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

International Nuclear Information System (INIS)

Low, J.O.

1985-12-01

An improved-confinement technology as applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste is being investigated. An improved-confinement technology, in situ grouting, is being demonstrated in a 2-year engineering feasibility test at the INEL. Grout formulation and development were completed by Oak Ridge National Laboratory in Tennessee to support the in situ grouting test. Three grout formulations have been adapted to the arid, unsaturated soil conditions at the INEL: ordinary particulate grout; microfine penetration grout; soil grout. Three test trenches were constructed north of the INEL's Subsurface Disposal Area (SDA). Nonradioactive waste forms closely resembling TRU waste buried at the INEL have been fabricated and are ready for emplacement into these test trenches. A literature search for a simulated (analog) TRU tracer was completed as well as a chemical characterization of the INEL soil. Data developed from the chemistry characterization and literature search have been inputed into the selection and laboratory testing of the TRU analog tracers. Simulated TRU tracers will be loaded into waste forms prior to emplacement into the test trenches. Test trench data acquisition instrumentation will be installed during waste form emplacement. Instrumentation will monitor for moisture movement and tracer detection. Plans for test completion in FY-1986 are also shown. Various buried waste improved-confinement technologies performed by other Department of Energy sites were assessed for applicability to the INEL buried TRU waste. Primary demonstrations were performed at the Hanford site in Washington and at ORNL. This report also includes information on accomplishments of related activities at the INEL such as the program for Environmental Surveillance of the Radioactive Waste Management complex as well as the Subsurface Migration Studies. 18 refs., 11 figs., 12 tabs

Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Low, J.O.

1985-12-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve management techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; and (c) retrieve, process, and certify the waste for disposal at a federal repository. Fourteen studies are described in this plan for Alternatives 2 and 3. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for the INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind, water penetration, erosion, and plant and animal intrusion. Several studies proposed under this alternative will examine special techniques to immobilize or encapsulate the buried waste. An in situ grouting study was implemented at the INEL starting in FY-1985 and will be completed at the end of FY-1986 with the grouting of a simulated INEL buried TRU waste trench. Studies of the third alternative will investigate improved retrieval, processing, and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies

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

International Nuclear Information System (INIS)

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

1987-01-01

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

Annual technology assessment and progress report for the buried transuranic waste program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Berreth, P.D.

1984-11-01

The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive waste. In 1983, DOE formulated a comprehensive plan to manage transuranic (TRU) defense waste. The DOE plan for buried TRU waste is to monitor it, take remedial actions as necessary, and reevaluate its safety periodically. The DOE strategy reflects concern that, based on present technology, retrieval and processing of buried waste may be risky and costly. To implement the DOE plan, EG and G Idaho, Inc., prime contractor at the Idaho National Engineering Laboratory (INEL), has developed a strategy for long-term management of the 2 million cubic feet of INEL buried TRU waste. That strategy involves four main activities: (a) environmental monitoring, (b) remedial action if necessary, (c) assimilation of data from both special studies and ongoing waste management activities, and (d) selection of a long-term management alternative in 1995. This report, submitted as the first in a series of annual reports, summarizes the buried TRU waste activities performed in fiscal year (FY) 1984 at the INEL in response to the DOE plan. Specifically, technologies applicable to buried waste confinement, retrieval, certification, and processing have been assessed, a long-range plan to conduct buried wasted studies over the next ten years has been prepared, and retrieval and soil management alternatives have been evaluated. 17 references, 7 figures, 1 table

Annual technology assessment and progress report for the Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory (1987)

International Nuclear Information System (INIS)

Loomis, G.G.; Low, J.O.

1988-01-01

This report presents FY-87 activities for the Buried Transuranic (TRU) Waste Studies Program at the Idaho National Engineering Laboratory (INEL). This program investigates techniques to provide long-term confinement of buried TRU waste, as well as methods of retrieval. The confinement method of in situ grouting was examined in a simulated shallow-land buried TRU waste pit constructed adjacent to the RWMC TRU waste burial pits. The in situ grouting technique involved an experimental dyanmic compaction process which simultaneously grouts and compacts the waste. The simulated waste pit consisted of regions of randomly dumped drums, stacked boxes, and stacked drums, thus representing the various conditions of buried waste at the RWMC. Simulated waste and airborne tracers were loaded into the various simulated buried waste containers. Pregrouting and post-grouting data, such as hydraulic conductivity, were obtained to assess the hydrological integrity of the grouted waste material. In addition, post-grouting destructive examinations were performed and the results analyzed. Retrieval and processing of the TRU buried waste is also being examined at the INEL. At a conceptual level, retrieval of TRU buried waste involves a movable containment building to confine airborne particulate, heavy equipment to remove the waste, processing equipment, and equipment to control the air quality within the building. Studies were performed in FY-87 to identify containment building requirements such as type, mobility, and ventilation. An experimental program to demonstrate the retrieval technique using existing INEL heavy equipment has also been identified. 11 refs., 17 figs., 11 tabs

Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Berreth, P.D.; Fischer, D.K.; Suckel, R.A.

1984-11-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the INEL. The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve handling techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; (c) retrieve, process, and certify the waste for disposal at a federal repository. Fifteen studies are described in this plan for the latter two alternatives. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind water penetration, erosion, and plant and animal intrusion. Several studies proposed will examine special techniques to immobilize or encapsulate the buried waste. Studies of the third alternative will investigate improved retrieval, processing and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies. 19 references, 8 figures, 4 tables

In situ vitrification of buried waste: Containment issues and suppression systems

International Nuclear Information System (INIS)

Luey, J.; Powell, T.D.

1992-03-01

Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the US Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt

In situ vitrification of buried waste: Containment issues and suppression systems

International Nuclear Information System (INIS)

Luey, J.; Powell, T.D.

