data sharing with regulatory agencies, tribal organizations, and the general public.« less

  12. LPT. Elevations of low power test building (TAN640 and 641). ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Elevations of low power test building (TAN-640 and -641). West and south elevations show stepped shield wall. South and east elevations show pumice block passageway on south side. Reactor cell walls are concrete. One-story parts are pumice block. Metal rollup doors. Ralph M. Parsons 1229-12 ANP/GE-7-640-A-2. November 1956. Approved by INEEL Classification Office for public release. INEEL index code no. 038-0640-00-693-107275 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. Recreation, consumption of wild game, risk, and the Department of Energy sites: perceptions of people attending the Lewiston, ID, "Roundup".

    PubMed

    Burger, J

    1999-02-26

    Several federal agencies are reclaiming land through remediation and restoration, and are considering potential future land uses that are compatible with current land uses and local needs. Understanding potential recreational and wild game consumption patterns and risk perceptions are critical for determining cleanup levels and assessing potential risk associated with certain uses. In this article, recreational rates of people attending the Lewiston "Roundup" rodeo in northwestern Idaho were examined, as well as their perceptions of the safety of consuming fish and game from two Department of Energy (DOE) facilities: the Hanford Site and the Idaho National Engineering and Environmental Laboratory (INEEL). These are two of DOE's largest sites. Lewiston is closer to Hanford, but is in the same state as INEEL. Men engaged in significantly higher hunting and fishing rates than women, but there were no gender differences in camping and hiking rates. Rates of hunting and camping decreased significantly with age, while rates of hiking were lowest for 31- to 45-yr-olds. Level of education generally was not related to rates of recreation. Over 70% of the subjects ate deer, elk, and self-caught fish; 30-50% ate grouse, moose, and waterfowl; and fewer people ate other game species. Overall, subjects were less concerned about eating the fish and game from INEEL than from Hanford, and more people thought Hanford should be cleaned up completely compared to INEEL. Mean rates of fishing, hiking, and camping all exceeded the DOE's maximum recreational exposure assumption of 14 d/yr used in their future use documents. Although at present people are generally not allowed access to DOE lands for recreation, recreation is one future land use being considered for these federal facilities. Given that some people would engage in multiple activities, the potential exists for people living in the general region of Hanford and INEEL to exceed the 14-d exposure assumption. The relative gender differences in recreational rates mean that men are potentially more at risk, particularly since hunting (on both sites) and fishing (on Hanford) are attractive.

  14. Technical Status Report: Preliminary Glass Formulation Report for INEEL HAW. Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Peeler, D.; Reamer, I.; Vienna, J.

    1998-03-01

    Preliminary glass formulation work has been initiated at Pacific Northwest National Laboratory (PNNL) and the Savannah River Technology Center (SRTC) to support immobilization efforts of Idaho National Engineering and Environmental Laboratory (INEEL) high activity waste (HAW). Based on current pretreatment flow sheet assumptions, several glasses were fabricated and tested using an average `All Blend` waste stream composition which is dominated by the presence of ZrO{sub 2} (i.e., approximately 80 wt percent). The results of this initial work show that immobilization via vitrification is a viable option for a specific INEEL HAW waste stream. Waste loadings of at least 19 wtmore » percent can be achieved for the `All Blend` stream while maintaining targeted processing and product performance criteria. This waste loading translates into a ZrO{sub 2} content in excess of 15 wt percent in the final glass waste form. Frits developed for this work are based in the alkali borosilicate system. Although the results indicate that vitrification can be used to immobilize the `All Blend` waste stream, the glass compositions are by no means optimized.« less

  15. A&M. TAN607 floor plans. Shows three floor levels of pool, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 floor plans. Shows three floor levels of pool, hot shop, and warm shop. Includes view of pool vestibule, personnel labyrinth, location of floor rails, and room numbers of office areas, labs, instrument rooms, and stairways. This drawing was re-drawn to show as-built features in 1993. Ralph M. Parsons 902-3-ANP-607-A 96. Date of original: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106748 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. A&M. TAN607 sections. Section A shows variable roof lines, variable ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 sections. Section A shows variable roof lines, variable thickness of hot shop shield walls, relationship of subterranean pool to grade. Section B shows relative heights of hot shop floor and its control gallery, position of bridge cranes and manipulator rails. Locomotive service pit. Referent drawing is ID-33-E-158 Above. Ralph M. Parsons 902-3-ANP-607-A 105. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106757 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. Idaho National Engineering and Environmental Laboratory Wildland Fire Management Environmental Assessment - April 2003

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Irving, J.S.

    DOE prepared an environmental assessment (EA)for wildland fire management activities on the Idaho National Engineering and Environmental Laboratory (INEEL) (DOE/EA-1372). The EA was developed to evaluate wildland fire management options for pre-fire, fire suppression, and post fire activities. Those activities have an important role in minimizing the conversion of the native sagebrush steppe ecosystem found on the INEEL to non-native weeds. Four alternative management approaches were analyzed: Alternative 1 - maximum fire protection; Alternative 2 - balanced fire protection; Alternative 2 - balanced fire protection; Alternative 3 - protect infrastructure and personnel; and Alternative 4 - no action/traditional fire protection.

  18. Idaho National Engineering and Environmental Laboratory Wildland Fire Management Environmental Assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Irving, John S

    DOE prepared an environmental assessment (EA)for wildland fire management activities on the Idaho National Engineering and Environmental Laboratory (INEEL) (DOE/EA-1372). The EA was developed to evaluate wildland fire management options for pre-fire, fire suppression, and post fire activities. Those activities have an important role in minimizing the conversion of the native sagebrush steppe ecosystem found on the INEEL to non-native weeds. Four alternative management approaches were analyzed: Alternative 1 - maximum fire protection; Alternative 2 - balanced fire protection; Alternative 2 - balanced fire protection; Alternative 3 - protect infrastructure and personnel; and Alternative 4 - no action/traditional fire protection.

  19. Development of the auto-steering software and equipment technology (ASSET)

    NASA Astrophysics Data System (ADS)

    McKay, Mark D.; Anderson, Matthew O.; Wadsworth, Derek C.

    2003-09-01

    The Idaho National Engineering and Environmental Laboratory (INEEL), through collaboration with INSAT Co., has developed a low cost robotic auto-steering system for parallel contour swathing. The capability to perform parallel contour swathing while minimizing "skip" and "overlap" is a necessity for cost-effective crop management within precision agriculture. Current methods for performing parallel contour swathing consist of using a Differential Global Position System (DGPS) coupled with a light bar system to prompt an operator where to steer. The complexity of operating heavy equipment, ensuring proper chemical mixture and application, and steering to a light bar indicator can be overwhelming to an operator. To simplify these tasks, an inexpensive robotic steering system has been developed and tested on several farming implements. This development leveraged research conducted by the INEEL and Utah State University. The INEEL-INSAT Auto-Steering Software and Equipment Technology provides the following: 1) the ability to drive in a straight line within +/- 2 feet while traveling at least 15 mph, 2) interfaces to a Real Time Kinematic (RTK) DGPS and sub-meter DGPS, 3) safety features such as Emergency-stop, steering wheel deactivation, computer watchdog deactivation, etc., and 4) a low-cost, field-ready system that is easily adapted to other systems.

  20. Basalt-flow imaging using a high-resolution directional borehole radar

    USGS Publications Warehouse

    Moulton, C.W.; Wright, D.L.; Hutton, S.R.; Smith, D.V.G.; Abraham, J.D.

    2002-01-01

    A new high-resolution directional borehole radar-logging tool (DBOR tool) was used to log three wells at the Idaho National Engineering and Environmental Laboratory (INEEL). The radar system uses identical directional cavity-backed monopole transmitting and receiving antennas that can be mechanically rotated while the tool is stationary or moving slowly in a borehole. Faster reconnaissance logging with no antenna rotation was also done to find zones of interest. The microprocessor-controlled motor/encoder in the tool can rotate the antennas azimuthally, to a commanded angle, accurate to a within few degrees. The three logged wells in the unsaturated zone at the INEEL had been cored with good core recovery through most zones. After coring, PVC casing was installed in the wells. The unsaturated zone consists of layered basalt flows that are interbedded with thin layers of coarse-to-fine grained sediments. Several zones were found that show distinctive signatures consistent with fractures in the basalt. These zones may correspond to suspected preferential flow paths. The DBOR data were compared to core, and other borehole log information to help provide better understanding of hydraulic flow and transport in preferential flow paths in the unsaturated zone basalts at the INEEL.

  1. 1995 annual epidemiologic surveillance report for Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-12-31

    The US Department of Energy's (DOE) conduct of epidemiologic surveillance provides an early warning system for health problems among workers. This program monitors illnesses and health conditions that result in an absence of five or more consecutive workdays, occupational injuries and illnesses, and disabilities and deaths among current workers. This report summarizes epidemiologic surveillance data collected from the Idaho National Engineering and Environmental Laboratory (INEEL) from January 1, 1995 through December 31, 1995. The data were collected by a coordinator at INEEL and submitted to the Epidemiologic Surveillance Data Center, located at Oak Ridge Institute for Science and Education, wheremore » quality control procedures and data analyses were carried out.« less

  2. Measurement of Sedimentary Interbed Hydraulic Properties and Their Hydrologic Influence near the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory

    USGS Publications Warehouse

    Perkins, Kim S.

    2003-01-01

    Disposal of wastewater to unlined infiltration ponds near the Idaho Nuclear Technology and Engineering Center (INTEC), formerly known as the Idaho Chemical Processing Plant, at the Idaho National Engineering and Environmental Laboratory (INEEL) has resulted in the formation of perched water bodies in the unsaturated zone (Cecil and others, 1991). The unsaturated zone at INEEL comprises numerous basalt flows interbedded with thinner layers of coarse- to fine-grained sediments and perched ground-water zones exist at various depths associated with massive basalts, basalt-flow contacts, sedimentary interbeds, and sediment-basalt contacts. Perched ground water is believed to result from large infiltration events such as seasonal flow in the Big Lost River and wastewater discharge to infiltration ponds. Evidence from a large-scale tracer experiment conducted in 1999 near the Radioactive Waste Management Complex (RWMC), approximately 13 km from the INTEC, indicates that rapid lateral flow of perched water in the unsaturated zone may be an important factor in contaminant transport at the INEEL (Nimmo and others, 2002b). Because sedimentary interbeds, and possibly baked-zone alterations at sediment-basalt contacts (Cecil and other, 1991) play an important role in the generation of perched water it is important to assess the hydraulic properties of these units.

  3. A&M. TAN607. Section views of hot shop. Section E shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Section views of hot shop. Section E shows equipment areas along rear wall. Section F shows storage pool cut along east/west line. Roof trusses, shelves along sides of pool, drain, roof trusses, shelves along sides of pool, drain, and sump. Section G cuts along north/south to show centerline of turntables, manipulator arms, O-man bridge, crane bridge. Referent drawing is ID-33-E-158 above. Ralph M. Parsons 902-3-ANP-607-A 107. Date: December 1952, but as-built in 1982. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106759 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. Site dose calculations for the INEEL/TMI-2 storage facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jones, K.B.

    1997-12-01

    The U.S. Department of Energy (DOE) is licensing an independent spent-fuel storage installation (ISFSI) for the Three Mile Island unit 2 (TMI-2) core debris to be constructed at the Idaho Chemical Processing Plant (ICPP) site at the Idaho National Engineering and Environmental Laboratory (INEEL) using the NUHOMS spent-fuel storage system. This paper describes the site dose calculations, performed in support of the license application, that estimate exposures both on the site and for members of the public. These calculations are unusual for dry-storage facilities in that they must account for effluents from the system in addition to skyshine from themore » ISFSI. The purpose of the analysis was to demonstrate compliance with the 10 CFR 20 and 10 CFR 72.104 exposure limits.« less

  5. 23. CONSTRUCTION PROGRESS VIEW LOOKING TOWARD EAST SHOWING CONCRETE BLOCK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    23. CONSTRUCTION PROGRESS VIEW LOOKING TOWARD EAST SHOWING CONCRETE BLOCK CONSTRUCTION. INEEL PHOTO NUMBER NRTS-59-4305. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  6. 19. CONSTRUCTION PROGRESS PHOTO SHOWING (TYPICALLY COMPLEX) WASTE HOLDING CELL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    19. CONSTRUCTION PROGRESS PHOTO SHOWING (TYPICALLY COMPLEX) WASTE HOLDING CELL PIPING. INEEL PHOTO NUMBER NRTS-59-3212. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  7. 15. CONSTRUCTION PROGRESS PHOTO SHOWING FORMS GOING UP ON ACCESS ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    15. CONSTRUCTION PROGRESS PHOTO SHOWING FORMS GOING UP ON ACCESS CORRIDOR. INEEL PHOTO NUMBER NRTS-59-336. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  8. 20. CONSTRUCTION PROGRESS PHOTO OF INSTRUMENT PANEL IN PLACE IN ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    20. CONSTRUCTION PROGRESS PHOTO OF INSTRUMENT PANEL IN PLACE IN OPERATING CORRIDOR. INEEL PHOTO NUMBER NRTS-59-6091. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  9. Subsurface high resolution definition of subsurface heterogeneity for understanding the biodynamics of natural field systems: Advancing the ability for scaling to field conditions. 1998 annual progress report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Majer, E.L.; Brockman, F.J.

    1998-06-01

    'This research is an integrated physical (geophysical and hydrologic) and microbial study using innovative geophysical imaging and microbial characterization methods to identify key scales of physical heterogeneities that affect the biodynamics of natural subsurface environments. Data from controlled laboratory and in-situ experiments at the INEEL Test Area North (TAN) site are being used to determine the dominant physical characteristics (lithologic, structural, and hydrologic) that can be imaged in-situ and correlated with microbial properties. The overall goal of this research is to contribute to the understanding of the interrelationships between transport properties and spatially varying physical, chemical, and microbiological heterogeneity. Themore » outcome will be an improved understanding of the relationship between physical and microbial heterogeneity, thus facilitating the design of bioremediation strategies in similar environments. This report summarizes work as of May 1998, the second year of the project. This work is an extension of basic research on natural heterogeneity first initiated within the DOE/OHER Subsurface Science Program (SSP) and is intended to be one of the building blocks of an integrated and collaborative approach with an INEEL/PNNL effort aimed at understanding the effect of physical heterogeneity on transport properties and biodynamics in natural systems. The work is closely integrated with other EMSP projects at INEEL (Rick Colwell et al.) and PNNL (Fred Brockman and Jim Fredrickson).'« less

  10. Evaluation and Testing of IONSIV IE-911 for the Removal of Cesium-137 from INEEL Tank Waste and Dissolved Calcines

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    N. R. Mann; T. A. Todd; K. N. Brewer

    1999-04-01

    Development of waste treatment processes for the remediation of radioactive wastes is currently underway. A number of experiments were performed at the Idaho Nuclear Technology and Environmental Center (INTEC) located at the Idaho National Engineering and Environmental Laboratory (INEEL) with the commercially available sorbent material, IONSIV IE-911, crystalline silicotitanate (CST), manufactured by UOP LLC. The purpose of this work was to evaluate the removal efficiency, sorbent capacity and selectivity of CST for removing Cs-137 from actual and simulated acidic tank waste in addition to dissolved pilot-plant calcine solutions. The scope of this work included batch contact tests performed with non-radioactivemore » dissolved Al and Run-64 pilot plant calcines in addition to simulants representing the average composition of tank waste. Small-scale column tests were performed with actual INEEL tank WM-183 waste, tank waste simulant, dissolved Al and Run-64 pilot plant calcine solutions. Small-scale column experiments using actual WM-183 tank waste resulted in fifty-percent Cs-137 breakthrough at approximately 589 bed volumes. Small-scale column experiments using the tank waste simulant displayed fifty-percent Cs-137 breakthrough at approximately 700 bed volumes. Small-scale column experiments using dissolved Al calcine simulant displayed fifty-percent Cs-137 breakthrough at approximately 795 bed volumes. Column experiments with dissolved Run-64, pilot plant calcine did not reach fifty-percent breakthrough throughout the test.« less

  11. Chlorine-36 in Water, Snow, and Mid-Latitude Glacial Ice of North America: Meteoric and Weapons-Tests Production in the Vicinity of the Idaho National Engineering and Environmental Laboratory, Idaho

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    L. DeWayne; J. R. Green; S. Vogt, P. Sharma

    1999-01-01

    Measurements of chlorine-36 (36Cl) were made for 64 water, snow, and glacial-ice and -runoff samples to determine the meteoric and weapons-tests-produced concentrations and fluxes of this radionuclide at mid-latitudes in North America. The results will facilitate the use of 36Cl as a hydrogeologic tracer at the Idaho National Engineering and Environmental Laboratory (INEEL). This information was used to estimate meteoric and weapons-tests contributions of this nuclide to environmental inventories at and near the INEEL. The data presented in this report suggest a meteoric source 36Cl for environmental samples collected in southeastern Idaho and western Wyoming if the concentration is lessmore » than 1 x 10 7 atoms/L. Additionally, concentrations in water, snow, or glacial ice between 1 x 10 7 and 1 x 10 8 atoms/L may be indicative of a weapons-tests component from peak 36Cl production in the late 1950s. Chlorine-36 concentrations between 1 x 10 8 and 1 x 10 9 atoms/L may be representative of re-suspension of weapons-tests fallout airborne disposal of 36Cl from the INTEC, or evapotranspiration. It was concluded from the water, snow, and glacial data presented here that concentrations of 36Cl measured in environmental samples at the INEEL larger than 1 x 10 9 atoms/L can be attributed to waste-disposal practices.« less

  12. 42. ARAIII Prototype assembly and evaluation building ARA630 interior. Typical ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    42. ARA-III Prototype assembly and evaluation building ARA-630 interior. Typical view room partitions. Ineel photo no. 3-28. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  13. 21. CONSTRUCTION PROGRESS VIEW OF CALCINER VESSEL ON LOW BOY ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    21. CONSTRUCTION PROGRESS VIEW OF CALCINER VESSEL ON LOW BOY EN ROUTE TO FACILITY. INEEL PHOTO NUMBER NRTS-60-2487. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  14. 22. CONSTRUCTION PROGRESS PHOTO SHOWING WORKERS LOWERING CALCINER VESSEL INTO ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    22. CONSTRUCTION PROGRESS PHOTO SHOWING WORKERS LOWERING CALCINER VESSEL INTO CELL THROUGH THE HATCH. INEEL PHOTO NUMBER NRTS-60-2485. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  15. PBF (PER620) interior, basement level. Sampling equipment. Date: May 2004. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, basement level. Sampling equipment. Date: May 2004. INEEL negative no. HD-41-5-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  16. IET. Weather instrumentation tower, located south of control building. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Weather instrumentation tower, located south of control building. Camera facing west. Date: August 17, 1955. INEEL negative no. 55-2414 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. IET control building (TAN620). interior room. sign says, "emergency equipment ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET control building (TAN-620). interior room. sign says, "emergency equipment for metal fires." INEEL negative no. HD-21-1-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. PBF (PER620) interior. Counting room, main floor. Date: May 2004. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior. Counting room, main floor. Date: May 2004. INEEL negative no. HD-41-6-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. A&M. Hot liquid waste building (TAN616). Interior of evaporator control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste building (TAN-616). Interior of evaporator control room. Date: 1962. INEEL negative no. 62-6824 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. IET. Jet fuel tank being lowered into position below grade. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Jet fuel tank being lowered into position below grade. Two tanks already in place. Date: October 18, 1954. INEEL negative no. 12535 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. 52. ARAII. Support piers for SL1 reactor building. September 5, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    52. ARA-II. Support piers for SL-1 reactor building. September 5, 1957. Ineel photo no. 57-4398. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  2. PBF (PER620) interior, first basement level. Sampling equipment. Date: March ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, first basement level. Sampling equipment. Date: March 2004. INEEL negative no. HD-41-4-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  3. SPERTI, Instrument Cell Building (PER606). North facade. Date: August 2003. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I, Instrument Cell Building (PER-606). North facade. Date: August 2003. INEEL negative no. HD-35-3-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  4. PBF (PER620) interior, basement level. Detail of coolant piping. Date: ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, basement level. Detail of coolant piping. Date: May 2004. INEEL negative no. HD-41-5-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  5. IET. Diesel engine for emergency generator is headed for installation ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Diesel engine for emergency generator is headed for installation in shielded control building (TAN-620). Date: September 21, 1954. INEEL negative no. 12145 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. A&M. Hot liquid waste building (TAN616) under construction. Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste building (TAN-616) under construction. Camera facing northeast. Date: November 25, 1953. INEEL negative no. 9232 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. 16. CONSTRUCTION PROGRESS PHOTO SHOWING SURPLUS GUN BARREL BEING LOWERED ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    16. CONSTRUCTION PROGRESS PHOTO SHOWING SURPLUS GUN BARREL BEING LOWERED INTO PLACE FOR USE AS PIPE TUNNEL. INEEL PHOTO NUMBER NRTS-59-709. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  8. 25. CONSTRUCTION PROGRESS AERIAL VIEW OF WASTE CALCINING FACILITY TAKEN ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    25. CONSTRUCTION PROGRESS AERIAL VIEW OF WASTE CALCINING FACILITY TAKEN WHEN STRUCTURE WAS 99 PERCENT COMPLETE. INEEL PHOTO NUMBER NRTS-60-5409. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  9. 18. CONSTRUCTION PROGRESS PHOTO SHOWING SURPLUS GUN BARRELS IN PLACE ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    18. CONSTRUCTION PROGRESS PHOTO SHOWING SURPLUS GUN BARRELS IN PLACE TO BE USED AS PIPE TUNNELS. INEEL PHOTO NUMBER NRTS-59-925. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  10. A&M. TAN607 sections. Section C cuts hot shop on its ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607 sections. Section C cuts hot shop on its 160-foot east/west line. Shows tapered shield wall on east and west facades of building. Relationship between hot shop and special equipment service room, cable tracks for overhead bridge crane, location of well. Concrete roof beams. Section D shows similar east/west of cold assembly room 115 and its bridge crane rail. Shows heavy shielding around special services cubicle and height of viewing windows on east and west sides. Rear of building is shown in relationship to the ridge east of the building. Referent drawing is ID-33-E-158 above. Ralph M. Parsons 902-3-ANP-607-A 106. Date: December 1952. Approved by INEEL Classification Office for public release. INEEL index code no. 034-0607-00-693-106758 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. Legacy sample disposition project. Volume 2: Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gurley, R.N.; Shifty, K.L.

    1998-02-01

    This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmentalmore » and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions.« less

  12. INEEL AIR MODELING PROTOCOL ext

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    C. S. Staley; M. L. Abbott; P. D. Ritter

    2004-12-01

    Various laws stemming from the Clean Air Act of 1970 and the Clean Air Act amendments of 1990 require air emissions modeling. Modeling is used to ensure that air emissions from new projects and from modifications to existing facilities do not exceed certain standards. For radionuclides, any new airborne release must be modeled to show that downwind receptors do not receive exposures exceeding the dose limits and to determine the requirements for emissions monitoring. For criteria and toxic pollutants, emissions usually must first exceed threshold values before modeling of downwind concentrations is required. This document was prepared to provide guidancemore » for performing environmental compliance-driven air modeling of emissions from Idaho National Engineering and Environmental Laboratory facilities. This document assumes that the user has experience in air modeling and dose and risk assessment. It is not intended to be a "cookbook," nor should all recommendations herein be construed as requirements. However, there are certain procedures that are required by law, and these are pointed out. It is also important to understand that air emissions modeling is a constantly evolving process. This document should, therefore, be reviewed periodically and revised as needed. The document is divided into two parts. Part A is the protocol for radiological assessments, and Part B is for nonradiological assessments. This document is an update of and supersedes document INEEL/INT-98-00236, Rev. 0, INEEL Air Modeling Protocol. This updated document incorporates changes in some of the rules, procedures, and air modeling codes that have occurred since the protocol was first published in 1998.« less

  13. Photonuclear-based Detection of Nuclear Smuggling in Cargo Containers

    NASA Astrophysics Data System (ADS)

    Jones, J. L.; Haskell, K. J.; Hoggan, J. M.; Norman, D. R.; Yoon, W. Y.

    2003-08-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) and the Los Alamos National Laboratory (LANL) have performed experiments in La Honda, California and at the Idaho Accelerator Center in Pocatello, Idaho to assess and develop a photonuclear-based detection system for shielded nuclear materials in cargo containers. The detection system, measuring photonuclear-related neutron emissions, is planned for integration with the ARACOR Eagle Cargo Container Inspection System (Sunnyvale, CA). The Eagle Inspection system uses a nominal 6-MeV electron accelerator and operates with safe radiation exposure limits to both container stowaways and to its operators. The INEEL has fabricated custom-built, helium-3-based, neutron detectors for this inspection application and is performing an experimental application assessment. Because the Eagle Inspection system could not be moved to LANL where special nuclear material was available, the response of the Eagle had to be determined indirectly so as to support the development and testing of the detection system. Experiments in California have successfully matched the delayed neutron emission performance of the ARACOR Eagle with that of the transportable INEEL electron accelerator (i.e., the Varitron) and are reported here. A demonstration test is planned at LANL using the Varitron and shielded special nuclear materials within a cargo container. Detector results are providing very useful information regarding the challenges of delayed neutron counting near the photofission threshold energy of 5.5 - 6.0 MeV, are identifying the possible utilization of prompt neutron emissions to allow enhanced signal-to-noise measurements, and are showing the overall benefits of using higher electron beam energies.

  14. 41. OPERATING CORRIDOR PLAN AND SECTIONS, INCLUDING SOME ISOMETRIC DETAILS. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    41. OPERATING CORRIDOR PLAN AND SECTIONS, INCLUDING SOME ISOMETRIC DETAILS. INEEL DRAWING NUMBER 200-0633-00-287-106455. FLUOR NUMBER 5775-CPP-633-P-60 - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  15. PBF Reactor Building (PER620). Fuel rod test assembly is on ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Fuel rod test assembly is on display at PBF. Date: 1982. INEEL negative no. 82-4893 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  16. PBF (PER620) interior. System control racks, secondary control and equipment ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior. System control racks, secondary control and equipment room. Date: May 2004. INEEL negative no. HD-41-6-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  17. SPERTI, Instrument Cell Building (PER606). West facade. Camera facing northeast. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I, Instrument Cell Building (PER-606). West facade. Camera facing northeast. Date: August 2003. INEEL negative no. HD-35-3-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. SPERTI, Instrument Cell Building (PER606). East facade. Camera facing southwest. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I, Instrument Cell Building (PER-606). East facade. Camera facing southwest. Date: August 2003. INEEL negative no. HD-35-3-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. 74. ARAII. Dr. William Zinn of combustion engineering company and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    74. ARA-II. Dr. William Zinn of combustion engineering company and others at controls of SL-1. August 8, 1959. Ineel photo no. 59-4109. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  20. IET. Stack interior. Masons lay fire brick liner, leaving air ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Stack interior. Masons lay fire brick liner, leaving air layer between bricks and concrete wall. Date: May 20, 1955. INEEL negative no. 55-1306 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. 41. ARAIII Prototype assembly and evaluation building ARA630. West end ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    41. ARA-III Prototype assembly and evaluation building ARA-630. West end and south side of building. Camera facing northeast. Ineel photo no. 3-22. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  2. LOFT. "Exploded view" of loft containment building (TAN650), including control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. "Exploded view" of loft containment building (TAN-650), including control building (TAN-630). EG&G. February 1979. INEEL index code no. 036-010-65-220-209565 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. 104. ARAIII. Interior view of room 110 in ARA607 used ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    104. ARA-III. Interior view of room 110 in ARA-607 used as data acquisition control room. Camera facing northeast. Ineel photo no. 81-103. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. IET. Typical detail during Snaptran reactor experiments. Shielding bricks protect ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Typical detail during Snaptran reactor experiments. Shielding bricks protect ion chamber beneath reactor on dolly. Photographer: Page Comiskey. Date: August 11, 1965. INEEL negative no. 65-4039 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. 8. ARAI Shop and maintenance building ARA627 interior view. Remains ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    8. ARA-I Shop and maintenance building ARA-627 interior view. Remains of cabinetry and electrical switch panel in one of rooms. Ineel photo no. 1-11. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  6. IET control building (TAN620). interior personnel service room. sign next ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET control building (TAN-620). interior personnel service room. sign next to shower stall says, "fight athlete's foot with sani-mist." INEEL negative no. HD-21-1-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. 29. FLOOR PLAN OF WASTE CALCINATION FACILITY SHOWING MAIN ABOVEGRADE ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    29. FLOOR PLAN OF WASTE CALCINATION FACILITY SHOWING MAIN ABOVE-GRADE FLOOR LEVEL. INEEL DRAWING NUMBER 200-0633-00-287-106354. FLUOR NUMBER 5775-CPP-633-A-4. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  8. PBF Reactor Building (PER620). PBF crane holds fuel test assembly ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). PBF crane holds fuel test assembly aloft prior to lowering into reactor for test. Date: 1982. INEEL negative no. 82-4909 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  9. SPERTI Control Building (PER601) floor plan. Detail of cable inlet. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Control Building (PER-601) floor plan. Detail of cable inlet. Idaho Operations Office. Date: February 1955. INEEL index no. 760-0601-00-396-109139 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. PBF Cooling Tower (PER720). Camera faces south to show north ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower (PER-720). Camera faces south to show north facade. Note enclosed stairway. Date: August 2003. INEEL negative no. HD-35-10-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  11. PBF Reactor Building (PER620). Canal takes shape, with rebar and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Canal takes shape, with rebar and concrete placement underway. Photographer: John Capek. Date: August 16, 1967. INEEL negative no. 67-4370 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. PBF Cooling Tower (PER720). Closeup detail of louvered wall panels ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower (PER-720). Close-up detail of louvered wall panels on south facade. Date: August 2003. INEEL negative no. HD-35-11-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  13. LPT. Shield test facility (TAN645) interior. Mechanical equipment room with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645) interior. Mechanical equipment room with switchgear and control boards. Photographer: Jack L. Anderson. Date: February 20, 1959. INEEL negative no. 59-858 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. 80. ARAIII. Forming of the mechanical equipment pit in reactor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    80. ARA-III. Forming of the mechanical equipment pit in reactor building (ARA-608). Camera facing northwest. September 22, 1958. Ineel photo no. 58-4675. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  15. LPT. Shield test facility (TAN645) interior. Mechanical equipment room with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-645) interior. Mechanical equipment room with airwasher and refrigeration compressor. Photographer: Jack L. Anderson. Date: February 20, 1959. INEEL negative no. 59-855 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. 51. ARAII. Camera looking southeast at foundation piers for SL1 ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    51. ARA-II. Camera looking southeast at foundation piers for SL-1 reactor building support. August 22, 1957. Ineel photo no. 57-4212. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  17. PBF Control Building auxiliary features, including fire hose house and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building auxiliary features, including fire hose house and sewage system. Ebasco Services 1205 PER/PER-A-4. INEEL undex no. 760-0619-00-205-123024 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. A&M. Radioactive parts security storage area. camera facing northwest. Outdoor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Radioactive parts security storage area. camera facing northwest. Outdoor storage of concrete storage casks. Photographer: M. Holmes. Date: November 21, 1959. INEEL negative no. 59-6081 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. 38. SECTIONS OF ACCESS CORRIDOR, INCLUDES SECTION SHOWING ARRANGEMENT OF ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    38. SECTIONS OF ACCESS CORRIDOR, INCLUDES SECTION SHOWING ARRANGEMENT OF NAVY GUN BARRELS. INEEL DRAWING NUMBER 200-0633-00-287-106454. FLUOR NUMBER 5775-CPP-633-P-59. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  20. A&M. Hot liquid waste holding tanks. Camera faces southeast. Located ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste holding tanks. Camera faces southeast. Located in vicinity of TAN-616, hot liquid waste treatment plant. Date: November 13, 1953. INEEL negative no. 9159 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. 24. ARAIII Reactor building ARA608 interior. Camera facing south. Chalk ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    24. ARA-III Reactor building ARA-608 interior. Camera facing south. Chalk marks on wall indicate presence or absence of spot contamination. Ineel photo no. 3-2. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

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

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    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 andmore » 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.« less

  3. LPT. Low power test (TAN641) interior. Heating and ventilating pneumatic ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-641) interior. Heating and ventilating pneumatic and electrical control panel. Contract nearly complete. Photographer: Jack L. Anderson. Date: December 19, 1957. INEEL negative no. 57-6198 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. LPT. Low power test control building (TAN641) east facade. Sign ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test control building (TAN-641) east facade. Sign says "Energy and Systems Technology Laboratory, INEL" (Post-ANP-use). Camera facing west. INEEL negative no. HD-40-3-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. 12. PHOTOGRAPH OF A PHOTOGRAPH OF A SCALE MODEL OF ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    12. PHOTOGRAPH OF A PHOTOGRAPH OF A SCALE MODEL OF THE WASTE CALCINER FACILITY, SHOWING WEST ELEVATION. (THE ORIGINAL MODEL HAS BEEN LOST.) INEEL PHOTO NUMBER 95-903-1-3. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  6. 3. CONTEXTUAL VIEW OF WASTE CALCINING FACILITY, CAMERA FACING NORTHEAST. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    3. CONTEXTUAL VIEW OF WASTE CALCINING FACILITY, CAMERA FACING NORTHEAST. SHOWS RELATIONSHIP BETWEEN DECONTAMINATION ROOM, ADSORBER REMOVAL HATCHES (FLAT ON GRADE), AND BRIDGE CRANE. INEEL PROOF NUMBER HD-17-2. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  7. 31. FLOOR PLANS OF WASTE CALCINATION FACILITY. SHOWS ACCESS CORRIDOR ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    31. FLOOR PLANS OF WASTE CALCINATION FACILITY. SHOWS ACCESS CORRIDOR AT MEZZANINE AND LOWER LEVELS. INEEL DRAWING NUMBER 200-0633-00-287-106352. FLUOR NUMBER 5775-CPP-633-A-2. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  8. 139. ARAIII Index of drwaings of gascooled reactor experiment buildings. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    139. ARA-III Index of drwaings of gas-cooled reactor experiment buildings. Aerojet-general 880-area/GCRE-100. Date: February 1958. Ineel index code no. 063-9999-80-013-102505. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  9. 105. ARAIII. Interior view of ARA608 highbay pit in 1983 ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    105. ARA-III. Interior view of ARA-608 high-bay pit in 1983 modified to contain high-temperature, high-pressure autoclave and furnace test area. Ineel photo no. 81-109. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  10. SPERTI Control Building (PER601). Elevations. Note cable inlet on west ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Control Building (PER-601). Elevations. Note cable inlet on west elevation. Idaho Operations Office. Date: February 1955. INEEL index no. 760-0601-00-396-109143 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  11. PBF Reactor Building (PER620). Floor at left of view is ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Floor at left of view is floor of first basement. Photographer: Farmer/Capek. Date: March 17, 1967. INEEL negative no. 67-1753 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. PBF Cooling Tower detail. Camera facing southwest. Wood fill rises ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower detail. Camera facing southwest. Wood fill rises from foundation piers of cold water basin. Photographer: Kirsh. Date: May 1, 1969. INEEL negative no. 69-2826 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  13. PBF (PER620) west facade. Camera facing east. Note 1980 addition ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) west facade. Camera facing east. Note 1980 addition on south side of west wall. Date: March 2004. INEEL negative no. HD-41-3-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  14. SPERTI, Instrument Cell Building (PER606). Oblique view of north and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I, Instrument Cell Building (PER-606). Oblique view of north and east facades. Camera facing southwest. Date: August 2003. INEEL negative no. HD-35-4-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  15. A&M. TAN607. Special equipment services room. Workers are filling viewing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Special equipment services room. Workers are filling viewing window with zinc bromide through tube penetrating concrete shield wall. Date: August 16, 1954. INEEL negative no. 11689 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. A&M. Special shielding materials. Stockpile of magnetite, used for making ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Special shielding materials. Stockpile of magnetite, used for making high-density concrete, and loading conveyor near TAN-607 construction site. Date: September 25, 1953. INEEL negative no. 8710 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. 39. CALCINER CELL PLANS. TOGETHER WITH HAER ID33C37 ILLUSTRATES COMPLEXITY ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    39. CALCINER CELL PLANS. TOGETHER WITH HAER ID-33-C-37 ILLUSTRATES COMPLEXITY OF PIPING. INEEL DRAWING NUMBER 200-0633-00-287-106445. FLUOR NUMBER 5775-CPP-633-P-50 - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  18. 40. CALCINER CELL SECTIONS. TOGETHER WITH HAER ID33C37 ILLUSTRATES COMPLEXITY ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    40. CALCINER CELL SECTIONS. TOGETHER WITH HAER ID-33-C-37 ILLUSTRATES COMPLEXITY OF PIPING. INEEL DRAWING NUMBER 200-0633-00-287-106446. FLUOR NUMBER 5775-CPP-P-51. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  19. 30. FLOOR PLANS OF WASTE CALCINATION FACILITY. SHOWS LEVELS ABOVE ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    30. FLOOR PLANS OF WASTE CALCINATION FACILITY. SHOWS LEVELS ABOVE GRADE AND AT LEVEL OF OPERATING CORRIDOR. INEEL DRAWING NUMBER 200-0633-00-287-106351. FLUOR NUMBER 5775-CPP-633-A-1. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  20. 146. ARAIII Control building (ARA607) Roof plan and details. Aerojetgeneral ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    146. ARA-III Control building (ARA-607) Roof plan and details. Aerojet-general 880-area/GCRE-607-A-3. Date: February 1958. Ineel index code no. 063-0607-00-013-102548. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  1. PBF (PER620) north facade. Camera facing south. Small metal shed ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) north facade. Camera facing south. Small metal shed at right is Stack Gas Monitor Building, PER-629. Date: March 2004. INEEL negative no. HD-41-2-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  2. 37. PLAN OF ACCESS CORRIDOR PIPING INCLUDES WASTE HOLD TANK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    37. PLAN OF ACCESS CORRIDOR PIPING INCLUDES WASTE HOLD TANK CELL, OFFGAS CELL, ADSORBER CELL, AND OFFGAS FILTER CELL. INEEL DRAWING NUMBER 200-0633-00-287-106453. FLUOR NUMBER 5775-CPP-P-58. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  3. 97. ARAIII. ML1 reactor has been moved into GCRE reactor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    97. ARA-III. ML-1 reactor has been moved into GCRE reactor building (ARA-608) for examination of corrosion on its underside and repair. May 24, 1963. Ineel photo no. 63-3485. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. 170. ARAIV Blast bunker installed after ML1 buildings were removed. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    170. ARA-IV Blast bunker installed after ML-1 buildings were removed. Isometric detail and section. EG&G Company. Date: June 1985. Ineel index code no. 066-0600-60-220-166261. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  5. LOFT. Containment and service building (TAN650). Roof plan and details. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Roof plan and details. Kaiser engineers 6413-11-STEP/LOFT-650-A-8. Date: October 1964. INEEL index code no. 036-650-00-486-122220 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. 166. ARAIII Fire hose houses (Probably numbered on site as ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    166. ARA-III Fire hose houses (Probably numbered on site as ARA-624). Aerojet-general 880-area/GCRE-701-S-4. Date: February 1958. Ineel index code no. 063-0624-00-013-102695. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  7. PBF Control Building (PER619). Interior in data acquisition room showing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619). Interior in data acquisition room showing data racks. The system recorded multiple channels of data during tests. INEEL negative no. HD-41-8-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. A&M. Hot liquid waste treatment building (TAN616). Camera facing east. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616). Camera facing east. Showing west facades of structure. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-1-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. IET control building (TAN620). equipment removed. Lube oil and waste ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET control building (TAN-620). equipment removed. Lube oil and waste piping at upper right. Fire door on right. Rebar exposed in concrete of ceiling. INEEL negative no. HD-21-5-3 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. PBF Control Building (PER619) south facade. Camera faces north. Note ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619) south facade. Camera faces north. Note buried tanks with bollards protecting their access hatches. Date: July 2004. INEEL negative no. HD-41-10-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  11. A&M. Outdoor turntable. Workings and design exposed during demolition. View ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Outdoor turntable. Workings and design exposed during demolition. View between two of the four rails of the track. Note motor and electrical conduit. Date: February 3, 2003. INEEL negative no. HD-37-1-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. LPT. Shield test control building (TAN645), north facade. Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test control building (TAN-645), north facade. Camera facing south. Obsolete sign dating from post-1970 program says "Energy and Systems Technology Experimental Facility, INEL." INEEL negative no. HD-40-5-4 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. LOFT. Interior view of entry (TAN624) rollup door. Camera is ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Interior view of entry (TAN-624) rollup door. Camera is inside entry building facing south. Rollup door was a modification of the original ANP door arrangement. Date: March 2004. INEEL negative no. HD-39-5-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. 123. ARAI Substation (ARA726) plan, elevation, security fence details, and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    123. ARA-I Substation (ARA-726) plan, elevation, security fence details, and sections. Norman Engineering Company 961-area/SF-726-E-1. Date: January 1959. Ineel index code no. 068-0726-10-613-102778. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  15. 144. ARAIII Control building (ARA607) Foundation plan. Aerojetgeneral 880area/GCRE607S1. Date: ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    144. ARA-III Control building (ARA-607) Foundation plan. Aerojet-general 880-area/GCRE-607-S-1. Date: February 1958. Ineel index code no. 063-0607-60-013-102568. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. PBF Reactor Building (PER620). Camera in first basement, facing south ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera in first basement, facing south and upward toward main floor. Cable trays being erected. Photographer: Kirsh. Date: May 20, 1969. INEEL negative no. 69-3110 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  17. PBF (PER620) interior, second basement level. Coolant and tank piping. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, second basement level. Coolant and tank piping. Mark on vertical pipe says, "H.P. Demin. Water." (High pressure demineralized water.) Date: March 2004. INEEL negative no. HD-41-4-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. PBF (PER620) interior, basement level. Concrete wall shows outline of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, basement level. Concrete wall shows outline of reactor basin. Sign says, "Flashing Light - Reactor On - Evacuate Area." Date: May 2004. INEEL negative no. HD-41-5-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. PBF (PER620) south facade. Camera facing north. Note pedestrian bridge ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) south facade. Camera facing north. Note pedestrian bridge crossing over conduit. Central high bay contains reactor room and canal. Date: March 2004. INEEL negative no. HD-41-2-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  20. SPERTI Terminal Building (PER604) with view into interior. Storage tanks ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Terminal Building (PER-604) with view into interior. Storage tanks and equipment in view. Camera facing west. Photographer: R.G. Larsen. Date: May 20, 1955. INEEL negative no. 55-1291 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  1. LPT. Low power test (TAN641) interior of mechanical equipment room. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-641) interior of mechanical equipment room. Air compressors in left foreground. Evaporate condenser in right background. Construction 93% complete. Photographer: Jack L. Anderson. Date: October 23, 1957. INEEL negative no. 57-5340 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  2. 87. ARAIII. GCRE reactor building (ARA608) Mechanical equipment room. Utility ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    87. ARA-III. GCRE reactor building (ARA-608) Mechanical equipment room. Utility air receiver, dryer, and compressor sit on their foundations prior to grouting. December 22, 1958. Ineel photo no. 58-6429. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  3. 65. ARAII. Interior view of SL1 reactor building control piping ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    65. ARA-II. Interior view of SL-1 reactor building control piping for water purification system. On operating floor of building. March 21, 1958. Ineel photo no. 58-1360. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. PBF Control Building (PER619). Interior of control room shows control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619). Interior of control room shows control console from direction facing visitors room and its observation window. Camera facing northeast. Date: May 2004. INEEL negative no. HD-41-7-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  5. 154. ARAIII Reactor building (ARA608) Foundation sections and details. Shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    154. ARA-III Reactor building (ARA-608) Foundation sections and details. Shows profiles of pits. Aerojet-general 888-area/GCRE-608-S-2. Date: February 1958. Ineel index code no. 062-0608-60-013-102654. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  6. 153. ARAIII Reactor building (ARA608) Foundation plan. Aerojetgeneral 880area/GCRE608S1. Date: ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    153. ARA-III Reactor building (ARA-608) Foundation plan. Aerojet-general 880-area/GCRE-608-S-1. Date: February 1958. Ineel index code no. 063-0608-60-013-102653. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  7. IET. Control and equipment building (TAN620) sections. Depth and profile ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Control and equipment building (TAN-620) sections. Depth and profile of earthen shield tunnels. Ralph M. Parsons 902-4-ANP-620-A-321. Date: February 1954. INEEL index code no. 035-0620-00-693-106906 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. 152. ARAIII Reactor building (ARA608) Details of heater and piping ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    152. ARA-III Reactor building (ARA-608) Details of heater and piping pits, including instrumentation plan. Aerojet-general 880-area/GCRE-608-T-18. Date: November 1958. Ineel index code no. 063-0608-25-013-102677. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  9. 149. ARAIII Reactor building (ARA608) Exterior elevations, showing north, south, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    149. ARA-III Reactor building (ARA-608) Exterior elevations, showing north, south, east, and west. Aerojet-general 880-area/GCRE-608-A-6. Date: February 1958. Ineel index code no. 063-0608-00-013-102615. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  10. LOFT. Containment and service building (TAN650). Room number schedule, sheet ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Room number schedule, sheet 2 of 2. Kaiser engineers 6413-11-STEP/LOFT-650-A-XX. Date: October 1969. INEEL index code no. 036-650-00-486-122228 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. 151. ARAIII Reactor building (ARA608) Details of reactor pit and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    151. ARA-III Reactor building (ARA-608) Details of reactor pit and instrument plan. Aerojet-general 880-area/GCRE-608-T-19. Date: November 1958. Ineel index code no. 063-0608-25-013-102678. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  12. PBF Cooling Tower Auxiliary Building (PER624) interior. Camera facing north. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower Auxiliary Building (PER-624) interior. Camera facing north. Deluge valves and automatic fire protection piping for Cooling Tower. Photographer: Holmes. Date: May 20, 1970. INEEL negative no. 70-2323 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  13. PBF Reactor Building (PER620) Cubicle 13. Plan, section, details. Note ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620) Cubicle 13. Plan, section, details. Note "quality assurance" code at bottom of drawing. Aerojet Nuclear Company. Date: May 1976. INEEL index no. 761-0620-00-400-195279 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  14. A&M. Hot liquid waste treatment building (TAN616). Camera facing northeast. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616). Camera facing northeast. South wall with oblique views of west sides of structure. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-1-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. A&M. Hot liquid waste treatment building (TAN616). Camera facing north. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616). Camera facing north. Detail of personnel entrance door, stoop, and stairway. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-2-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. PBF Cubicle 13. Shield wall details illustrate shielding technique of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cubicle 13. Shield wall details illustrate shielding technique of stepped penetrations and brick layout scheme for valve stem extension sleeve. Aerojet Nuclear Company. Date: May 1976. INEEL index no. 761-0620-00-400-195280 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  17. PBF (PER620) interior, first basement. Detail of valves and other ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior, first basement. Detail of valves and other penetrations along wall. Bricks are made of high density shielding materials. Date: March 2004. INEEL negative no. HD-41-4-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. SPERTI Electric Control Building (PER608). Plan, elevations, and details. Gibbs ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Electric Control Building (PER-608). Plan, elevations, and details. Gibbs and Hill, Inc. 1087-PER-608-S5. Date: August 1956. INEEL index no. 760-0608-00-312-108328 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. A&M. TAN607. Southern sections added in expansion project of 1957. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Southern sections added in expansion project of 1957. Camera facing northwest. Concrete decontamination section on left end. Photographer: Jack L. Anderson. Date: October 23, 1957. INEEL negative no. 57-5337 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. 156. ARAIII Reactor building (ARA608) Electrical and control details of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    156. ARA-III Reactor building (ARA-608) Electrical and control details of mobile work bridge over reactor and pipiing pits. Aerojet-general 880-area/GCRE-608-E-6. Date: November 1958. Ineel index code no. 063-0608-10-013-102621. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  1. SPERTI Terminal Building (PER604). Oblique view of front entry and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Terminal Building (PER-604). Oblique view of front entry and one side. Electrical transformers at right of building. Note "Butler" logo. Photographer: R.G. Larsen. Date: June 22, 1955. INEEL negative no. 55-1700 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  2. IET control building (TAN620). interior service area. equipment on concrete ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET control building (TAN-620). interior service area. equipment on concrete pads. liquid pump and valves on right. control panel at center of view, blower at left. piping for vent and sanitary sewer. INEEL negative no. HD-21-3-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. LPT. Shield test facility test building interior (TAN646). Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility test building interior (TAN-646). Camera facing south. Distant pool contained EBOR reactor; near pool was intended for fuel rod storage. Other post-1970 activity equipment remains in pool. INEEL negative no. HD-40-9-4 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. LPT. Shield test facility test building interior (TAN646). Camera points ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility test building interior (TAN-646). Camera points down into interior of north pool. Equipment on wall is electronical bus used for post-1970 experiment. Personnel ladder at right. INEEL negative no. HD-40-9-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. PBF Cooling Tower. View of stairway to fan deck. Vents ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower. View of stairway to fan deck. Vents are made of redwood. Camera facing southwest toward north side of Cooling Tower. Siding is corrugated asbestos concrete. Photographer: Kirsh. Date: June 6, 1969. INEEL negative no. 69-3463 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  6. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael J. Driscoll; Pavel Hejzlar; Peter Yarsky

    2005-12-09

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design Task; and D: Fuel Design.

  7. 32. SECTIONS AA, BB, CC, DD, AND EE WASTE CALCINATION ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    32. SECTIONS A-A, B-B, C-C, D-D, AND E-E WASTE CALCINATION FACILITY SHOWING RELATIONSHIPS OF DIFFERENT FLOOR LEVELS TO ONE ANOTHER. INEEL DRAWING NUMBER 200-0633-00-287-106353. FLUOR NUMBER 5775-CPP-633-A-3. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  8. 36. ARCHITECTURAL AND STRUCTURAL DETAILS OF ELEVATOR HOUSING, NaK HEATER ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    36. ARCHITECTURAL AND STRUCTURAL DETAILS OF ELEVATOR HOUSING, NaK HEATER STACK ROOF FLASHING, HOOD ELEVATION DETAIL. INCLUDES PARTIAL 'BILL OF MATERIAL.' INEEL DRAWING NUMBER 200-0633-00-287-106361. FLUOR NUMBER 5775-CPP-633-A-11. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  9. LPT. EBOR (TAN646). Floor plan for new helium management wing. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. EBOR (TAN-646). Floor plan for new helium management wing. Detail of sample vault and basement switch room. Kaiser engineers EBOR/GA-646-A-101. Date: May 1963. INEEL index code no. 037-0646-00-486-119115 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. LOFT. Interior, control room in control building (TAN630). Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Interior, control room in control building (TAN-630). Camera facing north. Sign says "This control console is partially active. Do not operate any switch handle without authorization." Date: May 2004. INEEL negative no. HD-39-14-3 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. LPT. Shield test facility (TAN646) exterior, as modified for EBOR. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-646) exterior, as modified for EBOR. Camera facing northeast. Heat exchange fans, helium storage tanks, and completed EBOR perimeter road. Photographer: Page Comisky. Date: ca. August 20, 1965. INEEL negative no. 65-4328 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. 141. ARAIII Equipment location plan. Includes list of equipment and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    141. ARA-III Equipment location plan. Includes list of equipment and location in reactor, control, and other buildings. Aerojet-general 880-area/GCRE-101-U-1. Date: February 1958. Ineel index code no. 063-0101-65-013-192508. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  13. 132. ARAII Administration building (ARA613) elevations of north, south, east, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    132. ARA-II Administration building (ARA-613) elevations of north, south, east, and west sides. F. C. Torkelson Company 842-area/SL-1-613-A-2. Date: October 1959. Ineel index no. 070-0613-00-851-150054. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  14. 119. ARAI Shop and maintenance (ARA627) building sections and details ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    119. ARA-I Shop and maintenance (ARA-627) building sections and details of interior mesh partitions. Norman Engineering Company 961-area/SF-627-A-3. Date: January 1959. Ineel index code no. 068-0627-00-613-102761. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  15. 117. ARAI Shop and maintenance (ARA627) building roof and floor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    117. ARA-I Shop and maintenance (ARA-627) building roof and floor plan. Includes room finish and equipment schedule. Norman Engineering Company 961-area/SF-627-A-1. Date: January 1959. Ineel index code no. 068-0627-00-613-102759. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. 140. ARAIII Grading and drainage plan showing plot plan, including ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    140. ARA-III Grading and drainage plan showing plot plan, including berms around waste storage tank and fuel oil storage tank. Aerojet-general 880-area-GCRE-101-1. Date: February 1958. Ineel index code no. 063-0101-00-013-102507. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  17. 112. ARAI Hot cell (ARA626) Building roof plan and details ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    112. ARA-I Hot cell (ARA-626) Building roof plan and details of roof ventilating equipment and parapet. Norman Engineering Company: 961-area/SF-626-A-2. Date: January 1959. Ineel index code no. 068-0626-00-613-102722. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  18. A&M. TAN607. Detail of control gallery for special services cubicle ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Detail of control gallery for special services cubicle (hot cell) at "100 percent complete." Cover has been removed from cable channel at middle window. Date: January 24, 1995. INEEL negative No. 55-0140 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. IET. Control room in control building (TAN620). Terminal panels for ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Control room in control building (TAN-620). Terminal panels for instrumentation wiring. Note alarm horn and emergency light at right edge of view. Cable reel comes from Collier, Pawtucket, RI. Date: February 1955. INEEL negative no. 55-362 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. SPERTI Terminal Building (PER604). Concrete foundation is at grade. Steel ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Terminal Building (PER-604). Concrete foundation is at grade. Steel frame has been erected, and some siding has been affixed. Photographer: R.G. Larsen. Date: April 22, 1955. INEEL negative no. 55-1003 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  1. PBF. Oblique and contextual view of PBF Cooling Tower, PER720. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF. Oblique and contextual view of PBF Cooling Tower, PER-720. Camera facing northeast. Auxiliary Building (PER-624) abuts Cooling Tower. Demolition equipment has arrived. Date: August 2003. INEEL negative no. HD-35-11-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  2. PBF Reactor Building (PER620). Camera in second basement near subpile ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera in second basement near sub-pile room (directly below reactor vessel). Door and penetrations lead to sub-pile room. Date: August 15, 1969. Photographer: Larry Page. INEEL negative no. 69-4310 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  3. PBF Cooling Tower contextual view. Camera facing southwest. West wing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower contextual view. Camera facing southwest. West wing and north facade (rear) of Reactor Building (PER-620) is at left; Cooling Tower to right. Photographer: Kirsh. Date: November 2, 1970. INEEL negative no. 70-4913 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  4. PBF (PER620) interior. Detail view of door in north wall ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior. Detail view of door in north wall of reactor bay. Camera facing north. Note tonnage weighting of hatch covers in floor. Date: May 2004. INEEL negative no. HD-41-8-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  5. PBF (PER620) interior. Detail view of actuator platform and control ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior. Detail view of actuator platform and control rod mechanism. Camera facing easterly from floor level. Reactor pool at lower left of view. Date: March 2004. INEEL negative no. HD-41-3-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  6. PBF Reactor Building (PER620). Camera faces southeast. Concrete placement will ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera faces southeast. Concrete placement will leave opening for neutron camera to be installed later. Note vertical piping within rebar. Photographer: John Capek. Date: July 6, 1967. INEEL negative no. 67-3514 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  7. PBF Reactor Building (PER620). Aerial view of early construction. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Aerial view of early construction. Camera facing northwest. Excavation and concrete placement in two basements are underway. Note exposed lava rock. Photographer: Farmer. Date: March 22, 1965. INEEL negative no. 65-2219 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. PBF Reactor Building (PER620). Reactor vessel arrives from gate city ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Reactor vessel arrives from gate city steel at door of PBF. On flatbed, it is too high to fit under door. Photographer: Larry Page. Date: February 13, 1970. INEEL negative no. 70-737 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  9. PBF Reactor Building (PER620). Camera faces north into highbay/reactor pit ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera faces north into high-bay/reactor pit area. Inside from for reactor enclosure is in place. Photographer: John Capek. Date: March 15, 1967. INEEL negative no. 67-1769 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. PBF Reactor Building (PER620). Camera facing south end of high ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera facing south end of high bay. Vertical-lift door is being installed. Later, pneumatic seals will be installed around door. Photographer: Kirsh. Date: September 31, 1968. INEEL negative no. 68-3176 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  11. SPERTI plot plan for control area. Includes Control Building (PER601), ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I plot plan for control area. Includes Control Building (PER-601), Gate House (PER-603), well sand settling tank, substation, and septic system. Date: February 1955. INEEL index no. 760-0101-00-396-109104 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. 90. ARAIII. GCRE reactor building (ARA608) mechanical loop pit. Shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    90. ARA-III. GCRE reactor building (ARA-608) mechanical loop pit. Shows nitrogen gas compressor in foreground, piping installations on walls of pit, and other details. February 24, 1959. Ineel photo no. 59-880. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  13. 9. DETAIL VIEW OF BRIDGE CRANE ON WEST SIDE OF ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    9. DETAIL VIEW OF BRIDGE CRANE ON WEST SIDE OF BUILDING. CAMERA FACING NORTHEAST. CONTAMINATED AIR FILTERS LOADED IN TRANSPORT CASKS WERE TRANSFERRED TO VEHICLES AND SENT TO RADIOACTIVE WASTE MANAGEMENT COMPLEX FOR STORAGE. INEEL PROOF NUMBER HD-17-1. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  14. LOFT. Reactor arrives at containment building (TAN650), now being pushed ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Reactor arrives at containment building (TAN-650), now being pushed by locomotive. Camera facing northerly. Note "Hello Dolly" and "PWR MTA No. 1" (pressurized water reactor mobile test assembly) signs. Date: 1973. INEEL negative no. 73-3710 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. 168. ARAIV Index of drawings prepared by Norman Engineering Company ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    168. ARA-IV Index of drawings prepared by Norman Engineering Company in preparation for construction of ARA-IV. Norman Engineering Company 961-area/ML-1index. Date: March 1961. Ineel index code no. 066-9999-90-613-102731. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. PBF Reactor Building (PER620) as seen from control room window ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620) as seen from control room window in PER-619. Photographer stood just outside window. Note exposed communication cables on desert surface. Date: July 2004. INEEL negative no. HD-41-9-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  17. LOFT. Containment and service building (TAN650). Sections H, K, and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Sections H, K, and L; details of pre-amp tower. Kaiser engineers 6413-11-STEP/LOFT-650-A-14. Date: January 1966. INEEL index code no. 036-650-00-486-122226 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. 147. ARAIII Control building (ARA607) Detail of instrument rack and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    147. ARA-III Control building (ARA-607) Detail of instrument rack and control console in control room. Aerojet-general 880-area/GCRE-607-E-4. Date: November 1958. Ineel index code no. 063-0607-10-013-102560. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  19. PBF Cooling Tower. Camera facing southwest. Round piers will support ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower. Camera facing southwest. Round piers will support Tower's wood "fill" or "packing." Black-topped stack in far distance is at Idaho Chemical Processing Plant. Photographer: John Capek. Date: October 16, 1968. INEEL negative no. 68-4097 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  20. LOFT. Containment and service building (TAN650) basement floor plan. Basement ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650) basement floor plan. Basement airlock, shielded roadway, service areas, connection to control building. Kaiser engineers 6413-11-STEP/LOFT-650-A-1. Date: October 1964. INEEL index code no. 036-650-00-416-122213 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. A&M. Technical service laboratory in administration building (TAN602). Floor plan, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Technical service laboratory in administration building (TAN-602). Floor plan, reception desk, door and finish schedules. Ralph M. Parsons 1480-12-ANP/GE-3-602-A-1. INEEL index code no. 033-0602-00-693-107488 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  2. 155. ARAIII Reactor building (ARA608) Details of reactor pit showing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    155. ARA-III Reactor building (ARA-608) Details of reactor pit showing tray supports and fuel element storage rack. Aerojet-general 880-area/GCRE-608-MS-2. Date: November 1958. Ineel index code no. 063-0608-40-013-102625. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  3. 160. ARAIII Service building (ARA610). Includes floor plan, north and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    160. ARA-III Service building (ARA-610). Includes floor plan, north and west elevations, and section details. Aerojet-general 880-area/GCRE-610-A-1. Date: February 1958. Ineel index code no. 063-0610-00-013-102684. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. A&M. Gate House (TAN601). Plan, elevations, sections, details. Shows expanded ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Gate House (TAN-601). Plan, elevations, sections, details. Shows expanded building as attached to TAN-602. Ralph M. Parsons 902-2-ANP-601-A 22. Date: December 1952. INEEL index code no. 033-0602-00-693-106704 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. ADM. Change House (TAN606) as completed. Camera facing northerly. Note ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Change House (TAN-606) as completed. Camera facing northerly. Note proximity to shielding berm. Part of hot shop (A&M Building, TAN-607) at left of view beyond berm. Date: October 29, 1954. INEEL negative no. 12705 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. PBF Reactor Building (PER620). Cubicle 10 detail. Camera facing west ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Cubicle 10 detail. Camera facing west toward brick shield wall. Valve stems against wall penetrate through east wall of cubicle. Photographer: John Capek. Date: August 19, 1970. INEEL negative no. 70-3469 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  7. SPERTI Reactor Pit Building (PER605) from contrasting direction as photo ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Reactor Pit Building (PER-605) from contrasting direction as photo above (ID-33-F-32). Note Guard House door, security fencing around facility. Photographer: R.G. Larsen. Date: July 22, 1955. INEEL negative no. 55-1702. - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. THE DOE COMPLEX-WIDE VADOSE ZONE SCIENCE AND TECHNOLOGY ROADMAP: CHARACTERIZATION MODELING AND SIMULATION OF SUBSURFACE CONTAMINANT FATE AND TRANSPORT

    EPA Science Inventory

    The Idaho National Engineering & Environmental Lab (INEEL) was charged by DOE EM to develop a complex-wide science and technology roadmap for the characterization, modeling and simulation of the fate and transport of contamination in the vadose zone. Various types of hazardous, r...

  9. A&M. Guard house (TAN638), contextual view. Built in 1968. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Guard house (TAN-638), contextual view. Built in 1968. Camera faces south. Guard house controlled access to radioactive waste storage tanks beyond and to left of view. Date: February 4, 2003. INEEL negative no. HD-33-4-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. LOFT. Reactor apparatus leaves A&M building (TAN607). Shielded locomotive has ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Reactor apparatus leaves A&M building (TAN-607). Shielded locomotive has aerojet logo, which replaced old general electric logo, pulls reactor from assembly shop on dolly. Camera facing easterly. Date: 1973. INEEL negative no. 73-3700 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. PBF Reactor Building (PER620). Detail of arrangement of highdensity blocks ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Detail of arrangement of high-density blocks and other basement shielding. Date: February 1966. Ebasco Services 1205 PER/PBF 620-A-7. INEEL index no. 761-0620-00-205-123070 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. LPT. Low power test control building (TAN641) interior. Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test control building (TAN-641) interior. Camera facing northeast at what remains of control room console. Cut in wall at right of view shows west wall of northern test cell. INEEL negative no. HD-40-4-4 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. LPT. Low power assembly and test building (TAN640). Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power assembly and test building (TAN-640). Camera facing west. Rollup doors to each test cell face east. Concrete walls poured in place. Apparatus at right of view was part of a post-ANP program. INEEL negative no. HD-40-1-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. LPT. Shield test facility assembly and test building (TAN646), south ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility assembly and test building (TAN-646), south facade. Camera facing north. High-bay section is pool room. Single-story section at right is control building (TAN-645). Small metal building is post-1970 addition. INEEL negative no. HD-40-7-3 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. 44. ARAIII Fuel oil tank ARA710. Camera facing west. Perimeter ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    44. ARA-III Fuel oil tank ARA-710. Camera facing west. Perimeter fence at left side of view. Gable-roofed building beyond tank on right is ARA-622. Gable-roofed building beyond tank on left is ARA-610. Ineel photo no. 3-16. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. 114. ARAI Hot cell (ARA626) Building details of fuel storage ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    114. ARA-I Hot cell (ARA-626) Building details of fuel storage pit in plan and section. Spaces shown for 20 elements. Norman Engineering Company: 961-area/SF-626-S-4. Date: January 1959. Ineel index code no. 068-0626-60-613-102752. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  17. PBF Reactor Building (PER620). Cubicle 10 area in basement. Highdensity ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Cubicle 10 area in basement. High-density shielding bricks will protect personnel from radiation coming from in-pile-tube coolant and blowdown tank. Photographer: John Capek. Date: January 26, 1970. INEEL negative no. 70-348 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. 72. ARAII. Interior view in ARA602 support building showing oilfired ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    72. ARA-II. Interior view in ARA-602 support building showing oil-fired hot air furnace and hot water boiler in foreground; hot water tank and diesel generator in background. December 12, 1957. Ineel photo no. 57-6099. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  19. PBF Control Building (PER619). Interior detail of control room's severe ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619). Interior detail of control room's severe fuel damage instrument panel. Indicators provided real-time information about test underway in PBF reactor. Note audio speaker. Date: May 2004. INEEL negative no, HD-41-7-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  20. ADM. Tanks: from left to right: fuel oil tank, fuel ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Tanks: from left to right: fuel oil tank, fuel pump house (TAN-611), engine fuel tank, water pump house, water storage tank. Camera facing northwest. Not edge of shielding berm at left of view. Date: November 25, 1953. INEEL negative no. 9217 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. PBF Reactor Building (PER620). Detail of fuel test assembly in ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Detail of fuel test assembly in preparation for test. When complete, it will fit into in-pile tube. The maximum outside diameter of which must be about 8.25 inches. Date: 1982. INEEL negative no. 82-4908 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  2. 86. ARAIII. GCRE reactor building (ARA608) showing mechanical loop pit ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    86. ARA-III. GCRE reactor building (ARA-608) showing mechanical loop pit after building shell had been erected. Beyond pit are demineralized water surge tank and heat exchanger. Camera facing northeast. December 22, 1958. Ineel photo no. 58-6427. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  3. 129. ARAII Administrative and technical support building (ARA606) sections showing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    129. ARA-II Administrative and technical support building (ARA-606) sections showing roof and wall details and longitudinal section. C.A. Sundberg and Associates 866-area/ALPR-606-A-5. Date: May 1958. Ineel index code no. 070-0606-00-822-102828. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. 142. ARAIII General plan of GCRE area, including electrical distribution ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    142. ARA-III General plan of GCRE area, including electrical distribution plan for power and lighting. Includes detail of floodlight and security lighting poles and fixtures. Aerojet-general 880-area/GCRE-406-1. Date: February 1958. Ineel index code no. 063-0406-00-013-102539. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  5. 121. ARAI Guard house (ARA628). Drawing shows north, south, east, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    121. ARA-I Guard house (ARA-628). Drawing shows north, south, east, and west elevations, floor plan, counter details, and roof plan. Norman Engineering Corporation 961-area/SF-628-A-1. Date: January 1959. Ineel index code no. 063-0628-00-613-102772. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  6. 145. ARAIII Control building (ARA607) Sections. Shows highbay section of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    145. ARA-III Control building (ARA-607) Sections. Shows high-bay section of building over crane rail and beam. Indicates materials of exterior siding. Aerojet-general 880-area/GCRE-607-A-11. Date: February 1958. Ineel index code no. 063-0607-00-013-102556. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  7. 128. ARAII Administrative and technical support building (ARA606) elevations for ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    128. ARA-II Administrative and technical support building (ARA-606) elevations for northwest, southwest, northeast, and southeast sides. C.A. Sundberg and Associates 866-area/ALPR-606-A-3. Date: May 1958. Ineel index code no. 070-0606-00-822-102826. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  8. 47. ARAI. Interior view of operating wall of hot cell ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    47. ARA-I. Interior view of operating wall of hot cell in ARA-626. Note stands for operators at viewing windows. Manipulators with hand grips extend cables and other controls into hot cell through ducts above windows. Ineel photo no. 81-27. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  9. PBF (PER620) interior. Detail view across top of reactor tank. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior. Detail view across top of reactor tank. Camera facing northeast. Ait tubing is cleanup equipment. Note projections from reactor structure above water level in tank. Date: May 2004. INEEL negative no. HD-41-5-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. PBF Cooling Tower (PER720) and its Auxiliary Building (PER625). Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower (PER-720) and its Auxiliary Building (PER-625). Camera facing west shows east facades. Center pipe carried secondary coolant water from reactor. Building to distributor basin. Date: August 2003. INEEL negative no. HD-35-10-1 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  11. General layout of reactor and control areas upon advent of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    General layout of reactor and control areas upon advent of power burst facility (PBF). Shows relationship of PBF to SPERT-I, -II, -III, and -IV. Ebasco Services 1205-PER/PBF-U-102. Date: July 1965. INEEL index no. 761-0100-00-205-123006 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. LOFT. Containment building entry, an adapted use of TAN624, which ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment building entry, an adapted use of TAN-624, which originated as the mobile test building for the ANP program. Camera facing north. Note four-rail track entered building stack at right of view. Date: March 2004. INEEL negative no. HD-39-4-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. PBF Cooling Tower (PER720), and Auxiliary Building (PER624). Camera faces ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower (PER-720), and Auxiliary Building (PER-624). Camera faces north to show south facades. Oblong vertical structure at left of center is weather shield for stairway. Date: August 2003. INEEL negative no. HD-35-10-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  14. A&M. TAN607. Detail of installed hot shop viewing window almost ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Detail of installed hot shop viewing window almost complete. Cable channel is still exposed, lacking cover. Note bottle in upper left corner containing spare zinc bromide in even of leak from window. Date: October 20, 1954. INEEL negative no. 12560 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. 77. ARAII. Room at northeast corner of ARA606 used for ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    77. ARA-II. Room at northeast corner of ARA-606 used for welding training and welding procedure qualification and performance testing. This was only building in use at ARA-II by 1983. Date: 1983. Ineel photo no. 83-476-3-5. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. LOFT, TAN650. Service building preamp tower, top three floors. Floor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT, TAN-650. Service building pre-amp tower, top three floors. Floor plan, cable mazes, duct labyrinth. Borated water tank enclosure on roof. Kaiser engineers 6413-11-STEP/LOFT-650-A-3. Date: October 1964. INEEL index code no. 036-650-00-486-122215 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. SPERTI Control Building (PER601) interior. Control panel with data readout ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Control Building (PER-601) interior. Control panel with data readout equipment in control room. Panels and equipment were fabricated elsewhere at NRTS during SPERT-I construction. Photographer: R.G. Larsen. Date: November 21, 1955. INEEL negative no. 55-3208 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. IET control building (TAN620). control room. facing north. control consoles ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET control building (TAN-620). control room. facing north. control consoles have been removed. Openings in floor were communication and control conduits. Periscope controls at center left (see also HAER No. ID-33-E-20). INEEL negative no. HD-21-3-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. 150. ARAIII Reactor building (ARA608) Sections. Show highbay section, heater ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    150. ARA-III Reactor building (ARA-608) Sections. Show high-bay section, heater stack, and depth of reactor, piping, and heater pits. Aerojet-general 880-area/GCRE-608-A-3. Date: February 1958. Ineel index code no. 063-0608-00-013-102613. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  20. 79. ARAIII. Early construction view of GCRE reactor building (ARA608) ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    79. ARA-III. Early construction view of GCRE reactor building (ARA-608) showing deep excavation, reinforcing steel, and forms for concrete placement for reactor and other pits. Camera facing southeast. July 22, 1958. Ineel photo no. 58-3466. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  1. 138. ARAII Building ARA606 floor plan for remodel as Inel ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    138. ARA-II Building ARA-606 floor plan for remodel as Inel Welding Laboratory. Shows room divisions and welding stations to be installed. Aerojet Nuclear Company 1375-ARA-II-606-E-2. Date: June 1976. Ineel index code no. 070-0606-10-400-156552. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  2. PBF Control Building (PER619) floor plan and elevations. Room numbers ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619) floor plan and elevations. Room numbers and functions. Roof plans for "high" roof and rest of roof. Ebasco Services 1205-PER/PER 619-A-1. Date: July 1965. INEEL index no. 760-0619-00-205-123022 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  3. LPT. Low power test (TAN640) interior. Basement level. Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-640) interior. Basement level. Camera facing north. Cable trays and conduit cross tunnel between critical experiment cell and critical experiment control room. Construction 93% complete. Photographer: Jack L. Anderson. Date: October 23, 1957. INEEL negative no. 57-5339 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. LPT. Shield test facility assembly and test building (TAN646), south ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility assembly and test building (TAN-646), south end of EBOR helium wing. Camera facing north. Monorail protrudes from upper-level door. Rust marks on concrete wall are from stack. Metal shed is post-1970 addition. INEEL negative no. HD-40-8-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. PBF Cooling Tower (PER720). Camera faces east to show west ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower (PER-720). Camera faces east to show west facade. Sloped (louvered) panels in this and opposite facade allow air to enter tower and cool water falling on splash bars within. Date: August 2003. INEEL negative no. HD-35-10-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  6. 126. ARAII Plot plan showing location of SL1 power plant ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    126. ARA-II Plot plan showing location of SL-1 power plant (reactor) building, and planned location of administrative and technical support building. C.A. Sundberg and Associates 866-area/ALPR-606-U-1. Date: May 1958. Ineel index code no. 070-0100-00-822-102834. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  7. 110. ARAI support facilities. Index of drawings related to initial ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    110. ARA-I support facilities. Index of drawings related to initial construction of hot cell building ARA-626, shop and maintenance building ARA-627, and other buildings at ARA-I. Date: Circa January 1959. Norman Engineering Company. Ineel index code no. 068-9999-80-613-102703. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  8. 148. ARAIII Reactor building (ARA608) Floor plan. Shows location of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    148. ARA-III Reactor building (ARA-608) Floor plan. Shows location of reactor, heater, and mechanical loop pits; mechanical and electrical equipment rooms; and other work areas. Aerojet-general 880-area/GCRE-608-A-1. Date: February 1958. Ineel index code no. 063-0608-00-013-102612. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  9. 116. ARAI Details of hot cell section of building ARA626. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    116. ARA-I Details of hot cell section of building ARA-626. Shows manipulator openings in operating face of hot cell, start/stop buttons, and other details. Norman Engineering Company 961/area/SF-626-E-6. Date: January 1959. Ineel index code no. 068-0626-10-613-102731. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  10. 137. ARAII Building ARA602 floor plan as it appeared in ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    137. ARA-II Building ARA-602 floor plan as it appeared in 1980 when electrical modifications were being made. Shows partial layout of floor plan. EG&G Idaho, Inc. 1570-ARA-II-602-E-3. Date: April 1980. Ineel index code no. 070--0602-10-220-159761. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  11. 111. ARAI Hot cell (ARA626) Building elevations of north, south, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    111. ARA-I Hot cell (ARA-626) Building elevations of north, south, east, and west sides. Includes details of personnel decontamination area, dark room, and other features. Norman Engineering Company: 961-area/SF-626-A-3. Date: January 1959. Ineel index code no. 068-0626-00-613-102723. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  12. 118. ARAI Shop and maintenance (ARA627) building elevations of north, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    118. ARA-I Shop and maintenance (ARA-627) building elevations of north, south, east, and west sides and other details of door and window types. Norman Engineering Company 961-area/SF-627-A-2. Date: January 1959. Ineel index code no. 068-0627-00-613-102760. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  13. 127. ARAII Administrative and technical support building (ARA606) ground floor ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    127. ARA-II Administrative and technical support building (ARA-606) ground floor plan. Indicates use of rooms for classrooms, offices, and lunch room. C.A. Sundberg and Associates 866-area-ALPR-606-A-2. Date: June 1958. Ineel index code no. 070-0606-00-822-102825. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  14. 135. ARAII SLI decontamination and lay down building (ARA614) north, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    135. ARA-II SL-I decontamination and lay down building (ARA-614) north, south, east, and west elevations, floor plan, and detail of doors. F.C. Torkelson Company 842-area/SL-1-614-A-1. Date: September 1960. Ineel index code no. 070-0614-00-851-150061. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  15. 125. ARAI Contaminated waste storage tank (ARA729). Shows location of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    125. ARA-I Contaminated waste storage tank (ARA-729). Shows location of tank on the ARA-I site, section views, connecting pipeline, and other details. Norman Engineering Company 961-area/SF-301-3. Date: January 1959. Ineel index code no. 068-0301-00-613-102711. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. PBF detail of metal pedestrian bridge over exposed control cables, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF detail of metal pedestrian bridge over exposed control cables, which run between Control (PER-619) and Reactor Buildings (PER-620). Camera facing northwest. Southwest corner of PER-620 at upper right of view. Date: May 2004. INEEL negative no. HD-41-6-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  17. PBF Reactor Building (PER620). Camera facing north toward south facade. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera facing north toward south facade. Note west-wing siding on concrete block; high-bay siding of metal. Excavation and forms for signal and cable trenches proceed from building. Photographer: Kirsh. Date August 20, 1968. INEEL negative no. 68-3332 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. Power Burst Facility (PBF), PER620, contextual and oblique view. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    Power Burst Facility (PBF), PER-620, contextual and oblique view. Camera facing northwest. South and east facade. The 1980 west-wing expansion is left of center bay. Concrete structure at right is PER-730. Date: March 2004. INEEL negative no. HD-41-2-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. 71. ARAII. Construction progress at SL1 site near end of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    71. ARA-II. Construction progress at SL-1 site near end of 1957. Buildings from right to left are guard house, support building, reactor building, water tank and pump house. Construction was 23 percent complete. December 20, 1957. Ineel photo no. 57-6224. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  20. A&M. Jet engine test building (TAN609). Exterior. Equipment inside rollup ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Jet engine test building (TAN-609). Exterior. Equipment inside roll-up door is blowdown test facility, part of loft-semiscale program. Note width of central section serving as blast protection for operator on left side. Photographer: Cahoon. Date: July 22, 1965. INEEL negative no. 65-3703 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. 167. ARAIII Plot plan as of 1986. Shows most of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    167. ARA-III Plot plan as of 1986. Shows most of original army buildings in addition to location for buildings ARA-621 and ARA-630, which were built in 1969 after army program had been canceled. Date: March 1986. Ineel index code no. 063-0100-00-220-421241. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  2. 88. ARAIII. "Petrochem" heater is hoisted over south exterior wall ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    88. ARA-III. "Petro-chem" heater is hoisted over south exterior wall of heater pit in GCRE reactor building (ARA-608). Printing on heater says, "Petro-chem iso-flow furnace; American industrial fabrications, inc." Camera facing north. January 7, 1959. Ineel photo no. 529-124. Photographer: Ken Mansfield. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  3. LOFT, TAN650. Camera facing southeast. From left to right: stack ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT, TAN-650. Camera facing southeast. From left to right: stack in distance, pre-amp wing, dome, north side of loft "service building." Note poured concrete wall of pre-amp wing on lower section; pumice block above. Date: May 2004. INEEL negative no. HD-39-19-3 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. PBF Control Building (PER619). Interior of control room. Control console ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Control Building (PER-619). Interior of control room. Control console in center of room. Indicator panels along walls. Window shown in ID-33-F-120 is between control panels at left. Camera facing northwest. Date: May 2004. INEEL negative no. HD-41-7-3 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  5. PBF Reactor Building (PER620). Camera is facing east and down ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera is facing east and down into canal and storage pit for fuel rod assemblies. Stainless steel liner is being applied, temporarily covered with plywood for protection. Photographer: John Capek. Date: August 29, 1969. INEEL negative no. 69-4641 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  6. A&M. Plot plan of administration and A&M areas. Shows relationships ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Plot plan of administration and A&M areas. Shows relationships among administration buildings and to A&M building (TAN-607), railroad turntable. Ralph M. Parsons 902-2&3-ANP-U 3. Date: December 1952. INEEL index code no. 032-0100-00-693-106690 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. 158. ARAIII Reactor building (ARA608) Secondary cooling loop and piping ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    158. ARA-III Reactor building (ARA-608) Secondary cooling loop and piping plan. This drawing was selected as a typical example of piping arrangements within reactor building. Aerojet/general 880-area/GCRE-608-P-16. Date: February 1958. INeel index code no. 063-0608-50-013-102641. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  8. A&M. Outdoor turntable. Aerial view of trackage as of 1954. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Outdoor turntable. Aerial view of trackage as of 1954. Camera faces northeast along line of track heading for the IET. Upper set of east/west tracks head for the hot shop; the other, for the cold shop. Date: November 24, 1954. INEEL negative no. 13203 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. 89. ARAIII. Petrochem oilfired gas heater installed in reactor building ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    89. ARA-III. Petro-chem oil-fired gas heater installed in reactor building (ARA-608). View is at floor level. Shows hand rails around heater pit and top of pit extending upwards through ceiling. January 20, 1959. Ineel photo no. 59-321. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  10. LPT. Low power test (TAN640) interior of cell 102. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Low power test (TAN-640) interior of cell 102. Camera looking west toward rear of cell. Five-ton bridge crane (Moffett, 10,000 lb.) and banks of lights at top of cell. Photographer: Jack L. Anderson. Date: December 19, 1957. INEEL negative no. 57-6200 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. A&M. Hot liquid waste treatment building (TAN616). Camera facing southwest. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616). Camera facing southwest. Oblique view of east and north walls. Note three corrugated pipes at lower left indicating location of underground hot waste storage tanks. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-1-4 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. A&M. Hot liquid waste treatment building (TAN616), south side. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616), south side. Camera facing north. Personnel door at left side of wall. Partial view of outdoor stairway to upper level platform. Note concrete construction. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-1-3 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. LOFT. Containment building (TAN650) detail. Camera facing east. Service building ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment building (TAN-650) detail. Camera facing east. Service building corner is at left of view above personnel access. Round feature at left of dome is tank that will contain borated water. Metal stack at right of view. Date: 1973. INEEL negative no. 73-1085 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. PBF Reactor Building (PER620). Cubicle 10. Camera facing southeast. Loop ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Cubicle 10. Camera facing southeast. Loop pressurizer on right. Other equipment includes loop strained, control valves, loop piping, pressurizer interchanger, and cleanup system cooler. High-density shielding brick walls. Photographer: Kirsh. Date: November 2, 1970. INEEL negative no. 70-4908 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  15. Drop Testing Representative Multi-Canister Overpacks

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Snow, Spencer D.; Morton, Dana K.

    The objective of the work reported herein was to determine the ability of the Multi- Canister Overpack (MCO) canister design to maintain its containment boundary after an accidental drop event. Two test MCO canisters were assembled at Hanford, prepared for testing at the Idaho National Engineering and Environmental Laboratory (INEEL), drop tested at Sandia National Laboratories, and evaluated back at the INEEL. In addition to the actual testing efforts, finite element plastic analysis techniques were used to make both pre-test and post-test predictions of the test MCOs structural deformations. The completed effort has demonstrated that the canister design is capablemore » of maintaining a 50 psig pressure boundary after drop testing. Based on helium leak testing methods, one test MCO was determined to have a leakage rate not greater than 1x10 -5 std cc/sec (prior internal helium presence prevented a more rigorous test) and the remaining test MCO had a measured leakage rate less than 1x10 -7 std cc/sec (i.e., a leaktight containment) after the drop test. The effort has also demonstrated the capability of finite element methods using plastic analysis techniques to accurately predict the structural deformations of canisters subjected to an accidental drop event.« less

  16. U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Oil Bypass Filter Technology Evaluation Fifth Quarterly Report October - December 2003

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Larry Zirker; James Francfort

    2004-02-01

    This Oil Bypass Filter Technology Evaluation quarterly report (October-December 2003) details the ongoing fleet evaluation of an oil bypass filter technology by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy's FreedomCAR & Vehicle Technologies Program. Eight four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the puraDYN Corporation. The bypass filters are reported to have engine oil filtering capability of <1 micron and a built-in additive package to facilitate extended oil-drain intervals. To date, the eight buses have accumulated 324,091 test miles. Thismore » represents an avoidance of 27 oil changes, which equate to 952 quarts (238 gallons) of new oil not conserved and therefore, 952 quarts of waste oil not generated. To validate the extended oil-drain intervals, an oil-analysis regime is used to evaluate the fitness of the oil for continued service by monitoring the presence of necessary additives, undesirable contaminants, and engine-wear metals. The test fleet has been expanded to include six Chevrolet Tahoe sport utility vehicles with gasoline engines.« less

  17. 143. ARAIII Control building (ARA607) Floor plan. Shows control room, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    143. ARA-III Control building (ARA-607) Floor plan. Shows control room, contaminated work area, counting and computer room, health physics room, instrument repair room, offices, and other rooms. Aerojet-general 880-area/GCRE-607-A-1. Date: February 1958. Ineel index code no. 063-0607-00-013-102546. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  18. SPERTI Gate House at control area (PER603). Floor plan, elevations, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Gate House at control area (PER-603). Floor plan, elevations, sections. This Gate House replaced the original gate house, for which drawings are no longer extant. F.C. Torkelson 842-SPERT-603-A-1. Date: February 1962. INEEL index no. 760-0603-00-851-151336 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. A&M. TAN633. Hot cell floor plans, elevations, sections. Hole schedule ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-633. Hot cell floor plans, elevations, sections. Hole schedule (penetrations through concrete). Swing-door details. Ralph M. Parsons 1229-13-ANP/GE-3-633-A-3. Date: December 1956. Approved by INEEL Classification Office for public release. INNEL index code no. 034-0633-00-693-107317 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. LOFT. Interior view of entry to reactor building, TAN650. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Interior view of entry to reactor building, TAN-650. Camera is inside entry (TAN-624) and facing north. At far end of domed chamber are penetrations in wall for electrical and other connections. Reactor and other equipment has been removed. Date: March 2004. INEEL negative no. HD-39-5-1 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. PBF Reactor Building (PER620). Construction view shows native lava rock ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Construction view shows native lava rock surrounding basement excavation and general complexity of planning required to build the PBF. A three-inch low-pressure air line protrudes from wall just below left center. Date: February 21, 1967. Photographer: Larry Page. INEEL negative no. 67-1125 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  2. 124. ARAI Reservoir (ARA727), later named water storage tank. Shows ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    124. ARA-I Reservoir (ARA-727), later named water storage tank. Shows plan of 100,000-gallon tank, elevation, image of "danger radiation hazard" sign, and other details. Norman Engineering Company 961-area/SF-727-S-1. Date: January 1959. Ineel index code no. 068-0727-60-613-102779. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  3. 131. ARAII Administration building (ARA613) floor plans for first and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    131. ARA-II Administration building (ARA-613) floor plans for first and second floors. Includes roof plan. Shows use of rooms as offices, laboratory, conference room. F.C. Torkelson Company 842-area/SL-1-613-A-1. Date: October 1958. Ineel index code no. 070-0613-00-851-150718. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. 115. ARAI Details of hot cell section of building ARA626. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    115. ARA-I Details of hot cell section of building ARA-626. Shows location of high density concrete, viewing windows, filters, monorail crane, bridge crane, and other details. Norman Engineering Company 961-area/SF-626-MS-1. Date: January 1959. Ineel index code no. 068-0626-40-613-102737. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  5. 133. ARAII SL1 burial ground. Shows gravel path from ARAII ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    133. ARA-II SL-1 burial ground. Shows gravel path from ARA-II compound to the burial ground, detail of security fence and entry gate, and sign "Danger radiation hazard." F. C. Torkelson Company 842-area-101-1. Date: October 1961. Ineel index code no. 059-0101-00-851-150723. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  6. PBF Reactor Building (PER620). Camera faces south toward verticallift door, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera faces south toward vertical-lift door, which is closed. Note crane and its trolley positioned near door; its rails along side walls. Reactor vessel and lifting beams are positioned above reactor pit. Photographer: John Capek. Date: January 9, 1970. INEEL negative no. 70-132 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  7. PBF Cooling Tower under construction. Cold water basin is five ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower under construction. Cold water basin is five feet deep. Foundation and basin walls are reinforced concrete. Camera facing west. Pipe openings through wall in front are outlets for return flow of cool water to reactor building. Photographer: John Capek. Date: September 4, 1968. INEEL negative no. 68-3473 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. PBF Cooling Tower. Hot deck of Cooling Tower with fan ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower. Hot deck of Cooling Tower with fan motors in place. Fan's propeller blades (not in view) rotate within lower portion of vents. Inlet pipe is a left of view. Contractor's construction buildings in view to right. Photographer: Larry Page. Date: June 30, 1969. INEEL negative no. 69-3781 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  9. LPT. EBOR (TAN646) interior, installing reactor in STF pool ("vault"). ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. EBOR (TAN-646) interior, installing reactor in STF pool ("vault"). Pressure vessel shows core barrel and outlet nozzle (next to man below) to inner duct weld, which is prepared and in position for stress relieving. Camera facing southeast. Photographer: Comiskey. Date: January 20, 1965. INEEL negative no. 65-239 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  10. 16. ARAII Administration building ARA613. South (front) and east sides. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    16. ARA-II Administration building ARA-613. South (front) and east sides. Camera facing northwest. Sign at left corner of building says, "Fuels and materials division, materials joining research and development laboratory." Part of south wall already has been demolished. Sign on roof railing says, "Danger--Abestos." Ineel photo no. 2-3. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  11. SPERTI. Detail view of Reactor Pit Building (PER605) and Instrument ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I. Detail view of Reactor Pit Building (PER-605) and Instrument Cell (PER-606). Earth shielding covers side of Cell Building next to reactor. Instrumentation required protection from radiation emitted during reactor operation. Photographer: R.G. Larsen. Date: May 20, 1955. INEEL negative no. 55-1290 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. LPT. Shield test facility (TAN646). Floor plan for water treatment ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility (TAN-646). Floor plan for water treatment room on west facade, tank and filter locations in basement along service tunnel and in coupling station. Ralph M. Parsons 1229-17 ANP/GE-6-646-P-2. April 1957. INEEL Index code no. 037-0645/0646-51-693-107387 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  13. LOFT complex in 1975 awaits renewed mission. Aerial view. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT complex in 1975 awaits renewed mission. Aerial view. Camera facing southwesterly. Left to right: stack, entry building (TAN-624), door shroud, duct shroud and filter hatches, dome (painted white), pre-amp building, equipment and piping building, shielded control room (TAN-630), airplane hangar (TAN-629). Date: 1975. INEEL negative no. 75-3690 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. LOFT. Containment and service building (TAN650) ground floor plan. Penetrations ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650) ground floor plan. Penetrations in dome wall. Shielded personnel maze at airlock door. Reactor chamber floor hatches and holddowns. Rails in concrete floor. Kaiser engineers 6413-11-STEP/LOFT-650-A-2. Date: October 1964. INEEL index code no. 036-650-00-486-122214 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. LOFT. Containment and service building (TAN650). Room number and function ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Room number and function of each room. Identifies type of floor, paint, walls, ceiling, doors. This is sheet 1 of a 2-page drawing. Kaiser engineers 6413-11-STEP/LOFT-650-XX. Date: October 1965. INEEL index code no. 036-650-00-486-122228 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. A&M. Radioactive parts security storage warehouses: TAN648 on left, and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Radioactive parts security storage warehouses: TAN-648 on left, and dolly storage building, TAN-647, on right. Camera facing south. This was the front entry for the warehouse and the rear of the dolly storage building. Date: August 6, 2003. INEEL negative no. HD-36-2-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. Snaptran2 experiment mounted on dolly being hauled by shielded locomotive ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    Snaptran-2 experiment mounted on dolly being hauled by shielded locomotive from IET towards A&M turntable. Note leads from experiment gathered at coupling bar in lower right of view. Another dolly in view at left. Camera facing southeast. Photographer: Page Comiskey. Date: August 25, 1965. INEEL negative no. 65-4503 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  18. A&M. A&M building (TAN607). Camera facing east. From left to ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. A&M building (TAN-607). Camera facing east. From left to right, pool section, hot shop, cold shop, and machine shop. Biparting doors to hot shop are in open position behind shroud. Four rail tracks lead to hot shop and cold shop. Date: August 20, 1954. INEEL negative no. 11706 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. LPT. Shield test facility assembly and test building (TAN646). East ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Shield test facility assembly and test building (TAN-646). East facade of ebor helium wing addition. Camera facing west. Note asbestos-cement siding on stair enclosure and upper-level. Concrete siding at lower level. Metal stack. Monorail protrudes from upper level of south wall at left of view. INEEL negative no. HD-40-7-4 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. IET. Aerial view during construction, facing southwest. Control building (TAN620) ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Aerial view during construction, facing southwest. Control building (TAN-620) in center. Retaining wall in place on west side. Tank building (TAN-627) and fuel transfer pump building (TAN-625) north of control building. Shielded roadway not yet built. Foundation of stack at right edge of view. Date: November 24, 1954. INEEL negative no. 13198 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  1. 1. CONTEXTUAL VIEW OF WASTE CALCINING FACILITY. CAMERA FACING NORTHEAST. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    1. CONTEXTUAL VIEW OF WASTE CALCINING FACILITY. CAMERA FACING NORTHEAST. ON RIGHT OF VIEW IS PART OF EARTH/GRAVEL SHIELDING FOR BIN SET. AERIAL STRUCTURE MOUNTED ON POLES IS PNEUMATIC TRANSFER SYSTEM FOR DELIVERY OF SAMPLES BEING SENT FROM NEW WASTE CALCINING FACILITY TO THE CPP REMOTE ANALYTICAL LABORATORY. INEEL PROOF NUMBER HD-17-1. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  2. A&M. TAN633. Sections show view of hot cell caskentry doors, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-633. Sections show view of hot cell cask-entry doors, manipulators in each cell, drainage trenches, door and room details. Ralph M. Parsons 1229-13-ANP/GE-3-633-A-2. Date: December 1956. Approved by INEEL Classification Office for public release. INNEL index code no. 034-0633-00-693-107316 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. 134. ARAII SL1 decontamination and lay down building (ARA614) erected ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    134. ARA-II SL-1 decontamination and lay down building (ARA-614) erected after accidental explosion of SL-1 reactor. Shows vicinity map, index of related drawings, plot plan and other detail. F.C. Torkelson Company 842-area/SL-1-101-U-2. Date: September 1962. Ineel index code no. 070-0101-65-851-150713. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  4. 122. ARAI Pump House (ARA629). Drawing shows north, south, east, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    122. ARA-I Pump House (ARA-629). Drawing shows north, south, east, and west elevations, floor plan, foundation plan, and other details. Note small enclosure at southwest corner of building to contain chlorination equipment. Norman Engineering Company 961-area/SF-629-A-1. Date: January 1959. Ineel index code no. 068-0629-00-613-102774. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  5. 136. ARRII Plot plan as it appeared in 1980, when ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    136. ARR-II Plot plan as it appeared in 1980, when interior modifications were being prepared to remodel electrical apparatus in ARA-602 in connection with use as a research and development joining laboratory. EG&G, Idaho, Inc. 1570-ARA-II-100-1. Date: April 1980. Ineel index code no. 070-0199-00-220-159749. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  6. 130. ARAII Administration building (ARA613) vicinity map and plot plan ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    130. ARA-II Administration building (ARA-613) vicinity map and plot plan showing relationship to other existing buildings on site and to ARA-602, to which this building was attached. F.C. Torkelson Comapny 842-area/SL-1-101-U-1. Date: October 1959. Ineel index code no. 070-0101-65-851-150053. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  7. SPERTI contextual view of instrument cell building, PER606. South facade. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I contextual view of instrument cell building, PER-606. South facade. Camera facing northwest. PBF Cooling Tower in view at right. High bay of PBF Reactor Building, PER-602, is further to right. PBF-625 at left edge of view. Date: August 2003. INEEL negative no. HD-35-3-4 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. PBF Reactor Building (PER620). Camera is in cab of electricpowered ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera is in cab of electric-powered rail crane and facing east. Reactor pit and storage canal have been shaped. Floors for wings on east and west side are above and below reactor in view. Photographer: Larry Page. Date: August 23, 1967. INEEL negative no. 67-4403 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  9. SPERTI Terminal Building (PER604) is under construction in foreground, with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Terminal Building (PER-604) is under construction in foreground, with vertical metal siding partially affixed to gable end of building. Utility lines are laid in shallow trench to Reactor Pit and Instrument Cell Buildings also under construction in distance. Photographer: R.G. Larsen. Date: April 22, 1955. INEEL negative no. 55-1001 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. IET. Snaptran. Flying a kite in the service of science. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Snaptran. Flying a kite in the service of science. Doug Wenzel and Jon Hurd obtain weather data on east side of IET as part of Snaptran experiment. tank building (TAN-627) and movable building (TAN-624) at left. Stack and ANP duct at right. Photographer: Farmer. Date: September 27, 1965. INEEL negative no. 65-4986 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. IET. Aerial view of snaptran destructive experiment in 1964. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Aerial view of snaptran destructive experiment in 1964. Camera facing north. Test cell building (TAN-624) is positioned away from coupling station. Weather tower in right foreground. Divided duct just beyond coupling station. Air intake structure on south side of shielded control room. Experiment is on dolly at coupling station. Date: 1964. INEEL negative no. 64-1736 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. 113. ARAI Hot cell (ARA626) Building wall sections and details ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    113. ARA-I Hot cell (ARA-626) Building wall sections and details of radio chemistry lab. Shows high-bay roof over hot cells and isolation rooms below grade storage pit for fuel elements. Norman Engineering Company: 961-area/SF-626-A-4. Date: January 1959. Ineel index code no. 068-0626-00-613-102724. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  13. LOFT. Construction view of tunnel during 1957 to compare with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Construction view of tunnel during 1957 to compare with HAER photo ID-33-E-358 above. Tunnel sections were pre-cast, then joined together. Photographer described this as :Personnel and service tunnel running east-west in test building of the FET." Date: December 19, 1957. Photographer: Jack L. Anderson. INEEL negative no. 57-6206 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. A&M. TAN633. Utilities plan and profiles. Layout of TAN633 in ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-633. Utilities plan and profiles. Layout of TAN-633 in relation to neighboring buildings: actuator building, pool building, water filter building, liquid waste treatment plant, and buried storage tanks. Ralph M. Parsons 1229-13-ANP/GE-3-301-U-1. Date: December 1956. INEEL index code no. 034-0301-00-693-107311 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. 120. ARAI Expansion of ARA627 shop and maintenance building for ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    120. ARA-I Expansion of ARA-627 shop and maintenance building for new use as materials and metallurgy laboratory. Shows ground floor plan addition of gas analyzer room, fatigue testing room, microscope room, and offices. Idaho Nuclear Corporation 1230-ARA-627-A-5. Date: June 1970. Ineel index code no. 068-0627-00-400-154062. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  16. LOFT complex, aerial view taken on same on same day ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT complex, aerial view taken on same on same day as HAER photo ID-33-E-376. Camera facing south. Note curve of rail track toward hot shop (TAN-607). Earth shielding on control building (TAN-630) is partly removed, showing edge of concrete structure. Great southern butte on horizon. Date: 1975. INEEL negative no. 75-3693 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. Runoff and erosion response of simulated waste burial covers in a semi-arid environment

    USGS Publications Warehouse

    Bent, G.C.; Goff, B.F.; Rightmire, K.G.; Sidle, R.C.

    1999-01-01

    Control of runoff (reducing infiltration) and erosion at shallow land burials is necessary in order to assure environmentally safe disposal of low-level radioactive-waste and other waste products. This study evaluated the runoff and erosion response of two perennial grass species on simulated waste burial covers at Idaho National Engineering and Environmental Laboratory (INEEL). Rainfall simulations were applied to three plots covered by crested wheatgrass [Agropyron desertorum (Fischer ex Link) Shultes], three plots covered by streambank wheatgrass [Elymus lanceolatus (Scribner and Smith) Gould spp. lanceolatus], and one bare plot. Average total runoff for rainfall simulations in 1987, 1989, and 1990 was 42 percent greater on streambank wheatgrass plots than on crested wheatgrass plots. Average total soil loss for rainfall simulations in 1987 and 1990 was 105 percent greater on streambank wheatgrass plots than on crested wheatgrass plots. Total runoff and soil loss from natural rainfall and snowmelt events during 1987 were 25 and 105 percent greater, respectively, on streambank wheatgrass plots than on crested wheatgrass plots. Thus, crested wheatgrass appears to be better suited in revegetation of waste burial covers at INEEL than streambank wheatgrass due to its much lower erosion rate and only slightly higher infiltration rate (lower runoff rate).

  18. Determination of variables in the prediction of strontium distribution coefficients for selected sediments

    USGS Publications Warehouse

    Pace, M.N.; Rosentreter, J.J.; Bartholomay, R.C.

    2001-01-01

    Idaho State University and the US Geological Survey, in cooperation with the US Department of Energy, conducted a study to determine and evaluate strontium distribution coefficients (Kds) of subsurface materials at the Idaho National Engineering and Environmental Laboratory (INEEL). The Kds were determined to aid in assessing the variability of strontium Kds and their effects on chemical transport of strontium-90 in the Snake River Plain aquifer system. Data from batch experiments done to determine strontium Kds of five sediment-infill samples and six standard reference material samples were analyzed by using multiple linear regression analysis and the stepwise variable-selection method in the statistical program, Statistical Product and Service Solutions, to derive an equation of variables that can be used to predict strontium Kds of sediment-infill samples. The sediment-infill samples were from basalt vesicles and fractures from a selected core at the INEEL; strontium Kds ranged from ???201 to 356 ml g-1. The standard material samples consisted of clay minerals and calcite. The statistical analyses of the batch-experiment results showed that the amount of strontium in the initial solution, the amount of manganese oxide in the sample material, and the amount of potassium in the initial solution are the most important variables in predicting strontium Kds of sediment-infill samples.

  19. 40. ARAIII Prototype assembly and evaluation building ARA630. East end ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    40. ARA-III Prototype assembly and evaluation building ARA-630. East end and south side of building. Camera facing west. Roof railing is part of demolition preparations. Building beyond ARA-622 is ARA-621. In left of view is reactor building. ARA-607 is low-roofed portion, while high-bay portion is ARA-608. Ineel photo no. 3-27. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  20. 46. ARAI. Aerial view of ARAI buildings as they looked ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    46. ARA-I. Aerial view of ARA-I buildings as they looked in 1981. From left to right, buildings are tank (ARA-727), contaminated waste storage tank (ARA-629), trailer, hot cell building (ARA-626), fuel oil storage tank (ARA-728), guard house (ARA-628), shop and maintenance building (ARA-627), and two trailers. Ineel photo no. 81-297. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  1. 7. WASTE CALCINING FACILITY, LOOKING AT NORTH END OF BUILDING. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    7. WASTE CALCINING FACILITY, LOOKING AT NORTH END OF BUILDING. CAMERA FACING SOUTH. TENT-ROOFED COVER IN RIGHT OF VIEW IS A TEMPORARY WEATHER-PROOFING SHELTER OVER THE BLOWER PIT IN CONNECTION WITH DEMOLITION PROCEDURES. SMALL BUILDING CPP-667 IN CENTER OF VIEW WAS USED FOR SUPPLEMENTARY OFFICE SPACE BY HEALTH PHYSICISTS AND OTHERS. INEEL PROOF SHEET NOT NUMBERED. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  2. A&M. TAN607. Detail of fuel storage pool under construction. Camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Detail of fuel storage pool under construction. Camera is on berm and facing northwest. Note depth of excavation. Formwork underway for floor and concrete walls of pool; wall between pool and vestibule. At center left of view, foundation for liquid waste treatment plant is poured. Date: August 25, 1953. INEEL negative no. 8541 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. SPERTI Reactor Pit Building (PER605) under construction. Poured concrete foundation ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Reactor Pit Building (PER-605) under construction. Poured concrete foundation will enclosure a "Pit" into which the reactor vessel will be placed. Steel framework has been erected. To left of view is instrument cell (PER-606), constructed of concrete block. Photographer: R.G. Larsen. Date: April 22, 1955. INEEL negative no. 55-1000 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  4. PBF Reactor Building (PER620). Camera faces south along west wall. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera faces south along west wall. Gap between native lava rock and concrete basement walls is being backfilled and compacted. Wire mesh protects workers from falling rock. Note penetrations for piping that will carry secondary coolant water to Cooling Tower. Photographer: Holmes. Date: June 15, 1967. INEEL negative no. 67-3665 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  5. LOFT complex, camera facing west. Mobile entry (TAN624) is position ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT complex, camera facing west. Mobile entry (TAN-624) is position next to containment building (TAN-650). Shielded roadway entrance in view just below and to right of stack. Borated water tank has been covered with weather shelter and is no longer visible. ANP hangar (TAN-629) in view beyond LOFT. Date: 1974. INEEL negative no. 74-4191 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  6. PBF Cooling Tower and it Auxiliary Building (PER624) to left ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower and it Auxiliary Building (PER-624) to left of tower. Camera facing west and the east louvered face of the tower. Details include secondary coolant water riser piping and flow control valves (butterfly valves) to distribute water evenly to all sections of tower. Photographer: Holmes. Date: May, 20, 1970. INEEL negative no. 70-2322 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  7. PBF Reactor Building (PER620). After lowering reactor vessel onto blocks, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). After lowering reactor vessel onto blocks, it is rolled on logs into PBF. Metal framework under vessel is handling device. Various penetrations in reactor bottom were for instrumentation, poison injection, drains. Large one, below center "manhole" was for primary coolant. Photographer: Larry Page. Date: February 13, 1970. INEEL negative no. 70-736 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  8. Monte Carlo treatment planning for molecular targeted radiotherapy within the MINERVA system

    NASA Astrophysics Data System (ADS)

    Lehmann, Joerg; Hartmann Siantar, Christine; Wessol, Daniel E.; Wemple, Charles A.; Nigg, David; Cogliati, Josh; Daly, Tom; Descalle, Marie-Anne; Flickinger, Terry; Pletcher, David; DeNardo, Gerald

    2005-03-01

    The aim of this project is to extend accurate and patient-specific treatment planning to new treatment modalities, such as molecular targeted radiation therapy, incorporating previously crafted and proven Monte Carlo and deterministic computation methods. A flexible software environment is being created that allows planning radiation treatment for these new modalities and combining different forms of radiation treatment with consideration of biological effects. The system uses common input interfaces, medical image sets for definition of patient geometry and dose reporting protocols. Previously, the Idaho National Engineering and Environmental Laboratory (INEEL), Montana State University (MSU) and Lawrence Livermore National Laboratory (LLNL) had accrued experience in the development and application of Monte Carlo based, three-dimensional, computational dosimetry and treatment planning tools for radiotherapy in several specialized areas. In particular, INEEL and MSU have developed computational dosimetry systems for neutron radiotherapy and neutron capture therapy, while LLNL has developed the PEREGRINE computational system for external beam photon-electron therapy. Building on that experience, the INEEL and MSU are developing the MINERVA (modality inclusive environment for radiotherapeutic variable analysis) software system as a general framework for computational dosimetry and treatment planning for a variety of emerging forms of radiotherapy. In collaboration with this development, LLNL has extended its PEREGRINE code to accommodate internal sources for molecular targeted radiotherapy (MTR), and has interfaced it with the plugin architecture of MINERVA. Results from the extended PEREGRINE code have been compared to published data from other codes, and found to be in general agreement (EGS4—2%, MCNP—10%) (Descalle et al 2003 Cancer Biother. Radiopharm. 18 71-9). The code is currently being benchmarked against experimental data. The interpatient variability of the drug pharmacokinetics in MTR can only be properly accounted for by image-based, patient-specific treatment planning, as has been common in external beam radiation therapy for many years. MINERVA offers 3D Monte Carlo-based MTR treatment planning as its first integrated operational capability. The new MINERVA system will ultimately incorporate capabilities for a comprehensive list of radiation therapies. In progress are modules for external beam photon-electron therapy and boron neutron capture therapy (BNCT). Brachytherapy and proton therapy are planned. Through the open application programming interface (API), other groups can add their own modules and share them with the community.

  9. 91. ARAIII. GCRE reactor building (ARA608) at 48 percent completion. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    91. ARA-III. GCRE reactor building (ARA-608) at 48 percent completion. Camera faces west end of building; shows roll-up door. High bay section on right view. Petro-chem heater stack extends above roof of low-bay section on left. Excavation for 13, 8 kv electrical conduit in foreground. January 20, 1959. Ineel photo no. 59-322. Photographer: Jack L. Anderson. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  10. LPT. Aerial of low power test facility (TAN640 and 641) ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Aerial of low power test facility (TAN-640 and -641) and shield test facility (TAN-645 and -646). Camera facing south. Low power reactor cells at left, then one-story control building; diagonal fence; shield test control building, then (high-bay) pool room. In foreground are electrical pad, water tanks and guard house. Photographer: Lowin. Date: February 24, 1965. INEEL negative no. 65-987 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. LOFT. Reactor support apparatus inside containment building (TAN650). Camera is ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Reactor support apparatus inside containment building (TAN-650). Camera is on crane rail level and facing northerly. View shows top two banks of round conduit openings on wall for electrical and other connections to control room. Ladders and platforms provide access to reactor instrumentation. Note hatch in floor and drain at edge of floor near wall. Date: 1974. INEEL negative no. 74-219 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  12. PBF Cooling Tower. View from highbay roof of Reactor Building ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower. View from high-bay roof of Reactor Building (PER-620). Camera faces northwest. East louvered face has been installed. Inlet pipes protrude from fan deck. Two redwood vents under construction at top. Note piping, control, and power lines at sub-grade level in trench leading to Reactor Building. Photographer: Kirsh. Date: June 6, 1969. INEEL negative no. 69-3466 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  13. PBF Reactor Building (PER620). Camera facing southeast in second basement. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera facing southeast in second basement. Round form and reinforcing steel surround reactor vessel pit, which will be heavily shielded by several feet of concrete. Block-out is for door to sub-pile room. Rectangular form and rebar beyond pit is for canal wall. Photographer: John Capek. Date: March 10, 1967. INEEL negative no. 67-1643 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  14. LPT. Aerial of low power test (TAN640 and 641) and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. Aerial of low power test (TAN-640 and -641) and shield test (TAN-645 and -646) facilities. Camera facing north west. Low power test facility at right. Shield test facility at left. Flight engine test area in background at center left of view. Administrative and A&M areas at right. Photographer: Lowin. Date: February 24, 1965. INEEL negative no. 65-991 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  15. LOFT. Containment and service building (TAN650). Section through north/south axis. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Section through north/south axis. Shows basement and four additional levels of pre-amp tower, shielded roadway, chambers below reactor floor, railroad door, sumps, shielding. Section C shows basement sumps and chambers below reactor floor. Kaiser engineers 6413-11-STEP/LOFT-650-A-5. Date: October 1964. INEEL index code no. 036-650-00-486-122217 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  16. LOFT. Containment and service building (TAN650). South elevation, details, section. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). South elevation, details, section. Shows part of duct enclosure, railroad door opening, roof ventilators, shielded personnel entrance, and change room. Section F shows view from west looking toward shielding around airlock door on main floor. Kaiser engineers 6413-11-STEP/LOFT-650-A-9. Date: October 1964. INEEL index code no. 036-650-00-486-122221 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. Oil Bypass Filter Technology Evaluation, Fourth Quarterly Report, July--September 2003

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    James E. Francfort; Larry Zirker

    2003-11-01

    This fourth Oil Bypass Filter Technology Evaluation report details the ongoing fleet evaluation of an oil bypass filter technology by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy’s FreedomCAR & Vehicle Technologies Program. Eight four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the puraDYN Corporation. The bypass filters are reported to have engine oil filtering capability of <1 micron and a built-in additive package to facilitate extended oil-drain intervals. To date, the eight buses have accumulated 259,398 test miles. This represents anmore » avoidance of 21 oil changes, which equates to 740 quarts (185 gallons) of oil not used or disposed of. To validate the extended oil-drain intervals, an oil-analysis regime evaluates the fitness of the oil for continued service by monitoring the presence of necessary additives, undesirable contaminants, and engine-wear metals. For bus 73450, higher values of iron have been reported, but the wear rate ratio (parts per million of iron per thousand miles driven) has remained consistent. In anticipation of also evaluating oil bypass systems on six Chevrolet Tahoe sport utility vehicles, the oil is being sampled on each of the Tahoes to develop a characterization history or baseline for each engine.« less

  18. Applying lessons learned to enhance human performance and reduce human error for ISS operations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nelson, W.R.

    1999-01-01

    A major component of reliability, safety, and mission success for space missions is ensuring that the humans involved (flight crew, ground crew, mission control, etc.) perform their tasks and functions as required. This includes compliance with training and procedures during normal conditions, and successful compensation when malfunctions or unexpected conditions occur. A very significant issue that affects human performance in space flight is human error. Human errors can invalidate carefully designed equipment and procedures. If certain errors combine with equipment failures or design flaws, mission failure or loss of life can occur. The control of human error during operation ofmore » the International Space Station (ISS) will be critical to the overall success of the program. As experience from Mir operations has shown, human performance plays a vital role in the success or failure of long duration space missions. The Department of Energy{close_quote}s Idaho National Engineering and Environmental Laboratory (INEEL) is developing a systematic approach to enhance human performance and reduce human errors for ISS operations. This approach is based on the systematic identification and evaluation of lessons learned from past space missions such as Mir to enhance the design and operation of ISS. This paper will describe previous INEEL research on human error sponsored by NASA and how it can be applied to enhance human reliability for ISS. {copyright} {ital 1999 American Institute of Physics.}« less

  19. Applying lessons learned to enhance human performance and reduce human error for ISS operations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nelson, W.R.

    1998-09-01

    A major component of reliability, safety, and mission success for space missions is ensuring that the humans involved (flight crew, ground crew, mission control, etc.) perform their tasks and functions as required. This includes compliance with training and procedures during normal conditions, and successful compensation when malfunctions or unexpected conditions occur. A very significant issue that affects human performance in space flight is human error. Human errors can invalidate carefully designed equipment and procedures. If certain errors combine with equipment failures or design flaws, mission failure or loss of life can occur. The control of human error during operation ofmore » the International Space Station (ISS) will be critical to the overall success of the program. As experience from Mir operations has shown, human performance plays a vital role in the success or failure of long duration space missions. The Department of Energy`s Idaho National Engineering and Environmental Laboratory (INEEL) is developed a systematic approach to enhance human performance and reduce human errors for ISS operations. This approach is based on the systematic identification and evaluation of lessons learned from past space missions such as Mir to enhance the design and operation of ISS. This paper describes previous INEEL research on human error sponsored by NASA and how it can be applied to enhance human reliability for ISS.« less

  20. A hybrid liquid-phase precipitation (LPP) process in conjunction with membrane distillation (MD) for the treatment of the INEEL sodium-bearing liquid waste.

    PubMed

    Bader, M S H

    2005-05-20

    A novel hybrid system combining liquid-phase precipitation (LPP) and membrane distillation (MD) is integrated for the treatment of the INEEL sodium-bearing liquid waste. The integrated system provides a "full separation" approach that consists of three main processing stages. The first stage is focused on the separation and recovery of nitric acid from the bulk of the waste stream using vacuum membrane distillation (VMD). In the second stage, polyvalent cations (mainly TRU elements and their fission products except cesium along with aluminum and other toxic metals) are separated from the bulk of monovalent anions and cations (dominantly sodium nitrate) by a front-end LPP. In the third stage, MD is used first to concentrate sodium nitrate to near saturation followed by a rear-end LPP to precipitate and separate sodium nitrate along with the remaining minor species from the bulk of the aqueous phase. The LPP-MD hybrid system uses a small amount of an additive and energy to carry out the treatment, addresses multiple critical species, extracts an economic value from some of waste species, generates minimal waste with suitable disposal paths, and offers rapid deployment. As such, the LPP-MD could be a valuable tool for multiple needs across the DOE complex where no effective or economic alternatives are available.

  1. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems; NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pavel Hejzlar, Peter Yarsky, Mike Driscoll, Dan Wachs, Kevan Weaver, Ken Czerwinski, Mike Pope, James Parry, Theron D. Marshall, Cliff B. Davis, Dustin Crawford, Thomas Hartmann, Pradip Saha; Hejzlar, Pavel; Yarsky, Peter

    2005-01-31

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings.

  2. PBF Reactor Building (PER620). In subpile room, camera faces southeast ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). In sub-pile room, camera faces southeast and looks up toward bottom of reactor vessel. Upper assembly in center of view is in-pile tube as it connects to vessel. Lower lateral constraints and rotating control cable are in position. Other connections have been bolted together. Note light bulbs for scale. Photographer: John Capek. Date: August 21, 1970. INEEL negative no. 70-3494 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  3. PBF Reactor Building (PER620) basement, inside cubicle 13. Lead bricks ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620) basement, inside cubicle 13. Lead bricks shield the fission product detection system (FPDS). The system detected fission products in pressure loop from in-pile tube. shielding was to prevent other radiation in cubicle from interfering. Assembly of bricks in foreground will slide back to enclose and shield equipment in the three chambers. Date: 1982. INEEL negative no. 82-6376 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  4. LOFT. Mobile test building (TAN624) is recycled from ANP program ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Mobile test building (TAN-624) is recycled from ANP program for placement before LOFT containment building door. It has not yet been connected to containment building. Note borated water tank at right of dome. Narrow, vertical structure at right of door is shroud is shroud for air exhaust duct. Filter vaults lie between duct shroud and stack. Camera facing westerly. Date: 1974. INEEL negative no. 74-1072 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  5. PBF Reactor Building (PER620). Camera on main floor faces south ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Camera on main floor faces south (open) doorway. In foreground is canal gate, lined with stainless steel and painted with protective coatings. Reactor pit is round with protective coatings. Reactor put is round form discernible beyond. Lifting beams and rigging are in place for a load test before reactor vessel arrives. Photographer: John Capek. Date: January 26, 1970. INEEL negative no. 70-347 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  6. LOFT. Containment building (TAN650) with fourrail tracks in place. Stack ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment building (TAN-650) with four-rail tracks in place. Stack has been erected. Curved shroud over doorway and to the right is weather protection for railroad door seen in HAER photo ID-33-E-367. Motor-operated door rolls on wheels to open and close. Service portions of containment building can be seen at rear of dome on left and right. Camera facing north. Date: 1973. INEEL negative no. 73-1600 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  7. A&M. TAN607. Interior view of operating gallery in hot shop. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Interior view of operating gallery in hot shop. Shielded viewing windows are along right side of corridor. Cabinet on wheels at left of corridor is operating console for hot shop manipulators. When in use, it is stationed at window station and connected to appropriate control cables. note reserve bottles of zinc bromide above each station. Date: January 3, 1955. INEEL negative no. 55-0072 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  8. LOFT. Containment and service building (TAN650). Section through east/west axis ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Section through east/west axis of building as viewed from the north. Shows steel ladder to top of dome, gable roof of borated water tank enclosure, pumice block siding of pre-amp tower, metal siding of duct enclosure. Kaiser engineers 6413-11-STEP/LOFT-650-A-6. Date: October 1964. INEEL index code no. 036-650-00-486-122218 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  9. PBF contextual view shows relationship between PBF Control Building (PER619, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF contextual view shows relationship between PBF Control Building (PER-619, in foreground at right) and SPERT-I Control Building (PER-601). Walkway with railing connects to waste reduction operations support building (PER-632), built in 1981. Note paneled stucco siding applied to PER-619 after 1980. Original concrete block is exposed at corner. Date: July 2004. INEEL negative no. HD-41-9-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. LOFT. Containment and service building (TAN650). Section through east/west axis ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT. Containment and service building (TAN-650). Section through east/west axis of building as viewed from the south. Shows basement and grade levels of containment building, connection to control room on west side, air filter vaults, and duct enclosure for air exhaust system. Kaiser engineers 6413-11-STEP/LOFT-650-A-4. Date: October 1964. INEEL index code no. 036-650-00-486-122216 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. SPERTI Reactor Pit Building (PER605). Earth shielding protect adjacent Instrument ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Reactor Pit Building (PER-605). Earth shielding protect adjacent Instrument Cell (PER-606). Security fencing surrounds complex, to which gate entry is provided next to Guard House (PER-607). Note gravel road leading to control area. Earth-covered conduit leads from instrument cell to terminal building out of view. Photographer: R.G. Larsen. Date: June 22, 1955. INEEL negative no. 55-1701 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. SPERTI Instrument Cell Building (PER606) elevation; plan of Guard House ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I Instrument Cell Building (PER-606) elevation; plan of Guard House (PER-607); elevations for Pit Building (PER-605) southwest, southeast, and northeast sides. Earthen shield is mounded between back wall of Instrument Cell Building and the southwest elevation of Pit Building. Detail of filtered louver in door of Instrument Cell Building. Idaho Operations Office PER-605-IDO-3. INEEL index no. 761-0605-00-396-109183 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  13. A&M. Hot liquid waste treatment building (TAN616). Contextual view, facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. Hot liquid waste treatment building (TAN-616). Contextual view, facing south. Wall of hot shop (TAN-607) with high bay at left of view. Lower-roofed building at left edge of view is TAN- 633, hot cell annex. Complex at center of view is TAN-616. Tall metal building with gable roof is TAN-615. Photographer: Ron Paarmann. Date: September 22, 1997. INEEL negative no. HD-20-2-2 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. Oil Bypass Filter Technology Evaluation - Third Quarterly Report, April--June 2003

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Laurence R. Zirker; James E. Francfort

    2003-08-01

    This Third Quarterly report details the ongoing fleet evaluation of an oil bypass filter technology by the Idaho National Engineering and Environmental Laboratory (INEEL) for the U.S. Department of Energy’s FreedomCAR & Vehicle Technologies Program. Eight full-size, four-cycle diesel-engine buses used to transport INEEL employees on various routes have been equipped with oil bypass filter systems from the PuraDYN Corporation. The reported engine lubricating oil-filtering capability (down to 0.1 microns) and additive package of the bypass filter system is intended to extend oil-drain intervals. To validate the extended oil-drain intervals, an oil-analysis regime monitors the presence of necessary additives inmore » the oil, detects undesirable contaminants and engine wear metals, and evaluates the fitness of the oil for continued service. The eight buses have accumulated 185,000 miles to date without any oil changes. The preliminary economic analysis suggests that the per bus payback point for the oil bypass filter technology should be between 108,000 miles when 74 gallons of oil use is avoided and 168,000 miles when 118 gallons of oil use is avoided. As discussed in the report, the variation in the payback point is dependant on the assumed cost of oil. In anticipation of also evaluating oil bypass systems on six Chevrolet Tahoe sport utility vehicles, the oil is being sampled on the six Tahoes to develop an oil characterization history for each engine.« less

  15. Paleomagnetism of Basaltic Lava Flows in Coreholes ICPP 213, ICPP-214, ICPP-215, and USGS 128 Near the Vadose Zone Research Park, Idaho Nuclear Technology and Engineering Center, Idaho National Engineering and Environmental Laboratory, Idaho

    USGS Publications Warehouse

    Champion, Duane E.; Herman, Theodore C.

    2003-01-01

    A paleomagnetic study was conducted on basalt from 41 lava flows represented in about 2,300 ft of core from coreholes ICPP-213, ICPP-214, ICPP-215, and USGS 128. These wells are in the area of the Idaho Nuclear Technology and Engineering Center (INTEC) Vadose Zone Research Park within the Idaho National Engineering and Environmental Laboratory (INEEL). Paleomagnetic measurements were made on 508 samples from the four coreholes, which are compared to each other, and to surface outcrop paleomagnetic data. In general, subhorizontal lines of correlation exist between sediment layers and between basalt layers in the area of the new percolation ponds. Some of the basalt flows and flow sequences are strongly correlative at different depth intervals and represent important stratigraphic unifying elements. Some units pinch out, or thicken or thin even over short separation distances of about 1,500 ft. A more distant correlation of more than 1 mile to corehole USGS 128 is possible for several of the basalt flows, but at greater depth. This is probably due to the broad subsidence of the eastern Snake River Plain centered along its topographic axis located to the south of INEEL. This study shows this most clearly in the oldest portions of the cored sections that have differentially subsided the greatest amount.

  16. LOFT/FET complex. Construction view of abutment footings for arches of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LOFT/FET complex. Construction view of abutment footings for arches of hangar (TAN-629). Tunnels between basement of hangar and control building (TAN-630) had to fit between arches. (Note concrete work taking place at hole at lower edge of view. This photo may document unexpected bubble in underlying lava rock. It was dumped full of concrete and a footing made. Source: Interview with John DeClue). Date: December 19, 1957. Photographer: Jack L. Anderson. INEEL negative no. 57-6203 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  17. PBF Reactor Building (PER620). Plot plan shows layout, including auxiliary ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620). Plot plan shows layout, including auxiliary buildings: Emergency Generator (621), Hose House (622), Cooling Tower Auxiliary (624), Maintenance and Storage Warehouse (625), Gas Cylinder Storage (627), Hose House (628), Cooling Tower (720), Substation (719), and other features. Road connections between PBF Reactor, its control building, and SPERT-I site. Note cable trenches along road to control building. Date: July 1965. Ebasco Services, PER-U-101. INEEL index no. 761-0100-00-205-123005 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  18. PBF Reactor Building (PER620) under construction. Aerial view with camera ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620) under construction. Aerial view with camera facing northeast. Steel framework is exposed for west wing and high bay. Concrete block siding on east wing. Railroad crane set up on west side. Note trenches proceeding from front of building. Left trench is for secondary coolant and will lead to Cooling Tower. Shorter trench will contain cables leading to control area. Photographer: Larry Page. Date: March 22, 1967. INEEL negative no. 67-5025 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  19. A&M. TAN607. Construction view, facing southwest. At upper left of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    A&M. TAN-607. Construction view, facing southwest. At upper left of view, north-wall equipment and operating galleries take shape on hot shop. Pumice-block side of storage pool section in center left of view. Water filter building (TAN-608) next to north wall of pool. Hot liquid waste building (TAN-616) at right of view. Note concrete construction of TAN-608 and 616. Date: January 18, 1954. INEEL negative no. 9604 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  20. 92. ARAIII. Overall view of GCRE area in 1959. From ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    92. ARA-III. Overall view of GCRE area in 1959. From left to right: ARA-607 (control building), ARA-608 (with high-bay, reactor building), ARA-610 (service building), ARA-609 (guard house), ARA-709 (water storage tank) ARA-710 in front of ARA-709 (fuel oil tank), ARA-611 (well pumphouse), and the cooling tower. Note petro-chem stack and other stacks emerging from reactor building. Camera facing northeast. August 1959. Ineel photo no. 59-4444. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  1. The Preparation and Characterization of INTEC HAW Phase I Composition Variation Study Glasses

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Musick, C. A.; Peeler, D. K.; Piepel, G. F.

    1999-03-01

    A glass composition variation study (CVS) is in progress to define formulations for the vitrification of high activity waste (HAW) proposed to be separated from dissolved calcine stored at the Idaho National Engineering and Environmental Laboratory (INEEL). Estimates of calcine and HAW compositions prepared in FY97 were used to define test matrix glasses. The HAW composition is of particular interest because high aluminum, zirconium, phosphorous and potassium, and low iron and sodium content places it outside the realm of vitrification experience in the Department of Energy (DOE) complex. Through application of statistical techniques, a test matrix was defined for Phasemore » 1 of the CVS. From this matrix, formulations were systematically selected for preparation and characterization with respect to homogeneity, viscosity, liquidus temperature (TL), and leaching response when subjected to the Product Consistency Test (PCT). Based on the properties determined, certain formulations appear suitable for further development including use in planning Phase 2 of the study. It is recommended that glasses to be investigated in Phase 2 be limited to 3-5 wt % phosphate. The results of characterizing the Phase 1 glasses are presented in this document. A full analysis of the composition-property relationships of glasses being developed for immobilizing HAWs will be performing at the completion of CVS phases. This analysis will be needed for the optimization of the glass formulations of vitrifying HAW. Contributions were made to this document by personnel working at the INEEL, Pacific Northwest National Laboratories (PNNL), and the Savannah River Technology Center (SRTC).« less

  2. IET. Aerial view of project, 95 percent complete. Camera facing ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Aerial view of project, 95 percent complete. Camera facing east. Left to right: stack, duct, mobile test cell building (TAN-624), four-rail track, dolly. Retaining wall between mobile test building and shielded control building (TAN-620) just beyond. North of control building are tank building (TAN-627) and fuel-transfer pump building (TAN-625). Guard house at upper right along exclusion fence. Construction vehicles and temporary warehouse in view near guard house. Date: June 6, 1955. INEEL negative no. 55-1462 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  3. PBF Reactor Building (PER620) basement. Workers wearing protective gear work ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Reactor Building (PER-620) basement. Workers wearing protective gear work inside cubicle 13 on the fission product detection system. Man on left is atop shielded box shown in previous photo. Posture of second man illustrates waist-high height of shielding box. His hand rests on the access panel, which has been filled with lead bricks and which has been slid shut to enclose detection instruments within box. Photographer: John Capek. Date: January 24, 1983. INEEL negative no. 83-41-3-5 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  4. SERA -- An advanced treatment planning system for neutron therapy and BNCT

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nigg, D.W.; Wemple, C.A.; Wessol, D.E.

    1999-09-01

    Detailed treatment planning calculations on a patient-specific basis are required for boron neutron capture therapy (BNCT). Two integrated treatment planning systems developed specifically for BNCT have been in clinical use in the United States over the past few years. The MacNCTPLAN BNCT treatment planning system is used in the clinical BNCT trials that are underway at the Massachusetts Institute of Technology. A second system, BNCT{_}rtpe (BNCT radiation therapy planning environment), developed independently by the Idaho national Engineering and Environmental Laboratory (INEEL) in collaboration with Montana State University (MSU), is used for treatment planning in the current series of BNCT clinicalmore » trials for glioblastoma at Brookhaven National Laboratory (BNL). This latter system is also licensed for use at several other BNCT research facilities worldwide. Although the currently available BNCT planning systems have served their purpose well, they suffer from somewhat long computation times (2 to 3 CPU-hours or more per field) relative to standard photon therapy planning software. This is largely due to the need for explicit three-dimensional solutions to the relevant transport equations. The simplifying approximations that work well for photon transport computations are not generally applicable to neutron transport computations. Greater computational speeds for BNCT treatment planning must therefore generally be achieved through the application of improved numerical techniques rather than by simplification of the governing equations. Recent efforts at INEEL and MSU have been directed toward this goal. This has resulted in a new paradigm for this type of calculation and the subsequent creation of the new simulation environment for radiotherapy applications (SERA) treatment planning system for BNCT. SERA is currently in initial clinical testing in connection with the trials at BNL, and it is expected to replace the present BNCT{_}rtpe system upon general release during 1999.« less

  5. ICPP tank farm closure study. Volume 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Spaulding, B.C.; Gavalya, R.A.; Dahlmeir, M.M.

    1998-02-01

    The disposition of INEEL radioactive wastes is now under a Settlement Agreement between the DOE and the State of Idaho. The Settlement Agreement requires that existing liquid sodium bearing waste (SBW), and other liquid waste inventories be treated by December 31, 2012. This agreement also requires that all HLW, including calcined waste, be disposed or made road ready to ship from the INEEL by 2035. Sodium bearing waste (SBW) is produced from decontamination operations and HLW from reprocessing of SNF. SBW and HLW are radioactive and hazardous mixed waste; the radioactive constituents are regulated by DOE and the hazardous constituentsmore » are regulated by the Resource Conservation and Recovery Act (RCRA). Calcined waste, a dry granular material, is produced in the New Waste Calcining Facility (NWCF). Two primary waste tank storage locations exist at the ICPP: Tank Farm Facility (TFF) and the Calcined Solids Storage Facility (CSSF). The TFF has the following underground storage tanks: four 18,400-gallon tanks (WM 100-102, WL 101); four 30,000-gallon tanks (WM 103-106); and eleven 300,000+ gallon tanks. This includes nine 300,000-gallon tanks (WM 182-190) and two 318,000 gallon tanks (WM 180-181). This study analyzes the closure and subsequent use of the eleven 300,000+ gallon tanks. The 18,400 and 30,000-gallon tanks were not included in the work scope and will be closed as a separate activity. This study was conducted to support the HLW Environmental Impact Statement (EIS) waste separations options and addresses closure of the 300,000-gallon liquid waste storage tanks and subsequent tank void uses. A figure provides a diagram estimating how the TFF could be used as part of the separations options. Other possible TFF uses are also discussed in this study.« less

  6. Reevalution of background iodine-129 concentrations in water from the Snake River Plain Aquifer, Idaho, 2003

    USGS Publications Warehouse

    Cecil, L. DeWayne; Hall, L. Flint; Green, Jaromy R.

    2003-01-01

    Background concentrations of iodine-129 (129I, half-life = 15.7 million years) resulting from natural production in the earth?s atmosphere, in situ production in the earth by spontaneous fission of uranium-238(238U), and fallout from nuclear weapons tests conducted in the 1950s and 1960s were reevaluated on the basis of 52 analyses of ground- and surface-water samples collected from the eastern Snake River Plain in southeastern Idaho. The background concentration estimated using the results of a subset of 30 ground-water samples analyzed in this reevaluation is 5.4 attocuries per liter (aCi/L; 1 aCi = 10-18 curies) and the 95-percent nonparametric confidence interval is 5.2 to 10.0 aCi/L. In a previous study, a background 129I concentration was estimated on the basis of analyses of water samples from 16 sites on or tributary to the eastern Snake River Plain. At the 99-percent confidence level, background concentrations of 129I in that study were less than or equal to 8.2 aCi/L. During 1993?94, 34 water samples from 32 additional sites were analyzed for 129I to better establish the background concentrations in surface and ground water from the eastern Snake River Plain that is presumed to be unaffected by wastedisposal practices at the Idaho National Engineering and Environmental Laboratory (INEEL). Surface water contained larger 129I concentrations than water from springs and wells contained. Because surface water is more likely to be affected by anthropogenic fallout and evapotranspiration, background 129I concentrations were estimated in the current research using the laboratory results of ground-water samples that were assumed to be unaffected by INEEL disposal practices.

  7. Transport of Carbon Tetrachloride in a Fractured Vadose Zone due to Atmospheric Pressure Fluctuations, Diffusion, and Vapor Density

    NASA Astrophysics Data System (ADS)

    McCray, J. E.; Downs, W.; Falta, R. W.; Housley, T.

    2005-12-01

    DNAPL sources of carbon tetrachloride (CT) vapors are of interest at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The site is underlain by thick fractured basalt that includes sedimentary interbeds, each are a few meters thick. Daily atmospheric pressure fluctuations serve as driving forces for CT vapor transport in the subsurface. Other important transport processes for vapor movement include gas-phase diffusion and density-driven transport. The objective of this research is to investigate the influence and relative importance of these processes on gaseous transport of CT. Gas pressure and vapor concentration measurements were conducted at various depths in two wells. A numerical multiphase flow model (TOUGH2), calibrated to field pressure data, is used to conduct sensitivity analyses to elucidate the importance of the different transport mechanisms. Results show that the basalt is highly permeable to vertical air flow. The pressure dampening occurs mainly in the sedimentary interbeds. Model-calibrated permeability values for the interbeds are similar to those obtained in a study by the U.S. Geological Survey for shallow sediments, and an order of magnitude higher than column-scale values obtained by previous studies conducted by INEEL scientists. The transport simulations indicate that considering the effect of barometric pressure changes is critical to simulating transport of pollutants in the vadose zone above the DNAPL source. Predicted concentrations can be orders of magnitude smaller than actual concentrations if the effect is not considered. Below the DNAPL vapor source, accounting for density and diffusion alone would yield acceptable results provided that a 20% error in concentrations are acceptable, and that simulating concentrations trends (and not actual concentrations) is the primary goal.

  8. Hydraulic and geochemical framework of the Idaho National Engineering and Environmental Laboratory vadose zone

    USGS Publications Warehouse

    Nimmo, John R.; Rousseau, Joseph P.; Perkins, Kim S.; Stollenwerk, Kenneth G.; Glynn, Pierre D.; Bartholomay, Roy C.; Knobel, LeRoy L.

    2004-01-01

    Questions of major importance for subsurface contaminant transport at the Idaho National Engineering and Environmental Laboratory (INEEL) include (i) travel times to the aquifer, both average or typical values and the range of values to be expected, and (ii) modes of contaminant transport, especially sorption processes. The hydraulic and geochemical framework within which these questions are addressed is dominated by extreme heterogeneity in a vadose zone and aquifer consisting of interbedded basalts and sediments. Hydraulically, major issues include diverse possible types of flow pathways, extreme anisotropy, preferential flow, combined vertical and horizontal flow, and temporary saturation or perching. Geochemically, major issues include contaminant mobility as influenced by redox conditions, the concentration of organic and inorganic complexing solutes and other local variables, the interaction with infiltrating waters and with the contaminant source environment, and the aqueous speciation of contaminants such as actinides. Another major issue is the possibility of colloid transport, which inverts some of the traditional concepts of mobility, as sorbed contaminants on mobile colloids may be transported with ease compared with contaminants that are not sorbed. With respect to the goal of minimizing aquifer concentrations of contaminants, some characteristics of the vadose zone are essentially completely favorable. Examples include the great thickness (200 m) of the vadose zone, and the presence of substantial quantities of fine sediments that can retard contaminant transport both hydraulically and chemically. Most characteristics, however, have both favorable and unfavorable aspects. For example, preferential flow, as promoted by several notable features of the vadose zone at the INEEL, can provide fast, minimally sorbing pathways for contaminants to reach the aquifer easily, but it also leads to a wide dispersal of contaminants in a large volume of subsurface material, thus increasing the opportunity for dilution and sorption.

  9. PBF Cooling Tower detail. Camera facing southwest into north side ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF Cooling Tower detail. Camera facing southwest into north side of Tower. Five horizontal layers of splash bars constitute fill decks, which will break up falling water into droplets, promoting evaporative cooling. Louvered faces, through which air enters tower, are on east and west sides. Louvers have been installed. Support framework for one of two venturi-shaped fan stacks (or "vents") is in center top. Orifices in hot basins (not in view) will distribute water over fill. Photographer: Kirsh. Date: May 15, 1969. INEEL negative no. 69-3032 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  10. Historical Development of the U.S. Geological Survey Hydrologic Monitoring and Investigative Programs at the Idaho National Engineering and Environmental Laboratory, Idaho, 1949 to 2001

    DTIC Science & Technology

    2005-01-01

    Cesium- 137 , Cobalt-60, and Chromium-51 ………………………………………… 12 Plutonium-238, Plutonium-239, -240 (undivided), and Americium-241 ……………… 12 Iodine-129...1992) presented water-level data from the ESRPA collected from 1983 through 1990 from 137 wells. At the end of 2000, water levels in 203 aquifer and...Cesium- 137 , Cobalt-60, and Chromium-51 The USGS has routinely monitored ground water at the INEEL for gamma radiation since 1962. Gamma

  11. SPERT1. Contextual aerial view of SPERTI Reactor Pit Building (PER605) ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-1. Contextual aerial view of SPERT-I Reactor Pit Building (PER-605) at top of view, and its accessories: the earth-shielded instrument cell (PER-606) immediately adjacent to it; the Guard House (PER-607) to its right; and the Terminal Building in lower center of view (PER-604). Camera faces west. Road and buried line leaving view at right lead to Control Building (PER-601) out of view. Sagebrush vegetation has been scraped from around buildings. Photographer: R.G. Larsen. Date: June 6, 1955. INEEL negative no. 55-1477. - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  12. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mac Donald, Philip Elsworth; Buongiorno, Jacopo; Davis, Cliff Bybee

    The purpose of this collaborative Idaho National Engineering and Environmental Laboratory (INEEL) and Massachusetts Institute of Technology (MIT) Laboratory Directed Research and Development (LDRD) project is to investigate the suitability of lead or lead-bismuth cooled fast reactors for producing low-cost electricity as well as for actinide burning. The goal is to identify and analyze the key technical issues in core neutronics, materials, thermal-hydraulics, fuels, and economics associated with the development of this reactor concept. Work has been accomplished in four major areas of research: core neutronic design, plant engineering, material compatibility studies, and coolant activation. The publications derived from workmore » on this project (since project inception) are listed in Appendix A.« less

  13. ADM. Aerial view of administration area. Camera facing westerly. From ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Aerial view of administration area. Camera facing westerly. From left to right in foregound: Substation (TAN-605), Warehouse (TAN-628), Gate House (TAN-601), Administration Building (TAN-602). Left to right middle ground: Service Building (TAN-603), Warehouse (later known as Maintenance Shop or Craft Shop, TAN-604), Water Well Pump Houses, Fuel Tanks and Fuel Pump Houses, and Water Storage Tanks. Change House (TAN-606) on near side of berm. Large building beyond berm is A&M. Building, TAN-607. Railroad tracks beyond lead from (unseen) turntable to the IET. Date: June 6, 1955. INEEL negative no. 13201 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. SPERTI/PBF. Contextual aerial view after PBF had begun operating, but ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SPERT-I/PBF. Contextual aerial view after PBF had begun operating, but prior to expansion of southwest corner of Reactor Building (PER-620). Camera facing northeast. Reactor Building in center of view. Cooling Tower (PER-720) to its left. Warehouse (PER-625) at lower left was built in 1966. SPERT-I Reactor Building (PER-605) and Instrument Cell Building (PER-604) at right of view. Buried cables and piping proceed from PBF toward lower edge of view to Control Building further south and out of view. Photographer: Farmer. Date: March 26, 1976. INEEL negative no. 76-1344 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  15. PBF (PER620) interior of Reactor Room. Camera facing south from ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PBF (PER-620) interior of Reactor Room. Camera facing south from stairway platform in southwest corner (similar to platform in view at left). Reactor was beneath water in circular tank. Fuel was stored in the canal north of it. Platform and apparatus at right is reactor bridge with control rod mechanisms and actuators. The entire apparatus swung over the reactor and pool during operations. Personnel in view are involved with decontamination and preparation of facility for demolition. Note rails near ceiling for crane; motor for rollup door at upper center of view. Date: March 2004. INEEL negative no. HD-41-3-2 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID

  16. Geologic Controls of Hydraulic Conductivity in the Snake River Plain Aquifer At and Near the Idaho National Engineering and Environmental Laboratory, Idaho

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    S. R. Anderson; M. A. Kuntz; L. C. Davis

    1999-02-01

    The effective hydraulic conductivity of basalt and interbedded sediment that compose the Snake River Plain aquifer at and near the Idaho National Engineering and Environmental Laboratory (INEEL) ranges from about 1.0x10 -2 to 3.2x10 4 feet per day (ft/d). This six-order-of-magnitude range of hydraulic conductivity was estimated from single-well aquifer tests in 114 wells, and is attributed mainly to the physical characteristics and distribution of basalt flows and dikes. Hydraulic conductivity is greatest in thin pahoehoe flows and near-vent volcanic deposits. Hydraulic conductivity is least in flows and deposits cut by dikes. Estimates of hydraulic conductivity at and near themore » INEEL are similar to those measured in similar volcanic settings in Hawaii. The largest variety of rock types and the greatest range of hydraulic conductivity are in volcanic rift zones, which are characterized by numerous aligned volcanic vents and fissures related to underlying dikes. Three broad categories of hydraulic conductivity corresponding to six general types of geologic controls can be inferred from the distribution of wells and vent corridors. Hydraulic conductivity of basalt flows probably is increased by localized fissures and coarse mixtures of interbedded sediment, scoria, and basalt rubble. Hydraulic conductivity of basalt flows is decreased locally by abundant alteration minerals of probable hydrothermal origin. Hydraulic conductivity varies as much as six orders of magnitude in a single vent corridor and varies from three to five orders of magnitude within distances of 500 to 1,000 feet. Abrupt changes in hydraulic conductivity over short distances suggest the presence of preferential pathways and local barriers that may greatly affect the movement of ground water and the dispersion of radioactive and chemical wastes downgradient from points of waste disposal.« less

  17. Effect of activities at the Idaho National Engineering and Environmental Laboratory on the water quality of the Snake River Plain aquifer in the Magic Valley study

    USGS Publications Warehouse

    Bartholomay, Roy C.

    1998-01-01

    Radiochemical and chemical constituents in wastewater generated at facilities of the Idaho National Engineering and Environmental Laboratory (INEEL) (figure 1) have been discharged to waste-disposal ponds and wells since the early 1950 s. Public concern has been expressed that some of these constituents could migrate through the Snake River Plain aquifer to the Snake River in the Twin Falls-Hagerman area Because of these concerns the U.S. Department of Energy (DOE) requested that the U.S. Geological Survey (USGS) conduct three studies to gain a greater understanding of the chemical quality of water in the aquifer. One study described a one-time sampling effort for radionuclides, trace elements, and organic compounds in the eastern part of the A&B Irrigation District in Minidoka County (Mann and Knobel, 1990). Another ongoing study involves sampling for tritium from 19 springs on the north side of the Snake River in the Twin Falls-Hagerman area (Mann, 1989; Mann and Low, 1994). A third study an ongoing annual sampling effort in the area between the southern boundary of the INEEL and Hagerman (figure 1) (hereafter referred to as the Magic Valley study area), is being conducted with the Idaho Department of Water Resources in cooperation with the DOE. Data for a variety of radiochemical and chemical constituents from this study have been published by Wegner and Campbell (1991); Bartholomay, Edwards, and Campbell (1992, 1993, 1994a, 1994b); and Bartholomay, Williams, and Campbell (1995, 1996, 1997b). Data discussed in this fact sheet were taken from these reports. An evaluation of data collected during the first four years of this study (Bartholomay Williams, and Campbell, 1997a) showed no pattern of water-quality change for radionuclide data as concentrations randomly increased or decreased. The inorganic constituent data showed no statistical change between sample rounds.

  18. A Decision Support System for Optimum Use of Fertilizers

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hoskinson, Reed Louis; Hess, John Richard; Fink, Raymond Keith

    1999-07-01

    The Decision Support System for Agriculture (DSS4Ag) is an expert system being developed by the Site-Specific Technologies for Agriculture (SST4Ag) precision farming research project at the INEEL. DSS4Ag uses state-of-the-art artificial intelligence and computer science technologies to make spatially variable, site-specific, economically optimum decisions on fertilizer use. The DSS4Ag has an open architecture that allows for external input and addition of new requirements and integrates its results with existing agricultural systems’ infrastructures. The DSS4Ag reflects a paradigm shift in the information revolution in agriculture that is precision farming. We depict this information revolution in agriculture as an historic trend inmore » the agricultural decision-making process.« less

  19. A Decision Support System for Optimum Use of Fertilizers

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    R. L. Hoskinson; J. R. Hess; R. K. Fink

    1999-07-01

    The Decision Support System for Agriculture (DSS4Ag) is an expert system being developed by the Site-Specific Technologies for Agriculture (SST4Ag) precision farming research project at the INEEL. DSS4Ag uses state-of-the-art artificial intelligence and computer science technologies to make spatially variable, site-specific, economically optimum decisions on fertilizer use. The DSS4Ag has an open architecture that allows for external input and addition of new requirements and integrates its results with existing agricultural systems' infrastructures. The DSS4Ag reflects a paradigm shift in the information revolution in agriculture that is precision farming. We depict this information revolution in agriculture as an historic trend inmore » the agricultural decision-making process.« less

  20. The Integrated Waste Tracking System - A Flexible Waste Management Tool

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Anderson, Robert Stephen

    2001-02-01

    The US Department of Energy (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) has fully embraced a flexible, computer-based tool to help increase waste management efficiency and integrate multiple operational functions from waste generation through waste disposition while reducing cost. The Integrated Waste Tracking System (IWTS)provides comprehensive information management for containerized waste during generation,storage, treatment, transport, and disposal. The IWTS provides all information necessary for facilities to properly manage and demonstrate regulatory compliance. As a platformindependent, client-server and Web-based inventory and compliance system, the IWTS has proven to be a successful tracking, characterization, compliance, and reporting tool that meets themore » needs of both operations and management while providing a high level of management flexibility.« less

  1. 1996 LMITCO environmental monitoring program report for the Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-09-01

    This report describes the calendar year 1996 environmental surveillance and compliance monitoring activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory (INEEL). Results of sampling performed by the Radiological Environmental Surveillance, Site Environmental Surveillance, Drinking Water, Effluent Monitoring, Storm Water Monitoring, Groundwater Monitoring, and Special Request Monitoring Programs are included in this report. The primary purposes of the surveillance and monitoring activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards, and to ensure protection of human health and themore » environment. This report compares 1996 data with program-specific regulatory guidelines and past data to evaluate trends.« less

  2. Environmental Science and Research Foundation, Inc. annual technical report: Calendar year 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reynolds, R.D.; Warren, R.W.

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation`s mission to DOE-ID provides support in several key areas. The Foundation conducts an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provides environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research on the Idaho National Environmental Research Park. This research benefits major DOE-ID programs includingmore » Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. Summaries are included of the individual research projects.« less

  3. Chemical and physical properties affecting strontium distribution coefficients of surficial-sediment samples at the Idaho National Engineering and Environmental Laboratory, Idaho

    USGS Publications Warehouse

    Liszewski, M.J.; Rosentreter, J.J.; Miller, Karl E.; Bartholomay, R.C.

    2000-01-01

    The U.S. Geological Survey and Idaho State University, in cooperation with the U.S. Department of Energy, conducted a study to determine strontium distribution coefficients (K(d)s) of surficial sediments at the Idaho National Engineering and Environmental Laboratory (INEEL). Batch experiments using synthesized aqueous solutions were used to determine K(d)s, which describe the distribution of a solute between the solution and solid phase, of 20 surficial-sediment samples from the INEEL. The K(d)s for the 20 surficial-sediment samples ranged from 36 to 275 ml/g. Many properties of both the synthesized aqueous solutions and sediments used in the experiments also were determined. Solution properties determined were initial and equilibrium concentrations of calcium, magnesium, and strontium, pH and specific conductance, and initial concentrations of potassium and sodium. Sediment properties determined were grain-size distribution, bulk mineralogy, whole-rock major-oxide and strontium and barium concentrations, and Brunauer-Emmett-Teller (BET) surface area. Solution and sediment properties were correlated with strontium K(d)s of the 20 surficial sediments using Pearson correlation coefficients. Solution properties with the strongest correlations with strontium K(d)s were equilibrium pH and equilibrium calcium concentration correlation coefficients, 0.6598 and -0.6518, respectively. Sediment properties with the strongest correlations with strontium K(d)s were manganese oxide (MnO), BET surface area, and the >4.75-mm-grain-size fraction correlation coefficients, 0.7054, 0.7022, and -0.6660, respectively. Effects of solution properties on strontium K(d)s were interpreted as being due to competition among similarly charged and sized cations in solution for strontium-sorption sites; effects of sediment properties on strontium K(d)s were interpreted as being surface-area related. Multivariate analyses of these solution and sediment properties resulted in r2 values of 0.8071 when all five properties were used and 0.8043 when three properties, equilibrium pH, MnO, and BET surface area, were used.

  4. Use of chlorine-36 to determine regional-scale aquifer dispersivity, eastern Snake River Plain aquifer, Idaho/USA

    USGS Publications Warehouse

    Cecil, L.D.; Welhan, J.A.; Green, J.R.; Grape, S.K.; Sudicky, E.R.

    2000-01-01

    Chlorine-36 (36Cl) derived from processed nuclear waste that was disposed at the US Department of Energy's Idaho National Engineering and Environmental Laboratory (INEEL) through a deep injection well in 1958, was detected 24-28 yr later in groundwater monitoring wells approximately 26 km downgradient from the source. Groundwater samples covering the period 1966-1995 were selected from the US Geological Survey's archived-sample library at the INEEL and analyzed for 36Cl by accelerator mass spectrometry (AMS). The smaller 36Cl peak concentrations in water from the far-field monitoring wells relative to the input suggest that aquifer dispersivity may be large. However, the sharpness of the 1958 disposal peak of 36Cl is matched by the measured 36Cl concentrations in water from these wells. This implies that a small aquifer dispersivity may be attributed to preferential groundwater flowpaths. Assuming that tracer arrival times at monitoring wells are controlled by preferential flow, a 1-D system-response model was used to estimate dispersivity by comparing the shape of predicted 36Cl-concentration curves to the shape of 36Cl-concentration curves measured in water from these observation wells. The comparisons suggest that a 1-D dispersivity of 5 m provides the best fit to the tracer data. Previous work using a 2-D equivalent porous-media model concluded that longitudinal dispersivity (equivalent to 1-D dispersivity in our model) was 90 m (Ackerman, 1991). A 90 m dispersivity value eliminates the 1958 disposal peak in our model output curves. The implications of the arrival of 36Cl at downgradient monitoring wells are important for three reasons: (1) the arrival times and associated 36Cl concentrations provide quantitative constraints on residence times, velocities, and dispersivities in the aquifer; (2) they help to refine our working hypotheses of groundwater flow in this aquifer and (3) they may suggest a means of estimating the distribution of preferential flowpaths in the aquifer. ?? 2000 Elsevier Science B.V. All rights reserved.

  5. Multimedia case management system implemented in Java

    NASA Astrophysics Data System (ADS)

    Stewart, Howard D.; Davis, Midge L.; Handy, Dale L.; Kvarfordt, Kent B.; Ford, Glenn

    1999-01-01

    Managing the timely access of information is a major challenge facing law enforcement agencies. One of the areas of greatest need is that of the case management process. During the course of FY98, the Office of National Drug Control Policy (ONDCP), the Counterdrug Technology Assessment Center (CTAC), the Idaho National Engineering and Environmental Laboratory (INEEL), and the Criminal Investigative Bureau (CIB) of the state of Idaho, created a Northwest testbed to develop and integrate a multimedia case management system. A system was developed to assist investigators in tracking and maintaining investigative cases and improving access to internal and external data resources. In this paper, we discuss the results of our case management system development and the ability to present state and federal information incorporating object oriented and multimedia techniques. We then outline our plans for future research and development.

  6. Environmental Science and Research Foundation annual technical report: Calendar year 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Morris, R.C.; Blew, R.D.

    1997-07-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation`s mission to DOE-ID provides support in several key areas. The authors conduct an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provide environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research in the Idaho National Environmental Research Park. This research benefits major DOE-ID programs includingmore » Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. The major accomplishments of the Foundation and its University Affiliates during the calendar year 1996 are discussed.« less

  7. Novel Threat-risk Index Using Probabilistic Risk Assessment and Human Reliability Analysis - Final Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    George A. Beitel

    2004-02-01

    In support of a national need to improve the current state-of-the-art in alerting decision makers to the risk of terrorist attack, a quantitative approach employing scientific and engineering concepts to develop a threat-risk index was undertaken at the Idaho National Engineering and Environmental Laboratory (INEEL). As a result of this effort, a set of models has been successfully integrated into a single comprehensive model known as Quantitative Threat-Risk Index Model (QTRIM), with the capability of computing a quantitative threat-risk index on a system level, as well as for the major components of the system. Such a threat-risk index could providemore » a quantitative variant or basis for either prioritizing security upgrades or updating the current qualitative national color-coded terrorist threat alert.« less

  8. Radiological Characterization Methodology of INEEL Stored RH-TRU Waste from ANL-E

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rajiv N. Bhatt

    2003-02-01

    An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using this methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

  9. Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kuan, P.; Bhatt, R.N.

    2003-01-14

    An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

  10. Spatial variability of sedimentary interbed properties near the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory, Idaho

    USGS Publications Warehouse

    Winfield, Kari A.

    2003-01-01

    The subsurface at the Idaho National Engineering and Environmental Laboratory (INEEL) is complex, comprised primarily of thick, fractured basalt flows interbedded with thinner sedimentary intervals. The unsaturated zone can be as thick as 200 m in the southwestern part of the INEEL. The Vadose Zone Research Park (VZRP), located approximately 10 km southwest of the Idaho Nuclear Technology and Engineering Center (INTEC), was established in 2001 to study the subsurface of a relatively undisturbed part of the INEEL. Waste percolation ponds for the INTEC were relocated to the VZRP due to concerns that perched water within the vadose zone under the original infiltration ponds (located immediately south of the INTEC) could contribute to migration of contaminants to the Snake River Plain aquifer. Knowledge of the spatial distribution of texture and hydraulic properties is important for developing a better understanding of subsurface flow processes within the interbeds, for example, by identifying low permeability layers that could lead to the formation of perched ground-water zones. Because particle-size distributions are easier to measure than hydraulic properties, particle size serves as an analog for determining how the unsaturated hydraulic properties vary both vertically within particular interbeds and laterally within the VZRP. As part of the characterization program for the subsurface at the VZRP, unsaturated and saturated hydraulic properties were measured on 10 core samples from six boreholes. Bulk properties, including particle size, bulk density, particle density, and specific surface area, were determined on material from the same depth intervals as the core samples, with an additional 66 particle- size distributions measured on bulk samples from the same boreholes. From lithologic logs of the 32 boreholes at the VZRP, three relatively thick interbeds (in places up to 10 m thick) were identified at depths of 35, 45, and 55 m below land surface. The 35-m interbed extends laterally over a distance of at least 900 m from the Big Lost River to the new percolation pond area of the VZRP. Most wells within the VZRP were drilled to depths less than 50 m, making it difficult to infer the lateral extent of the 45-m and 55-m interbeds. The 35-m interbed is uniform in texture both vertically and laterally; the 45-m interbed coarsens upward; and the 55-m interbed contains alternating coarse and fine layers. Seventy-one out of 90 samples were silt loams and 9 out of 90 samples were classified as either sandy loams, loamy sands, or sands. The coarsest samples were located within the 45-m and 55-m interbeds of borehole ICPP-SCI-V-215, located near the southeast corner of the new percolation pond area. At the tops of some interbeds, baked-zone intervals were identified by their oxidized color (yellowish red to red) compared to the color of the underlying non-baked material (pale yellow to brown). The average geometric mean particle diameter of baked-zone intervals was only slightly coarser, in some cases, than the underlying non-baked sediment. This is likely due to both depositional differences between the top and bottom of the interbeds and the presence of small basalt clasts in the sediment. Core sample hydraulic properties from baked zones within the different interbeds did not show effects from alteration caused during basalt deposition, but differed mainly by texture. Saturated hydraulic conductivities (Ksat) for the 10 core samples ranged from 10-7 to 10-4 cm/s. Low permeability layers, with Ksat values less than 10-7 cm/s, within the 35-m and 45-m interbeds may cause perched ground-water zones to form beneath the new percolation pond area, leading to the possible lateral movement of water away from the VZRP.

  11. Structured methods for identifying and correcting potential human errors in aviation operations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nelson, W.R.

    1997-10-01

    Human errors have been identified as the source of approximately 60% of the incidents and accidents that occur in commercial aviation. It can be assumed that a very large number of human errors occur in aviation operations, even though in most cases the redundancies and diversities built into the design of aircraft systems prevent the errors from leading to serious consequences. In addition, when it is acknowledged that many system failures have their roots in human errors that occur in the design phase, it becomes apparent that the identification and elimination of potential human errors could significantly decrease the risksmore » of aviation operations. This will become even more critical during the design of advanced automation-based aircraft systems as well as next-generation systems for air traffic management. Structured methods to identify and correct potential human errors in aviation operations have been developed and are currently undergoing testing at the Idaho National Engineering and Environmental Laboratory (INEEL).« less

  12. Direct cementitious waste option study report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dafoe, R.E.; Losinski, S.J.

    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 andmore » 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.« less

  13. Cementitious waste option scoping study report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lee, A.E.; Taylor, D.D.

    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) on the Idaho National Engineering and Environmental Laboratory (INEEL) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This study investigates the nonseparations Cementitious Waste Option (CWO) as a means to achieve this goal. Under this option all liquid sodium-bearing waste (SBW) and existing HLW calcine would be recalcined with sucrose, grouted, canisterized, and interim stored asmore » a mixed-HLW for eventual preparation and shipment off-Site for disposal. The CWO waste would be transported to a Greater Confinement Disposal Facility (GCDF) located in the southwestern desert of the US on the Nevada Test Site (NTS). All transport preparation, shipment, and disposal facility activities are beyond the scope of this study. CWO waste processing, packaging, and interim storage would occur over a 5-year period between 2013 and 2017. Waste transport and disposal would occur during the same time period.« less

  14. Producing Production Level Tooling in Prototype Timing

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mc Hugh, Kevin Matthew; Knirsch, J.

    A new rapid solidification process machine will be able to produce eight-inch diameter by six-inch thick finished cavities at the rate of one per hour - a rate that will change the tooling industry dramatically. Global Metal Technologies, Inc. (GMTI) (Solon, OH) has signed an exclusive license with Idaho National Engineered and Environmental Laboratories (INEEL) (Idaho Falls, ID) for the development and commercialization of the rapid solidification process (RSP tooling). The first production machine is scheduled for delivery in July 2001. The RSP tooling process is a method of producing production level tooling in prototype timing. The process' inventor, Kevinmore » McHugh, describes it as a rapid solidification method, which differentiates it from the standard spray forming methods. RSP itself is relatively straightforward. Molten metal is sprayed against the ceramic pattern, replicating the pattern's contours, surface texture and details. After spraying, the molten tool steel is cooled at room temperature and separated from the pattern. The irregular periphery of the freshly sprayed insert is squared off, either by machining or, in the case of harder tool steels, by wire EDM. XX« less

  15. Multi-Detector Analysis System for Spent Nuclear Fuel Characterization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Reber, Edward Lawrence; Aryaeinejad, Rahmat; Cole, Jerald Donald

    1999-09-01

    The Spent Nuclear Fuel (SNF) Non-Destructive Analysis (NDA) program at INEEL is developing a system to characterize SNF for fissile mass, radiation source term, and fissile isotopic content. The system is based on the integration of the Fission Assay Tomography System (FATS) and the Gamma-Neutron Analysis Technique (GNAT) developed under programs supported by the DOE Office of Non-proliferation and National Security. Both FATS and GNAT were developed as separate systems to provide information on the location of special nuclear material in weapons configuration (FATS role), and to measure isotopic ratios of fissile material to determine if the material was frommore » a weapon (GNAT role). FATS is capable of not only determining the presence and location of fissile material but also the quantity of fissile material present to within 50%. GNAT determines the ratios of the fissile and fissionable material by coincidence methods that allow the two prompt (immediately) produced fission fragments to be identified. Therefore, from the combination of FATS and GNAT, MDAS is able to measure the fissile material, radiation source term, and fissile isotopics content.« less

  16. In Situ Production of Chlorine-36 in the Eastern Snake River Plain Aquifer, Idaho: Implications for Describing Ground-Water Contamination Near a Nuclear Facility

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    L. D. Cecil; L. L. Knobel; J. R. Green

    2000-06-01

    The purpose of this report is to describe the calculated contribution to ground water of natural, in situ produced 36Cl in the eastern Snake River Plain aquifer and to compare these concentrations in ground water with measured concentrations near a nuclear facility in southeastern Idaho. The scope focused on isotopic and chemical analyses and associated 36Cl in situ production calculations on 25 whole-rock samples from 6 major water-bearing rock types present in the eastern Snake River Plain. The rock types investigated were basalt, rhyolite, limestone, dolomite, shale, and quartzite. Determining the contribution of in situ production to 36Cl inventories inmore » ground water facilitated the identification of the source for this radionuclide in environmental samples. On the basis of calculations reported here, in situ production of 36Cl was determined to be insignificant compared to concentrations measured in ground water near buried and injected nuclear waste at the INEEL. Maximum estimated 36Cl concentrations in ground water from in situ production are on the same order of magnitude as natural concentrations in meteoric water.« less

  17. Operable Unit 7-13/14 in situ thermal desorption treatability study work plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Shaw, P.; Nickelson, D.; Hyde, R.

    1999-05-01

    This Work Plan provides technical details for conducting a treatability study that will evaluate the application of in situ thermal desorption (ISTD) to landfill waste at the Subsurface Disposal Area (SDA) at the Idaho National Engineering and Environmental Laboratory (INEEL). ISTD is a form of thermally enhanced vapor vacuum extraction that heats contaminated soil and waste underground to raise its temperature and thereby vaporize and destroy most organics. An aboveground vapor vacuum collection and treatment system then destroys or absorbs the remaining organics and vents carbon dioxide and water to the atmosphere. The technology is a byproduct of an advancedmore » oil-well thermal extraction program. The purpose of the ISTD treatability study is to fill performance-based data gaps relative to off-gas system performance, administrative feasibility, effects of the treatment on radioactive contaminants, worker safety during mobilization and demobilization, and effects of landfill type waste on the process (time to remediate, subsidence potential, underground fires, etc.). By performing this treatability study, uncertainties associated with ISTD as a selected remedy will be reduced, providing a better foundation of remedial recommendations and ultimate selection of remedial actions for the SDA.« less

  18. Novel Fission-Product Separation based on Room-Temperature Ionic Liquids

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rogers, Robin D.

    2004-12-31

    U.S. DOE's underground storage tanks at Hanford, SRS, and INEEL contain liquid wastes with high concentrations of radioactive cesium-137 and strontium-90. Because the primary chemical components of alkaline supernatants are sodium nitrate and sodium hydroxide, the majority of this could be disposed of as low level waste if radioactive cesium-137 and strontium- 90 could be selectively removed. The underlying goal of this project was to investigate the application of ionic liquids as novel solvents for new solvent extraction processes for separation of cesium-137 and strontium-90 from tank wastes. Ionic liquids are a distinct sub-set of liquids, comprising only of cationsmore » and anions they are proving to be increasingly interesting fluids for application in systems from electrochemistry to energetic materials, and are also rapidly establishing their promise as viable media for synthesis and separations operations. Properties including low melting points, electrochemical conductivity, wide liquid ranges, lack of vapor-pressure, and chemical tunability have encouraged researchers to explore the uses of ILs in place of volatile organic solvents. The most promising current developments arise from control of the unique combinations of chemical and physical properties characteristic of ionic liquids.« less

  19. 1998 Environmental Monitoring Program Report for the Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    L. V. Street

    This report describes the calendar year 1998 compliance monitoring and environmental surveillance activities of the Lockheed Martin Idaho Technologies Company Environmental Monitoring Program performed at the Idaho National Engineering and Environmental Laboratory. This report includes results of sampling performed by the Drinking Water, Effluent, Storm Water, Groundwater Monitoring, and Environmental Surveillance Programs. This report compares the 1998 results to program-specific regulatory guidelines and past data to evaluate trends. The primary purposes of the monitoring and surveillance activities are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards, and to ensure protection ofmore » public health and the environment. Surveillance of environmental media did not identify any previously unknown environmental problems or trends, which would indicate a loss of control or unplanned releases from facility operations. The INEEL complied with permits and applicable regulations, with the exception of nitrogen samples in a disposal pond effluent stream and iron and total coliform bacteria in groundwater downgradient from one disposal pond. Data collected by the Environmental Monitoring Program demonstrate that the public health and environment were protected.« less

  20. Tanks Focus Area site needs assessment FY 1998

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by four major US Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). This document describes the TFA`s process of collecting site needs, analyzing them, and creating technical responses to the sites. It also summarizes the information contained within the TFA needs database, portraying information provided by four majormore » DOE sites with tank waste problems. The overall TFA program objective is to deliver a tank technology program that reduces the current cost, and the operational and safety risks of tank remediation. The TFA`s continues to enjoy close, cooperative relationships with each site. During the past year, the TFA has fostered exchanges of technical information between sites. These exchanges have proven to be healthy for all concerned. The TFA recognizes that site technology needs often change, and the TFA must be prepared not only to amend its program in response, but to help the sites arrive at the best technical approach to solve revised site needs.« less

  1. DOE Office of Scientific and Technical Information (OSTI.GOV)

    M. L. Abbott; K. N. Keck; R. E. Schindler

    This screening level risk assessment evaluates potential adverse human health and ecological impacts resulting from continued operations of the calciner at the New Waste Calcining Facility (NWCF) at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory (INEEL). The assessment was conducted in accordance with the Environmental Protection Agency (EPA) report, Guidance for Performing Screening Level Risk Analyses at Combustion Facilities Burning Hazardous Waste. This screening guidance is intended to give a conservative estimate of the potential risks to determine whether a more refined assessment is warranted. The NWCF uses a fluidized-bed combustor to solidifymore » (calcine) liquid radioactive mixed waste from the INTEC Tank Farm facility. Calciner off volatilized metal species, trace organic compounds, and low-levels of radionuclides. Conservative stack emission rates were calculated based on maximum waste solution feed samples, conservative assumptions for off gas partitioning of metals and organics, stack gas sampling for mercury, and conservative measurements of contaminant removal (decontamination factors) in the off gas treatment system. Stack emissions were modeled using the ISC3 air dispersion model to predict maximum particulate and vapor air concentrations and ground deposition rates. Results demonstrate that NWCF emissions calculated from best-available process knowledge would result in maximum onsite and offsite health and ecological impacts that are less then EPA-established criteria for operation of a combustion facility.« less

  2. 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

    USGS Publications Warehouse

    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.

  3. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.

    The United States Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticalitymore » during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).« less

  4. Removal of Cesium From Acidic Radioactive Tank Waste Using IONSIV IE-911 (CST)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mann, Nicholas Robert; Todd, Terry Allen

    2004-10-01

    IONSIV IE-911, or the engineered form of crystalline silicotitanate (CST), manufactured by UOP Molecular Sieves, has been evaluated for the removal of cesium from Idaho National Engineering and Environmental Laboratory (INEEL) acidic radioactive tank waste. A series of batch contacts and column tests were performed by using three separate batches of CST. Batch contacts were performed to evaluate the concentration effects of nitric acid, sodium, and potassium ions on cesium sorption. Additional batch tests were performed to determine if americium, mercury, and plutonium would sorb onto IONSIV IE-911. An equilibrium isotherm was generated by using a concentrated tank waste simulant.more » Column tests using a 1.5 cm 3 column and flow rates of 3, 5, 10, 20, and 30 bed volumes (BV)/hr were performed to elucidate dynamic cesium sorption capacities and sorption kinetics. Additional experiments investigated the effect of CST batch and pretreatment on cesium sorption. The thermal stability of IONSIV IE-911 was evaluated by performing thermal gravimetric analysis/differential thermal analysis. Overall, IONSIV IE-911 was shown to be effective for cesium sorption from complex, highly acidic solutions; however, sorbent stability in these solutions may have a deleterious effect on cesium sorption.« less

  5. Laboratory-Scale Column Testing Using IONSIV IE-911 for Removing Cesium from Acidic Tank Waste Simulant. 1: Cesium Exchange Capacity of a 15-cm3 Column and Dynamic Stability of the Exchange Media

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    T.J. Tranter; R.D. Tillotson; T.A. Todd

    2005-04-01

    Bench-scale column tests were performed using a commercial form of crystalline silicotitanate (CST) for removing radio-cesium from a surrogate acidic tank solution representative of liquid waste stored at the Idaho National Engineering and Environmental Laboratory (INEEL). An engineered form of CST ion exchanger, known as IONSIVtm IE-911 (UOP, Mt Laurel, NJ, USA), was tested in 15 cm3 columns at a flow rate of 5 bed volumes per hour. These experiments showed the ion exchange material to have reasonable selectivity and capacity for removing cesium from the complex chemical matrix of the solution. However, previous testing indicated that partial neutralization ofmore » the feed stream was necessary to increase the stability of the ion exchange media. Thus, in these studies, CST degradation was determined as a function of throughput in order to better assess the stability characteristics of the exchanger for potential future waste treatment applications. Results of these tests indicate that the degradation of the CST reaches a maximum very soon after the acidic feed is introduced to the column and then rapidly declines. Total dissolution of bed material did not exceed 3% under the experimental regime used.« less

  6. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.

    1998-10-01

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality duringmore » the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).« less

  7. Laboratory-Scale Column Testing Using IONSIV IE-911 for Removing Cesium from Acidic Tank Waste Simulant. 2: Determination of Cesium Exchange Capacity and Effective Mass Transfer Coefficient from a 500-cm3 Column Experiement

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    T.J. Tranter; R.D. Tillotson; T.A. Todd

    2005-04-01

    A semi-scale column test was performed using a commercial form of crystalline silicotitanate (CST) for removing radio-cesium from a surrogate acidic tank solution, which represents liquid waste stored at the Idaho National Engineering and Environmental Laboratory (INEEL). The engineered form of CST ion exchanger, known as IONSIVtmIE-911 (UOP, Mt. Laurel,NJ, USA), was tested in a 500-cm3 column to obtain a cesium breakthrough curve. The cesium exchange capacity of this column matched that obtained from previous testing with a 15-mc3 column. A numerical algorithm using implicit finite difference approximations was developed to solve the governing mass transport equations for the CSTmore » columns. An effective mass transfer coefficient was derived from solving these equations for previously reported 15 cm3 tests. The effective mass transfer coefficient was then used to predict the cesium breakthrough curve for the 500-cm3 column and compared to the experimental data reported in this paper. The calculated breakthrough curve showed excellent agreement with the data from the 500-cm3 column even though the interstitial velocity was a factor of two greater. Thus, this approach should provide a reasonable method for scale up to larger columns for treating actual tank waste.« less

  8. Detection and classification of concealed weapons using a magnetometer-based portal

    NASA Astrophysics Data System (ADS)

    Kotter, Dale K.; Roybal, Lyle G.; Polk, Robert E.

    2002-08-01

    A concealed weapons detection technology was developed through the support of the National Institute of Justice (NIJ) to provide a non intrusive means for rapid detection, location, and archiving of data (including visual) of potential suspects and weapon threats. This technology, developed by the Idaho National Engineering and Environmental Laboratory (INEEL), has been applied in a portal style weapons detection system using passive magnetic sensors as its basis. This paper will report on enhancements to the weapon detection system to enable weapon classification and to discriminate threats from non-threats. Advanced signal processing algorithms were used to analyze the magnetic spectrum generated when a person passes through a portal. These algorithms analyzed multiple variables including variance in the magnetic signature from random weapon placement and/or orientation. They perform pattern recognition and calculate the probability that the collected magnetic signature correlates to a known database of weapon versus non-weapon responses. Neural networks were used to further discriminate weapon type and identify controlled electronic items such as cell phones and pagers. False alarms were further reduced by analyzing the magnetic detector response by using a Joint Time Frequency Analysis digital signal processing technique. The frequency components and power spectrum for a given sensor response were derived. This unique fingerprint provided additional information to aid in signal analysis. This technology has the potential to produce major improvements in weapon detection and classification.

  9. Irradiation of Microbes from Spent Nuclear Fuel Storage Pool Environments

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Breckenridge, C.R.; Watkins, C.S.; Bruhn, D.F.

    Microbes have been isolated and identified from spent nuclear fuel storage pools at the Idaho National Engineering and Environmental Laboratory (INEEL). Included among these are Corynebacterium aquaticum, Pseudomonas putida, Comamonas acidovorans, Gluconobacter cerinus, Micrococcus diversus, Rhodococcus rhodochrous, and two strains of sulfate-reducing bacteria (SRB). We examined the sensitivity of these microbes to a variety of total exposures of radiation generated by a 6-MeV linear accelerator (LINAC). The advantage of using a LINAC is that it provides a relatively quick screen of radiation tolerance. In the first set of experiments, we exposed each of the aforementioned microbes along with four additionalmore » microbes, pseudomonas aeruginosa, Micrococcus luteus, Escherchia coli, and Deinococcus radiodurans to exposures of 5 x 10{sup 3} and 6 x 10{sup 4} rad. All microbial specimens withstood the lower exposure with little or no reduction in cell population. Upon exposing the microbes to the larger dose of 6 x 10{sup 4} rad, we observed two distinct groupings: microbes that demonstrate resistance to radiation, and microbes that display intolerance through a dramatic reduction from their initial population. Microbes in the radiation tolerant grouping were exposed to 1.1 x 10{sup 5} rad to examine the extent of their resistance. We observe a correlation between radiation resistance and gram stain. The gram-positive species we examined seem to demonstrate a greater radiation resistance.« less

  10. Multi-Megawatt Power System Trade Study

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Longhurst, Glen Reed; Schnitzler, Bruce Gordon; Parks, Benjamin Travis

    2001-11-01

    As part of a larger task, the Idaho National Engineering and Environmental Laboratory (INEEL) was tasked to perform a trade study comparing liquid-metal cooled reactors having Rankine power conversion systems with gas-cooled reactors having Brayton power conversion systems. This report summarizes the approach, the methodology, and the results of that trade study. Findings suggest that either approach has the possibility to approach the target specific mass of 3-5 kg/kWe for the power system, though it appears either will require improvements to achieve that. Higher reactor temperatures have the most potential for reducing the specific mass of gas-cooled reactors but domore » not necessarily have a similar effect for liquid-cooled Rankine systems. Fuels development will be the key to higher reactor operating temperatures. Higher temperature turbines will be important for Brayton systems. Both replacing lithium coolant in the primary circuit with gallium and replacing potassium with sodium in the power loop for liquid systems increase system specific mass. Changing the feed pump turbine to an electric motor in Rankine systems has little effect. Key technologies in reducing specific mass are high reactor and radiator operating temperatures, low radiator areal density, and low turbine/generator system masses. Turbine/generator mass tends to dominate overall power system mass for Rankine systems. Radiator mass was dominant for Brayton systems.« less

  11. Feasibility study for early removal of HEU from CPP-651-Phase II

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Smith, C.V.; Henry, R.; Milligan, C.

    1997-09-01

    A two-phase feasibility study was initiated in late 1996 to identify a way to expedite the removal of SNM from the CPP-651 vault. The first phase of this study provided preliminary information that appeared promising, but needed additional detailed planning and evaluate to validate the concepts and conclusions. The focus of Phase 2 was to provide the validation via resource-loaded schedules and more detailed cost estimates. Section 1 describes the purpose and objectives of the Phase 2 tasks and the programmatic drivers that influence related CPP-651 high-enriched uranium (HEU) management issues. Section 2 identifies the evaluation criteria and methodology andmore » the transfer issues and barriers preventing shipment. Section 3 provides site-specific background information for the CPP-651 facility and the Idaho National Engineering and Environmental Laboratory (INEEL) and describes the development of the basic material removal schedule, the proposed base case plan for removal of SNM, and the proposed HEU material management/shipping issues and strategies. Section 4 identifies the proposed options for accelerated removal of SNM and how they were evaluated via detailed scheduling, resource histograms, and cost analysis. Section 5 summarizes principal tasks for implementing this plan and other related HEU CPP-651 management issues that require continued planning efforts to assure successful implementation of this proposed early removal strategy.« less

  12. Geochemistry of the Birch Creek Drainage Basin, Idaho

    USGS Publications Warehouse

    Swanson, Shawn A.; Rosentreter, Jeffrey J.; Bartholomay, Roy C.; Knobel, LeRoy L.

    2003-01-01

    The U.S. Survey and Idaho State University, in cooperation with the U.S. Department of Energy, are conducting studies to describe the chemical character of ground water that moves as underflow from drainage basins into the eastern Snake River Plain aquifer (ESRPA) system at and near the Idaho National Engineering and Environmental Laboratory (INEEL) and the effects of these recharge waters on the geochemistry of the ESRPA system. Each of these recharge waters has a hydrochemical character related to geochemical processes, especially water-rock interactions, that occur during migration to the ESRPA. Results of these studies will benefit ongoing and planned geochemical modeling of the ESRPA at the INEEL by providing model input on the hydrochemical character of water from each drainage basin. During 2000, water samples were collected from five wells and one surface-water site in the Birch Creek drainage basin and analyzed for selected inorganic constituents, nutrients, dissolved organic carbon, tritium, measurements of gross alpha and beta radioactivity, and stable isotopes. Four duplicate samples also were collected for quality assurance. Results, which include analyses of samples previously collected from four other sites, in the basin, show that most water from the Birch Creek drainage basin has a calcium-magnesium bicarbonate character. The Birch Creek Valley can be divided roughly into three hydrologic areas. In the northern part, ground water is forced to the surface by a basalt barrier and the sampling sites were either surface water or shallow wells. Water chemistry in this area was characterized by simple evaporation models, simple calcite-carbon dioxide models, or complex models involving carbonate and silicate minerals. The central part of the valley is filled by sedimentary material and the sampling sites were wells that are deeper than those in the northern part. Water chemistry in this area was characterized by simple calcite-dolomite-carbon dioxide models. In the southern part, ground water enters the ESRPA. In this area, the sampling sites were wells with depths and water levels much deeper than those in the northern and central parts of the valley. The calcium and carbon water chemistry in this area was characterized by a simple calcite-carbon dioxide model, but complex calcite-silicate models more accurately accounted for mass transfer in these areas. Throughout the geochemical system, calcite precipitated if it was an active phase in the models. Carbon dioxide either precipitated (outgassed) or dissolved depending on the partial pressure of carbon dioxide in water from the modeled sites. Dolomite was an active phase only in models from the central part of the system. Generally the entire geochemical system could be modeled with either evaporative models, carbonate models, or carbonate-silicate models. In both of the latter types of models, a significant amount of calcite precipitated relative to the mass transfer to and from the other active phases. The amount of calcite precipitated in the more complex models was consistent with the amount of calcite precipitated in the simpler models. This consistency suggests that, although the simpler models can predict calcium and carbon concentrations in Birch Creek Valley ground and surface water, silicate-mineral-based models are required to account for the other constituents. The amount of mass transfer to and from the silicate mineral phases was generally small compared with that in the carbonate phases. It appears that the water chemistry of well USGS 126B represents the chemistry of water recharging the ESRPA by means of underflow from the Birch Creek Valley.

  13. Biogeochemistry and Spatial Distribution of the Microbial-Mineral Interface Using I2LD-FTMS

    NASA Astrophysics Data System (ADS)

    Scott, J. R.; Kauffman, M. E.; Kauffman, M. E.; Tremblay, P. L.

    2001-12-01

    Previous studies indicate that biogeochemistry can vary within individual mineral specimens in contact with microorganisms. These same studies have shown that microcosms containing a mixture of minerals simulating a heterogeneous geologic matrix do not yield the same results as the naturally occurring rock. Therefore, it is of utmost importance to develop analytical tools that can provide spatially correlative biogeochemical data of the microbial-mineral interface within naturally occurring geologic matrices. Imaging internal laser desorption Fourier transform mass spectrometry (I2LD-FTMS) can provide elemental and molecular information of the microbial-mineral interface at a spatial resolution limited only by the optical diffraction limit of the final focusing lens (down to 2 μ m). Additionally, the I2LD-FTMS used in this study has exceptional reproducibility, which can provide successive mapping sequences for depth-profiling studies. Basalt core samples, taken from the Snake River Plain Aquifer in southeastern Idaho, were mapped prior to, and after, exposure to a bacterial culture. The bacteria-basalt interface spectra were collected using the I2LD-FTMS at the INEEL. Mass spectra were recorded over a mass-to-charge range of 30-2500 Da with an average peak resolution of 15,000 using 10 μ m spots. Two-dimensional maps were constructed depicting the spatial distribution of the minerals within the basalt as well as the spatial distribution of the bacteria on the basalt surface. This represents the first reported application of I2LD-FTMS in the field of biogeochemistry.

  14. Hardening neutron spectrum for advanced actinide transmutation experiments in the ATR.

    PubMed

    Chang, G S; Ambrosek, R G

    2005-01-01

    The most effective method for transmuting long-lived isotopes contained in spent nuclear fuel into shorter-lived fission products is in a fast neutron spectrum reactor. In the absence of a fast test reactor in the United States, initial irradiation testing of candidate fuels can be performed in a thermal test reactor that has been modified to produce a test region with a hardened neutron spectrum. Such a test facility, with a spectrum similar but somewhat softer than that of the liquid-metal fast breeder reactor (LMFBR), has been constructed in the INEEL's Advanced Test Reactor (ATR). The radial fission power distribution of the actinide fuel pin, which is an important parameter in fission gas release modelling, needs to be accurately predicted and the hardened neutron spectrum in the ATR and the LMFBR fast neutron spectrum is compared. The comparison analyses in this study are performed using MCWO, a well-developed tool that couples the Monte Carlo transport code MCNP with the isotope depletion and build-up code ORIGEN-2. MCWO analysis yields time-dependent and neutron-spectrum-dependent minor actinide and Pu concentrations and detailed radial fission power profile calculations for a typical fast reactor (LMFBR) neutron spectrum and the hardened neutron spectrum test region in the ATR. The MCWO-calculated results indicate that the cadmium basket used in the advanced fuel test assembly in the ATR can effectively depress the linear heat generation rate in the experimental fuels and harden the neutron spectrum in the test region.

  15. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRAmore » regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.« less

  16. RH-TRU Waste Characterization by Acceptable Knowledge at the Idaho National Engineering and Environmental Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schulz, C.; Givens, C.; Bhatt, R.

    2003-02-24

    Idaho National Engineering and Environmental Laboratory (INEEL) is conducting an effort to characterize approximately 620 drums of remote-handled (RH-) transuranic (TRU) waste currently in its inventory that were generated at the Argonne National Laboratory-East (ANL-E) Alpha Gamma Hot Cell Facility (AGHCF) between 1971 and 1995. The waste was generated at the AGHCF during the destructive examination of irradiated and unirradiated fuel pins, targets, and other materials from reactor programs at ANL-West (ANL-W) and other Department of Energy (DOE) reactors. In support of this effort, Shaw Environmental and Infrastructure (formerly IT Corporation) developed an acceptable knowledge (AK) collection and management programmore » based on existing contact-handled (CH)-TRU waste program requirements and proposed RH-TRU waste program requirements in effect in July 2001. Consistent with Attachments B-B6 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) and th e proposed Class 3 permit modification (Attachment R [RH-WAP] of this permit), the draft AK Summary Report prepared under the AK procedure describes the waste generating process and includes determinations in the following areas based on AK: physical form (currently identified at the Waste Matrix Code level); waste stream delineation; applicability of hazardous waste numbers for hazardous waste constituents; and prohibited items. In addition, the procedure requires and the draft summary report contains information supporting determinations in the areas of defense relationship and radiological characterization.« less

  17. Proposal for Creating a Pocket of Innovation and Adaptability Within a Bureaucratic Enterprise

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nichols, T. T.; Millet, C. B.

    2001-07-02

    A conceptual framework is developed that is based on a behavioral model for organizations that rely upon innovation and adaptability for their survival in the market place. The model supports the assertion that change efforts aimed at performance improvement need a systems approach because contributions to an organization's performance cross functional lines and are systemic in nature. The model implies four conclusions for a unit trying to effectuate change within a greater bureaucracy. First, the desired behaviors are currently neither evaluated nor rewarded enough by either the enterprise or the local unit. Second, the model has to be applied tomore » the local unit, treating the unit as a distinct enterprise itself. Third, a misalignment between the unit's new form and that of the rest of the enterprise will invariably be created. Fourth, this misalignment has to be minimized enough by the local unit to avoid the larger enterprise from responding negatively to the change effort. The mode l results in a change approach that constrains localized behavior modification by the need to remain aligned with the overall structure of the complete enterprise. The conceptual framework is used to develop a proposal for effectuating behavioral change within the High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL). A ''strawman'' involving a set of critical systems, performance and evaluation measures, and tactics is presented as a starting point for further discussion and development within the Program organization.« less

  18. Proposal for Creating a Pocket of Innovation & Adaptability within a Bureaucratic Enterprise

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nichols, Todd Travis; Millet, C. D.

    2001-07-01

    A conceptual framework is developed that is based on a behavioral model for organizations that rely upon innovation and adaptability for their survival in the market place. The model supports the assertion that change efforts aimed at performance improvement need a systems approach because contributions to an organization's performance cross functional lines and are systemic in nature. The model implies four conclusions for a unit trying to effectuate change within a greater bureaucracy. First, the desired behaviors are currently neither evaluated nor rewarded enough by either the enterprise or the local unit. Second, the model has to be applied tomore » the local unit, treating the unit as a distinct enterprise itself. Third, a misalignment between the unit's new form and that of the rest of the enterprise will invariably be created. Fourth, this misalignment has to be minimized enough by the local unit to avoid the larger enterprise from responding negatively to the change effort. The model results in a change approach that constrains localized behavior modification by the need to remain aligned with the overall structure of the complete enterprise. The conceptual framework is used to develop a proposal for effectuating behavioral change within the High-Level Waste (HLW) Program at the Idaho National Engineering and Environmental Laboratory (INEEL). A "strawman" involving a set of critical systems, performance and evaluation measures, and tactics is presented as a starting point for further discussion and development within the Program organization.« less

  19. Mapping of explosive contamination using GC/chemiluminescence and ion mobility spectrometry techniques

    NASA Astrophysics Data System (ADS)

    Miller, Carla J.; Glenn, D. F.; Hartenstein, Steven D.; Hallowell, Susan F.

    1998-12-01

    Recent efforts at the Idaho National Engineering and Environmental Laboratory (INEEL) have included mapping explosive contamination resulting from manufacturing and carrying improvised explosive devices (IEDs). Two types of trace detection equipment were used to determine levels of contamination from designated sampling areas. A total of twenty IEDs were constructed: ten using TNT and ten using C-4. Two test scenarios were used. The first scenario tracked the activities of a manufacturer who straps the device onto an independent courier. The courier then performed a series of activities to simulate waiting in an airport. The second scenario tracked the activities of a manufacturer who also served as the courier. A sample set for each test consisted of thirty samples from various locations on each IED manufacturer, thirty from each IED courier, twenty-five from the manufacturing area, and twenty-five from the courier area. Pre-samples and post-samples were collected for analysis with each detection technique. Samples analyzed by gc/chemiluminescence were taken by swiping a teflon- coated sampling swipe across the surface of the sampling area to pick up any explosive particles. Samples analyzed by ion mobility spectrometry (IMS) were taken from the clothing of the manufacturer and courier by vacuuming the surface and collecting particulates on a fiberglass filter. Samples for IMS analysis from the manufacturing and courier rooms were taken by wiping a cotton sampling swipe across the surface area. Currently, building IEDs and monitoring the explosive contamination is being directed toward detection with portal monitors.

  20. Five Kilowatt Solid Oxide Fuel Cell/Diesel Reformer

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dennis Witmer; Thomas Johnson

    2008-12-31

    Reducing fossil fuel consumption both for energy security and for reduction in global greenhouse emissions has been a major goal of energy research in the US for many years. Fuel cells have been proposed as a technology that can address both these issues--as devices that convert the energy of a fuel directly into electrical energy, they offer low emissions and high efficiencies. These advantages are of particular interest to remote power users, where grid connected power is unavailable, and most electrical power comes from diesel electric generators. Diesel fuel is the fuel of choice because it can be easily transportedmore » and stored in quantities large enough to supply energy for small communities for extended periods of time. This projected aimed to demonstrate the operation of a solid oxide fuel cell on diesel fuel, and to measure the resulting efficiency. Results from this project have been somewhat encouraging, with a laboratory breadboard integration of a small scale diesel reformer and a Solid Oxide Fuel Cell demonstrated in the first 18 months of the project. This initial demonstration was conducted at INEEL in the spring of 2005 using a small scale diesel reformer provided by SOFCo and a fuel cell provided by Acumentrics. However, attempts to integrate and automate the available technology have not proved successful as yet. This is due both to the lack of movement on the fuel processing side as well as the rather poor stack lifetimes exhibited by the fuel cells. Commercial product is still unavailable, and precommercial devices are both extremely expensive and require extensive field support.« less

  1. Chemiresistor microsensors for in-situ monitoring of volatile organic compounds : final LDRD report.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Thomas, Michael Loren; Hughes, Robert Clark; Kooser, Ara S.

    2003-09-01

    This report provides a summary of the three-year LDRD (Laboratory Directed Research and Development) project aimed at developing microchemical sensors for continuous, in-situ monitoring of volatile organic compounds. A chemiresistor sensor array was integrated with a unique, waterproof housing that allows the sensors to be operated in a variety of media including air, soil, and water. Numerous tests were performed to evaluate and improve the sensitivity, stability, and discriminatory capabilities of the chemiresistors. Field tests were conducted in California, Nevada, and New Mexico to further test and develop the sensors in actual environments within integrated monitoring systems. The field testsmore » addressed issues regarding data acquisition, telemetry, power requirements, data processing, and other engineering requirements. Significant advances were made in the areas of polymer optimization, packaging, data analysis, discrimination, design, and information dissemination (e.g., real-time web posting of data; see www.sandia.gov/sensor). This project has stimulated significant interest among commercial and academic institutions. A CRADA (Cooperative Research and Development Agreement) was initiated in FY03 to investigate manufacturing methods, and a Work for Others contract was established between Sandia and Edwards Air Force Base for FY02-FY04. Funding was also obtained from DOE as part of their Advanced Monitoring Systems Initiative program from FY01 to FY03, and a DOE EMSP contract was awarded jointly to Sandia and INEEL for FY04-FY06. Contracts were also established for collaborative research with Brigham Young University to further evaluate, understand, and improve the performance of the chemiresistor sensors.« less

  2. INEEL Cultural Resource Management Program Annual Report - 2004

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Clayton F. Marler

    2005-01-01

    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 Idaho National Engineering and Environmental Laboratory Site is located in southeastern Idaho, and is home to vast numbersmore » and a wide variety of important cultural resources representing at least 13,000-year span of human occupation in the region. 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 resources with the management and ongoing operation of an active scientific laboratory, while also cleaning up the waste left by past programs and processes. The Department of Energy Idaho Operations Office has administrative responsibility for most of the Site, excluding lands and resources managed by the Naval Reactors Facility and (in 2004) Argonne National Laboratory-West. The Department of Energy is committed to a cultural resource program that accepts these challenges in a manner reflecting both the spirit and intent of the legislative requirements. This annual report is an overview of Cultural Resource Management Program activities conducted during Fiscal Year 2004 and is intended to be both informative to external stakeholders and to serve as a planning tool for future cultural resource management work to be conducted on the Site.« less

  3. FRamework Assessing Notorious Contributing Influences for Error (FRANCIE): Perspective on Taxonomy Development to Support Error Reporting and Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lon N. Haney; David I. Gertman

    2003-04-01

    Beginning in the 1980s a primary focus of human reliability analysis was estimation of human error probabilities. However, detailed qualitative modeling with comprehensive representation of contextual variables often was lacking. This was likely due to the lack of comprehensive error and performance shaping factor taxonomies, and the limited data available on observed error rates and their relationship to specific contextual variables. In the mid 90s Boeing, America West Airlines, NASA Ames Research Center and INEEL partnered in a NASA sponsored Advanced Concepts grant to: assess the state of the art in human error analysis, identify future needs for human errormore » analysis, and develop an approach addressing these needs. Identified needs included the need for a method to identify and prioritize task and contextual characteristics affecting human reliability. Other needs identified included developing comprehensive taxonomies to support detailed qualitative modeling and to structure meaningful data collection efforts across domains. A result was the development of the FRamework Assessing Notorious Contributing Influences for Error (FRANCIE) with a taxonomy for airline maintenance tasks. The assignment of performance shaping factors to generic errors by experts proved to be valuable to qualitative modeling. Performance shaping factors and error types from such detailed approaches can be used to structure error reporting schemes. In a recent NASA Advanced Human Support Technology grant FRANCIE was refined, and two new taxonomies for use on space missions were developed. The development, sharing, and use of error taxonomies, and the refinement of approaches for increased fidelity of qualitative modeling is offered as a means to help direct useful data collection strategies.« less

  4. An empirical approach to inversion of an unconventional helicopter electromagnetic dataset

    USGS Publications Warehouse

    Pellerin, L.; Labson, V.F.

    2003-01-01

    A helicopter electromagnetic (HEM) survey acquired at the U.S. Idaho National Engineering and Environmental Laboratory (INEEL) used a modification of a traditional mining airborne method flown at low levels for detailed characterization of shallow waste sites. The low sensor height, used to increase resolution, invalidates standard assumptions used in processing HEM data. Although the survey design strategy was sound, traditional interpretation techniques, routinely used in industry, proved ineffective. Processed data and apparent resistivity maps were severely distorted, and hence unusable, due to low flight height effects, high magnetic permeability of the basalt host, and the conductive, three-dimensional nature of the waste site targets.To accommodate these interpretation challenges, we modified a one-dimensional inversion routine to include a linear term in the objective function that allows for the magnetic and three-dimensional electromagnetic responses in the in-phase data. Although somewhat ad hoc, the use of this term in the inverse routine, referred to as the shift factor, was successful in defining the waste sites and reducing noise due to the low flight height and magnetic characteristics of the host rock. Many inversion scenarios were applied to the data and careful analysis was necessary to determine the parameters appropriate for interpretation, hence the approach was empirical. Data from three areas were processed with this scheme to highlight different interpretational aspects of the method. Wastes sites were delineated with the shift terms in two of the areas, allowing for separation of the anthropomorphic targets from the natural one-dimensional host. In the third area, the estimated resistivity and the shift factor were used for geological mapping. The high magnetic content of the native soil enabled the mapping of disturbed soil with the shift term. Published by Elsevier Science B.V.

  5. Automated baseline change detection -- Phases 1 and 2. Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Byler, E.

    1997-10-31

    The primary objective of this project is to apply robotic and optical sensor technology to the operational inspection of mixed toxic and radioactive waste stored in barrels, using Automated Baseline Change Detection (ABCD), based on image subtraction. Absolute change detection is based on detecting any visible physical changes, regardless of cause, between a current inspection image of a barrel and an archived baseline image of the same barrel. Thus, in addition to rust, the ABCD system can also detect corrosion, leaks, dents, and bulges. The ABCD approach and method rely on precise camera positioning and repositioning relative to the barrelmore » and on feature recognition in images. The ABCD image processing software was installed on a robotic vehicle developed under a related DOE/FETC contract DE-AC21-92MC29112 Intelligent Mobile Sensor System (IMSS) and integrated with the electronics and software. This vehicle was designed especially to navigate in DOE Waste Storage Facilities. Initial system testing was performed at Fernald in June 1996. After some further development and more extensive integration the prototype integrated system was installed and tested at the Radioactive Waste Management Facility (RWMC) at INEEL beginning in April 1997 through the present (November 1997). The integrated system, composed of ABCD imaging software and IMSS mobility base, is called MISS EVE (Mobile Intelligent Sensor System--Environmental Validation Expert). Evaluation of the integrated system in RWMC Building 628, containing approximately 10,000 drums, demonstrated an easy to use system with the ability to properly navigate through the facility, image all the defined drums, and process the results into a report delivered to the operator on a GUI interface and on hard copy. Further work is needed to make the brassboard system more operationally robust.« less

  6. Northern Cheyenne Reservation Coal Bed Natural Resource Assessment and Analysis of Produced Water Disposal Options

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Shaochang Wo; David A. Lopez; Jason Whiteman Sr.

    Coalbed methane (CBM) development in the Powder River Basin (PRB) is currently one of the most active gas plays in the United States. Monthly production in 2002 reached about 26 BCF in the Wyoming portion of the basin. Coalbed methane reserves for the Wyoming portion of the basin are approximately 25 trillion cubic feet (TCF). Although coal beds in the Powder River Basin extend well into Montana, including the area of the Northern Cheyenne Indian Reservation, the only CBM development in Montana is the CX Field, operated by the Fidelity Exploration, near the Wyoming border. The Northern Cheyenne Reservation ismore » located on the northwest flank of the PRB in Montana with a total land of 445,000 acres. The Reservation consists of five districts, Lame Deer, Busby, Ashland, Birney, and Muddy Cluster and has a population of 4,470 according to the 2000 Census. The CBM resource represents a significant potential asset to the Northern Cheyenne Indian Tribe. Methane gas in coal beds is trapped by hydrodynamic pressure. Because the production of CBM involves the dewatering of coalbed to allow the release of methane gas from the coal matrix, the relatively large volume of the co-produced water and its potential environmental impacts are the primary concerns for the Tribe. Presented in this report is a study conducted by the Idaho National Engineering and Environmental Laboratory (INEEL) and the Montana Bureau of Mines and Geology (MBMG) in partnership with the Northern Cheyenne Tribe to assess the Tribe’s CBM resources and evaluate applicable water handling options. The project was supported by the U.S. Department of Energy (DOE) through the Native American Initiative of the National Petroleum Technology Office, under contract DEAC07- 99ID13727. Matching funds were granted by the MBMG in supporting the work of geologic study and mapping conducted at MBMG.« less

  7. Mercury deposition in snow near an industrial emission source in the western U.S. and comparison to ISC3 model predictions

    USGS Publications Warehouse

    Abbott, M.L.; Susong, D.D.; Krabbenhoft, D.P.; Rood, A.S.

    2002-01-01

    Mercury (total and methyl) was evaluated in snow samples collected near a major mercury emission source on the Idaho National Engineering and Environmental Laboratory (INEEL) in southeastern Idaho and 160 km downwind in Teton Range in western Wyoming. The sampling was done to assess near-field (<12 km) deposition rates around the source, compare them to those measured in a relatively remote, pristine downwind location, and to use the measurements to develop improved, site-specific model input parameters for precipitation scavenging coefficient and the fraction of Hg emissions deposited locally. Measured snow water concentrations (ng L-1) were converted to deposition (ug m-2) using the sample location snow water equivalent. The deposition was then compared to that predicted using the ISC3 air dispersion/deposition model which was run with a range of particle and vapor scavenging coefficient input values. Accepted model statistical performance measures (fractional bias and normalized mean square error) were calculated for the different modeling runs, and the best model performance was selected. Measured concentrations close to the source (average = 5.3 ng L-1) were about twice those measured in the Teton Range (average = 2.7 ng L-1) which were within the expected range of values for remote background areas. For most of the sampling locations, the ISC3 model predicted within a factor of two of the observed deposition. The best modeling performance was obtained using a scavenging coefficient value for 0.25 ??m diameter particulate and the assumption that all of the mercury is reactive Hg(II) and subject to local deposition. A 0.1 ??m particle assumption provided conservative overprediction of the data, while a vapor assumption resulted in highly variable predictions. Partitioning a fraction of the Hg emissions to elemental Hg(0) (a U.S. EPA default assumption for combustion facility risk assessments) would have underpredicted the observed fallout.

  8. Operating Experience and Lessons Learned in the Use of Soft-Sided Packaging for Transportation and Disposal of Low Activity Radioactive Waste

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kapoor, A.; Gordon, S.; Goldston, W.

    2013-07-08

    This paper describes the operating experience and lessons learned at U.S. Department of Energy (DOE) sites as a result of an evaluation of potential trailer contamination and soft-sided packaging integrity issues related to the disposal of low-level and mixed low-level (LLW/MLLW) radioactive waste shipments. Nearly 4.3 million cubic meters of LLW/MLLW will have been generated and disposed of during fiscal year (FY) 2010 to FY 2015—either at commercial disposal sites or disposal sites owned by DOE. The LLW/MLLW is packaged in several different types of regulatory compliant packaging and transported via highway or rail to disposal sites safely and efficientlymore » in accordance with federal, state, and local regulations and DOE orders. In 1999, DOE supported the development of LLW containers that are more volumetrically efficient, more cost effective, and easier to use as compared to metal or wooden containers that existed at that time. The DOE Idaho National Engineering and Environmental Laboratory (INEEL), working in conjunction with the plastic industry, tested several types of soft-sided waste packaging systems that meet U.S. Department of Transportation requirements for transport of low specific activity and surface contaminated objects. Since then, soft-sided packaging of various capacities have been used successfully by the decontamination and decommissioning (D&D) projects to package, transport, and dispose D&D wastes throughout the DOE complex. The joint team of experts assembled by the Energy Facility Contractors Group from DOE waste generating sites, DOE and commercial waste disposal facilities, and soft-sided packaging suppliers conducted the review of soft-sided packaging operations and transportation of these packages to the disposal sites. As a result of this evaluation, the team developed several recommendations and best practices to prevent or minimize the recurrences of equipment contamination issues and proper use of soft-sided packaging for transport and disposal of waste.« less

  9. Review of the Need for a Large-scale Test Facility for Research on the Effects of Extreme Winds on Structures

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    R. G. Little

    1999-03-01

    The Idaho National Engineering and Environmental Laboratory (INEEL), through the US Department of Energy (DOE), has proposed that a large-scale wind test facility (LSWTF) be constructed to study, in full-scale, the behavior of low-rise structures under simulated extreme wind conditions. To determine the need for, and potential benefits of, such a facility, the Idaho Operations Office of the DOE requested that the National Research Council (NRC) perform an independent assessment of the role and potential value of an LSWTF in the overall context of wind engineering research. The NRC established the Committee to Review the Need for a Large-scale Testmore » Facility for Research on the Effects of Extreme Winds on Structures, under the auspices of the Board on Infrastructure and the Constructed Environment, to perform this assessment. This report conveys the results of the committee's deliberations as well as its findings and recommendations. Data developed at large-scale would enhanced the understanding of how structures, particularly light-frame structures, are affected by extreme winds (e.g., hurricanes, tornadoes, sever thunderstorms, and other events). With a large-scale wind test facility, full-sized structures, such as site-built or manufactured housing and small commercial or industrial buildings, could be tested under a range of wind conditions in a controlled, repeatable environment. At this time, the US has no facility specifically constructed for this purpose. During the course of this study, the committee was confronted by three difficult questions: (1) does the lack of a facility equate to a need for the facility? (2) is need alone sufficient justification for the construction of a facility? and (3) would the benefits derived from information produced in an LSWTF justify the costs of producing that information? The committee's evaluation of the need and justification for an LSWTF was shaped by these realities.« less

  10. Modelling deuterium release during thermal desorption of D +-irradiated tungsten

    NASA Astrophysics Data System (ADS)

    Poon, M.; Haasz, A. A.; Davis, J. W.

    2008-03-01

    Thermal desorption profiles were modelled based on SIMS measurements of implantation profiles and using the multi-trap diffusion code TMAP7 [G.R. Longhurst, TMAP7: Tritium Migration Analysis Program, User Manual, Idaho National Laboratory, INEEL/EXT-04-02352 (2004)]. The thermal desorption profiles were the result of 500 eV/D + irradiations on single crystal tungsten at 300 and 500 K to fluences of 10 22-10 24 D +/m 2. SIMS depth profiling was performed after irradiation to obtain the distribution of trapped D within the top 60 nm of the surface. Thermal desorption spectroscopy (TDS) was performed subsequently to obtain desorption profiles and to extract the total trapped D inventory. The SIMS profiles were calibrated to give D concentrations. To account for the total trapped D inventory measured by TDS, SIMS depth distributions were used in the near-surface (surface to 30 nm), NRA measurements [V.Kh. Alimov, J. Roth, M. Mayer, J. Nucl. Mater. 337-339 (2005) 619] were used in the range 1-7 μm, and a linear drop in the D distribution was assumed in the intermediate sub-surface region (˜30 nm to 1 μm). Traps were assumed to be saturated so that the D distribution also represented the trap distribution. Three trap energies, 1.07 ± 0.03, 1.34 ± 0.03 and 2.1 ± 0.05 eV were required to model the 520, 640 and 900 K desorption peaks, respectively. The 1.34 and 1.07 eV traps correspond to trapping of a first and second D atom at a vacancy, respectively, while the 2.1 eV trap corresponds to atomic D trapping at a void. A fourth trap energy of 0.65 eV was used to fit the 400 K desorption peak observed by Quastel et al. [A.D. Quastel, J.W. Davis, A.A. Haasz, R.G. Macaulay-Newcombe, J. Nucl. Mater. 359 (2006) 8].

  11. Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    G. L. Sharp; R. T. McCracken

    The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzedmore » in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility.1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety basis. The need for a design basis reconstitution program for the ATR has been identified along with the use of sound configuration management principles in order to support safe and efficient facility operation.« less

  12. Development of a SREX Flowsheet for the Separation of Strontium from Dissolved INEEL Zirconium Calcine

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Law, Jack Douglas; Wood, David James; Todd, Terry Allen

    1999-02-01

    Laboratory experimentation has indicated that the SREX process is effective for partitioning 90 Sr from acidic radioactive waste solutions located at the Idaho Nuclear Technology and Engineering Center. These laboratory results were used to develop a flowsheet for countercurrent testing of the SREX process with dissolved pilot plant calcine. Testing was performed using 24 stages of 2-cm diameter centrifugal contactors which are installed in the Remote Analytical Laboratory hot cell. Dissolved Run #64 pilot plant calcine spiked with 85 Sr was used as feed solution for the testing. The flowsheet tested consisted of an extraction section (0.15 M 4',4'(5')-di-(tert-butylcyclohexo)-18-crown-6 andmore » 1.5 M TBP in Isopar-L.), a 1.0 M NaNO3 scrub section to remove extracted K from the SREX solvent, a 0.01 M HNO3 strip section for the removal of Sr from the SREX solvent, a 0.25 M Na2CO3 wash section to remove degradation products from the solvent, and a 0.1 M HNO3 rinse section. The behavior of 85 Sr, Na, K, Al, B, Ca, Cr, Fe, Ni, and Zr was evaluated. The described flowsheet successfully extracted 85 Sr from the dissolved pilot plant calcine with a removal efficiency of 99.6%. Distribution coefficients for 85 Sr ranged from 3.6 to 4.5 in the extraction section. With these distribution coefficients a removal efficiency of approximately >99.99% was expected. It was determined that the lower than expected removal efficiency can be attributed to a stage efficiency of only 60% in the extraction section. Extracted K was effectively scrubbed from the SREX solvent with the 1.0 M NaNO3 resulting in only 6.4% of the K in the HLW strip product. Sodium was not extracted from the dissolved calcine by the SREX solvent; however, the use of a 1.0 M NaNO3 scrub solution resulted in a Na concentration of 70 mg/L (12.3% of the feed concentration) in the HLW strip product. Al, B, Ca, Cr, Fe, Ni, and Zr were determined to be essentially inextractable.« less

  13. Development of a SREX flowsheet for the separation of strontium from dissolved INEEL zirconium calcine

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Law, J.D.; Wood, D.J.; Todd, T.A.

    1999-01-01

    Laboratory experimentation has indicated that the SREX process is effective for partitioning {sup 90}Sr from acidic radioactive waste solutions located at the Idaho Nuclear Technology and Engineering Center. These laboratory results were used to develop a flowsheet for countercurrent testing of the SREX process with dissolved pilot plant calcine. Testing was performed using 24 stages of 2-cm diameter centrifugal contactors which are installed in the Remote Analytical Laboratory hot cell. Dissolved Run No.64 pilot plant calcine spiked with {sup 85}Sr was used as feed solution for the testing. The flowsheet tested consisted of an extraction section (0.15 M 4{prime},4{prime}(5{prime})-di-(tert-butylcyclohexo)-18-crown-6 andmore » 1.5 M TBP in Isopar-L.), a 1.0 M NaNO{sub 3} scrub section to remove extracted K from the SREX solvent, a 0.01 M HNO{sub 3} strip section for the removal of Sr from the SREX solvent, a 0.25 M Na2CO{sub 3} wash section to remove degradation products from the solvent, and a 0.1 M HNO{sub 3} rinse section. The behavior of {sup 85}Sr, Na, K, Al, B, Ca, Cr, Fe, Ni, and Zr was evaluated. The described flowsheet successfully extracted {sup 85}Sr from the dissolved pilot plant calcine with a removal efficiency of 99.6%. Distribution coefficients for {sup 85}Sr ranged from 3.6 to 4.5 in the extraction section. With these distribution coefficients a removal efficiency of approximately >99.99% was expected. It was determined that the lower than expected removal efficiency can be attributed to a stage efficiency of only 60% in the extraction section. Extracted K was effectively scrubbed from the SREX solvent with the 1.0 M NaNO{sub 3} resulting in only 6.4% of the K in the HLW strip product. Sodium was not extracted from the dissolved calcine by the SREX solvent; however, the use of a 1.0 M NaNO{sub 3} scrub solution resulted in a Na concentration of 70 mg/L (12.3% of the feed concentration) in the HLW strip product. Al, B, Ca, Cr, Fe, Ni, and Zr were determined to be essentially inextractable.« less

  14. The Impact of Soil Sampling Errors on Variable Rate Fertilization

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    R. L. Hoskinson; R C. Rope; L G. Blackwood

    2004-07-01

    Variable rate fertilization of an agricultural field is done taking into account spatial variability in the soil’s characteristics. Most often, spatial variability in the soil’s fertility is the primary characteristic used to determine the differences in fertilizers applied from one point to the next. For several years the Idaho National Engineering and Environmental Laboratory (INEEL) has been developing a Decision Support System for Agriculture (DSS4Ag) to determine the economically optimum recipe of various fertilizers to apply at each site in a field, based on existing soil fertility at the site, predicted yield of the crop that would result (and amore » predicted harvest-time market price), and the current costs and compositions of the fertilizers to be applied. Typically, soil is sampled at selected points within a field, the soil samples are analyzed in a lab, and the lab-measured soil fertility of the point samples is used for spatial interpolation, in some statistical manner, to determine the soil fertility at all other points in the field. Then a decision tool determines the fertilizers to apply at each point. Our research was conducted to measure the impact on the variable rate fertilization recipe caused by variability in the measurement of the soil’s fertility at the sampling points. The variability could be laboratory analytical errors or errors from variation in the sample collection method. The results show that for many of the fertility parameters, laboratory measurement error variance exceeds the estimated variability of the fertility measure across grid locations. These errors resulted in DSS4Ag fertilizer recipe recommended application rates that differed by up to 138 pounds of urea per acre, with half the field differing by more than 57 pounds of urea per acre. For potash the difference in application rate was up to 895 pounds per acre and over half the field differed by more than 242 pounds of potash per acre. Urea and potash differences accounted for almost 87% of the cost difference. The sum of these differences could result in a $34 per acre cost difference for the fertilization. Because of these differences, better analysis or better sampling methods may need to be done, or more samples collected, to ensure that the soil measurements are truly representative of the field’s spatial variability.« less

  15. The VIPER project (Visualization Integration Platform for Exploration Research): a biologically inspired autonomous reconfigurable robotic platform for diverse unstructured environments

    NASA Astrophysics Data System (ADS)

    Schubert, Oliver J.; Tolle, Charles R.

    2004-09-01

    Over the last decade the world has seen numerous autonomous vehicle programs. Wheels and track designs are the basis for many of these vehicles. This is primarily due to four main reasons: a vast preexisting knowledge base for these designs, energy efficiency of power sources, scalability of actuators, and the lack of control systems technologies for handling alternate highly complex distributed systems. Though large efforts seek to improve the mobility of these vehicles, many limitations still exist for these systems within unstructured environments, e.g. limited mobility within industrial and nuclear accident sites where existing plant configurations have been extensively changed. These unstructured operational environments include missions for exploration, reconnaissance, and emergency recovery of objects within reconfigured or collapsed structures, e.g. bombed buildings. More importantly, these environments present a clear and present danger for direct human interactions during the initial phases of recovery operations. Clearly, the current classes of autonomous vehicles are incapable of performing in these environments. Thus the next generation of designs must include highly reconfigurable and flexible autonomous robotic platforms. This new breed of autonomous vehicles will be both highly flexible and environmentally adaptable. Presented in this paper is one of the most successful designs from nature, the snake-eel-worm (SEW). This design implements shape memory alloy (SMA) actuators which allow for scaling of the robotic SEW designs from sub-micron scale to heavy industrial implementations without major conceptual redesigns as required in traditional hydraulic, pneumatic, or motor driven systems. Autonomous vehicles based on the SEW design posses the ability to easily move between air based environments and fluid based environments with limited or no reconfiguration. Under a SEW designed vehicle, one not only achieves vastly improved maneuverability within a highly unstructured environment, but also gains robotic manipulation abilities, normally relegated as secondary add-ons within existing vehicles, all within one small condensed package. The prototype design presented includes a Beowulf style computing system for advanced guidance calculations and visualization computations. All of the design and implementation pertaining to the SEW robot discussed in this paper is the product of a student team under the summer fellowship program at the DOEs INEEL.

  16. Age of irrigation water in ground water from the Eastern Snake River Plain Aquifer, south-central Idaho

    USGS Publications Warehouse

    Plummer, Niel; Rupert, M.G.; Busenberg, E.; Schlosser, P.

    2000-01-01

    Stable isotope data (2H and 18O) were used in conjunction with chlorofluorocarbon (CFC) and tritium/helium-3 (3H/3He) data to determine the fraction and age of irrigation water in ground water mixtures from farmed parts of the Eastern Snake River Plain (ESRP) Aquifer in south-central Idaho. Two groups of waters were recognized: (1) regional background water, unaffected by irrigation and fertilizer application, and (2) mixtures of irrigation water from the Snake River with regional background water. New data are presented comparing CFC and 3H/3He dating of water recharged through deep fractured basalt, and dating of young fractions in ground water mixtures. The 3H/3He ages of irrigation water in most mixtures ranged from about zero to eight years. The CFC ages of irrigation water in mixtures ranged from values near those based on 3H/3He dating to values biased older than the 3H/3He ages by as much as eight to 10 years. Unsaturated zone air had CFC-12 and CFC-113 concentrations that were 60% to 95%, and 50% to 90%, respectively, of modern air concentrations and were consistently contaminated with CFC-11. Irrigation water diverted from the Snake River was contaminated with CFC-11 but near solubility equilibrium with CFC-12 and CFC-113. The dating indicates ground water velocities of 5 to 8 m/d for water along the top of the ESRP Aquifer near the southwestern boundary of the Idaho National Engineering and Environmental Laboratory (INEEL). Many of the regional background waters contain excess terrigenic helium with a 3He/4He isotope ratio of 7 x 10-6 to 11 x 10-6 (R/Ra = 5 to 8) and could not be dated. Ratios of CFC data indicate that some rangeland water may contain as much as 5% to 30% young water (ages of less than or equal to two to 11.5 years) mixed with old regional background water. The relatively low residence times of ground water in irrigated parts of the ESRP Aquifer and the dilution with low-NO3 irrigation water from the Snake River lower the potential for NO3 contamination in agricultural areas.

  17. Design and characterization of microporous zeolitic hydroceramic waste forms for the solidification and stabilization of sodium bearing wastes

    NASA Astrophysics Data System (ADS)

    Bao, Yun

    During the production of nuclear weapon by the DOE, large amounts of liquid waste were generated and stored in millions of gallons of tanks at Savannah River, Hanford and INEEL sites. Typically, the waste contains large amounts of soluble NaOH, NaNO2 and NaNO3 and small amounts of soluble fission products, cladding materials and cleaning solution. Due to its high sodium content it has been called sodium bearing waste (SBW). We have formulated, tested and evaluated a new type of hydroceramic waste form specifically designed to solidify SBW. Hydroceramics can be made from an alumosilicate source such as metakaolin and NaOH solutions or the SBW itself. Under mild hydrothermal conditions, the mixture is transformed into a solid consisting of zeolites. This process leads to the incorporation of radionuclides into lattice sites and the cage structures of the zeolites. Hydroceramics have high strength and inherent stability in realistic geologic settings. The process of making hydroceramics from a series of SBWs was optimized. The results are reported in this thesis. Some SBWs containing relatively small amounts of NaNO3 and NaNO2 (SigmaNOx/Sigma Na<25 mol%) can be directly solidified with metakaolin. The remaining SBW having high concentrations of nitrate and nitrite (SigmaNOx/Sigma Na>25 mol%) require pretreatment since a zeolitic matrix such as cancrinite is unable to host more than 25 mol% nitrate/nitrite. Two procedures to denitrate/denitrite followed by solidification were developed. One is based on calcination in which a reducing agent such as sucrose and metakaolin have been chosen as a way of reducing nitrate and nitrite to an acceptable level. The resulting calcine can be solidified using additional metakaolin and NaOH to form a hydroceramic. As an alternate, a chemical denitration/denitrition process using Si and Al powders as the reducing agents, followed by adding metakaolin to the solution prepare a hydroceramic was also investigated. Si and Al not only are the reducing agents, but they also provide Si and Al species to make zeolites during the reducing process. Performance of the hydroceramics was documented using SEM microstructure and X-ray diffraction phase analysis, mechanical property and leaching tests (Product Consistency Test and ANSI/ANS-16.1 leaching test).

  18. Use of acceptable knowledge to demonstrate TRAMPAC compliance

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Whitworth, J.; Becker, B.; Guerin, D.

    2004-01-01

    Recently, Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) has supported the Central Characterization Project (CCP) managed by the U.S. Department of Energy (DOE) in the shipment of transuranic (TRU) waste from various small-quantity TRU waste generators to hub sites or other DOE sites in TRUPACT-II shipping containers. This support has involved using acceptable knowledge (AK) to demonstrate compliance with various requirements of Revision 19 of the TRUPACT-II Authorized Methods of Payload Compliance (TRAMPAC). LANL-CO has worked to facilitate TRUPACT-II shipments from the University of Missouri Research Reactor (MURR) and Lovelace Respiratory Research Institute (LRRI) to Argonne National Laboratory-East (ANL-E) and Losmore » Alamos National Laboratory (LANL), respectively. The latter two sites have TRU waste certification programs approved to ship waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In each case, AK was used to satisfy the necessary information to ship the waste to other DOE facilities. For the purposes of intersite shipment, AK provided data to WIPP Waste Information System (WWIS) transportation modules to ensure that required information was obtained prior to TRUPACT-II shipments. The WWIS modules were used for the intersite shipments, not to enter certification data into WWIS, but rather to take advantage of a validated system to ensure that the containers to be shipped were compliant with TRAMPAC requirements, particularly in the evaluation of quantitative criteria. LANL-CO also assisted with a TRAMPAC compliance demonstration for homogeneous waste containers shipped in TRUPACT-II containers from ANL-E to Idaho National Engineering and Environmental Laboratory (INEEL) for the purpose of core sampling. The basis for the TRAMPAC compliance determinations was AK regarding radiological composition, chemical composition, TRU waste container packaging, and absence of prohibited items. Also, even in the case where AK is not used to fully demonstrate TRAMPAC compliance, it may be used to identify problem areas for shippability of different waste streams. An example is the case of Pu-238-contaminated waste from the Savannah River Site that had a low probability of meeting decay heat limits and aspiration times due to several factors including large numbers of confinement layers. This paper will outline 17 TRAMPAC compliance criteria assessed and the types of information used to show compliance with all criteria other than dose rate and container weight, which are normally easily measured at load preparation.« less

  19. The Challenges of Creating a Real-Time Data Management System for TRU-Mixed Waste at the Advanced Mixed Waste Treatment Plant

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Paff, S. W; Doody, S.

    2003-02-25

    This paper discusses the challenges associated with creating a data management system for waste tracking at the Advanced Mixed Waste Treatment Plant (AMWTP) at the Idaho National Engineering Lab (INEEL). The waste tracking system combines data from plant automation systems and decision points. The primary purpose of the system is to provide information to enable the plant operators and engineers to assess the risks associated with each container and determine the best method of treating it. It is also used to track the transuranic (TRU) waste containers as they move throughout the various processes at the plant. And finally, themore » goal of the system is to support paperless shipments of the waste to the Waste Isolation Pilot Plant (WIPP). This paper describes the approach, methodologies, the underlying design of the database, and the challenges of creating the Data Management System (DMS) prior to completion of design and construction of a major plant. The system was built utilizing an Oracle database platform, and Oracle Forms 6i in client-server mode. The underlying data architecture is container-centric, with separate tables and objects for each type of analysis used to characterize the waste, including real-time radiography (RTR), non-destructive assay (NDA), head-space gas sampling and analysis (HSGS), visual examination (VE) and coring. The use of separate tables facilitated the construction of automatic interfaces with the analysis instruments that enabled direct data capture. Movements are tracked using a location system describing each waste container's current location and a history table tracking the container's movement history. The movement system is designed to interface both with radio-frequency bar-code devices and the plant's integrated control system (ICS). Collections of containers or information, such as batches, were created across the various types of analyses, which enabled a single, cohesive approach to be developed for verification and validation activities. The DMS includes general system functions, including task lists, electronic signature, non-conformance reports and message systems, that cut vertically across the remaining subsystems. Oracle's security features were utilized to ensure that only authorized users were allowed to log in, and to restrict access to system functionality according to user role.« less

  20. A Brief Review of Past INL Work Assessing Radionuclide Content in TMI-2 Melted Fuel Debris: The Use of 144Ce as a Surrogate for Pu Accountancy

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    D. L. Chichester; S. J. Thompson

    2013-09-01

    This report serves as a literature review of prior work performed at Idaho National Laboratory, and its predecessor organizations Idaho National Engineering Laboratory (INEL) and Idaho National Engineering and Environmental Laboratory (INEEL), studying radionuclide partitioning within the melted fuel debris of the reactor of the Three Mile Island 2 (TMI-2) nuclear power plant. The purpose of this review is to document prior published work that provides supporting evidence of the utility of using 144Ce as a surrogate for plutonium within melted fuel debris. When the TMI-2 accident occurred no quantitative nondestructive analysis (NDA) techniques existed that could assay plutonium inmore » the unconventional wastes from the reactor. However, unpublished work performed at INL by D. W. Akers in the late 1980s through the 1990s demonstrated that passive gamma-ray spectrometry of 144Ce could potentially be used to develop a semi-quantitative correlation for estimating plutonium content in these materials. The fate and transport of radioisotopes in fuel from different regions of the core, including uranium, fission products, and actinides, appear to be well characterized based on the maximum temperature reached by fuel in different parts of the core and the melting point, boiling point, and volatility of those radioisotopes. Also, the chemical interactions between fuel, fuel cladding, control elements, and core structural components appears to have played a large role in determining when and how fuel relocation occurred in the core; perhaps the most important of these reaction appears to be related to the formation of mixed-material alloys, eutectics, in the fuel cladding. Because of its high melting point, low volatility, and similar chemical behavior to plutonium, the element cerium appears to have behaved similarly to plutonium during the evolution of the TMI-2 accident. Anecdotal evidence extrapolated from open-source literature strengthens this logical feasibility for using cerium, which is rather easy to analyze using passive nondestructive analysis gamma-ray spectrometry, as a surrogate for plutonium in the final analysis of TMI-2 melted fuel debris. The generation of this report is motivated by the need to perform nuclear material accountancy measurements on the melted fuel debris that will be excavated from the damaged nuclear reactors at the Fukushima Daiichi nuclear power plant in Japan, which were destroyed by the Tohoku earthquake and tsunami on March 11, 2011. Lessons may be taken from prior U.S. work related to the study of the TMI-2 core debris to support the development of new assay methods for use at Fukushima Daiichi. While significant differences exist between the two reactor systems (pressurized water reactor (TMI-2) versus boiling water reactor (FD), fresh water post-accident cooing (TMI-2) versus salt water (FD), maintained containment (TMI-2) versus loss of containment (FD)) there remain sufficient similarities to motivate these comparisons.« less

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