1992-01-01

Pacific Northwest Laboratory (PNL) and Idaho National Engineering Laboratory (INEL) are developing a remedial action technology for buried waste through the adaptation of the in situ vitrification (ISV) process. The ISV process is a thermal treatment process originally developed for the U.S. Department of Energy (DOE) to stabilize soils contaminated with transuranic waste. ISV tests with buried waste forms have demonstrated that the processing of buried waste is more dynamic than the processing of soils. This paper will focus on the issue of containment of the gases released during the processing of buried waste and on engineered suppression systems to alleviate transient events associated with dynamic off-gassing from the ISV melt. (author)

Ultra wide band radar holographic imaging of buried waste at DOE sites

International Nuclear Information System (INIS)

Collins, H.D.; Gribble, R.P.; Hall, T.E.; Lechelt, W.M.

1995-04-01

Ultra wideband linear array holography is a unique real-time imaging technique for in-situ inspection of buried waste at various DOE sites. The array can be mounted on various platforms such as crane booms, pickup trucks, ATVs, and scanned generating ''3-D'' subsurface images in real time. Inspection speeds are 0.5 to 2 meters/sec, if the image is viewed in real time, greater for off-line processing. The Ground Penetrating Holographic (GPH) system developed for inspection of DOE sites employs two 32element arrays of tapered-slot antenna operating at 5-GHz and 2.5-GHz center frequencies. The GPH system, which is mounted on a small trailer with a computer image processor, display, and power supply, is capable of imaging a wide swath (1 to 2 meters) with its linear arrays. The lower frequency array will be used at INEL (for greater depth penetration) because of high soil attenuation. Recent holographic ''3-D'' images of buried waste container lids and dielectrics obtained in Hanford sand and INEL soils at various depths graphically illustrate the unique image resolution capabilities of the system. Experimental results using the 5-GHz array will be presented showing the excellent holographic image quality of various subsurface targets in sand and INEL soil

Simplified risk assessment for transporting ATR spent fuel within the INEL

International Nuclear Information System (INIS)

Franklin, E.M.; Courtney, J.C.

1994-01-01

Interest in characterizing the condition of stored spent fuels has generated the need to move spent fuels to hot cell facilities within the Idaho National Engineering Laboratory (INEL). A simplified probabilistic risk assessment (SPRA) and an evaluation of the radiological consequences in the event of an accident are discussed and applied to on-site Advanced Test Reactor (AYR) spent fuel shipments. Reported accident probabilities between 10 -4 and 10 -6 and low radiological consequences, affords this, and other spent fuel characterization efforts, an additional option to move spent fuels within the INEL

INEL Sample Management Office

International Nuclear Information System (INIS)

Watkins, C.

1994-01-01

The Idaho National Engineering Laboratory (INEL) Sample Management Office (SMO) was formed as part of the EG ampersand G Idaho Environmental Restoration Program (ERP) in June, 1990. Since then, the SMO has been recognized and sought out by other prime contractors and programs at the INEL. Since December 1991, the DOE-ID Division Directors for the Environmental Restoration Division and Waste Management Division supported the expansion of the INEL ERP SMO into the INEL site wide SMO. The INEL SMO serves as a point of contact for multiple environmental analytical chemistry and laboratory issues (e.g., capacity, capability). The SMO chemists work with project managers during planning to help develop data quality objectives, select appropriate analytical methods, identify special analytical services needs, identify a source for the services, and ensure that requirements for sampling and analysis (e.g., preservations, sample volumes) are clear and technically accurate. The SMO chemists also prepare work scope statements for the laboratories performing the analyses

Thermal processing system concepts and considerations for RWMC buried waste

International Nuclear Information System (INIS)

Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

1992-02-01

This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided

Thermal processing system concepts and considerations for RWMC buried waste

Energy Technology Data Exchange (ETDEWEB)

Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

1992-02-01

This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided.

INEL waste reduction: summary paper

International Nuclear Information System (INIS)

Rhoades, W.A.

1987-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

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

International Nuclear Information System (INIS)

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

1979-12-01

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

Stormwater management at the ARID INEL

International Nuclear Information System (INIS)

Walker, E.D.

1994-01-01

NPDES stormwater permits are required for stormwater discharges to waters of the US (WUS). The Idaho National Engineering Laboratory (INEL) applied for coverage under a general NPDES stormwater permit because there is some potential for stormwater discharge to the Big Lost River System, which could infiltrate to groundwater. The main requirements of the permit are to prevent contaminants from coming into contact with stormwater and prevent contaminated stormwater from running off of facilities into WUS or groundwater. All INEL major facility areas have prepared and implemented stormwater pollution prevention plans (SWPPPs). The INEL also applied for coverage under a separate NPDES general permit for stormwater discharges from construction sites. An INEL Generic SWPPP for construction activities was prepared and implemented for all construction projects at the INEL

INEL D&D long-range plan

Energy Technology Data Exchange (ETDEWEB)

Buckland, R.J.; Kenoyer, D.J.; LaBuy, S.A.

1995-09-01

This Long-Range Plan presents the Decontamination and Dismantlement (D&D) Program planning status for facilities at the Idaho National Engineering Laboratory (INEL). The plan provides a general description of the D&D Program objectives, management criteria, and policy; discusses current activities; and documents the INEL D&D Program cost and schedule estimate projections for the next 15 years. Appendices are included that provide INEL D&D project historical information, a comprehensive descriptive summary of each current D&D surplus facility, and a summary database of all INEL contaminated facilities awaiting or undergoing the facility transition process.

INEL metal recycle annual report, FY-94

International Nuclear Information System (INIS)

Bechtold, T.E.

1994-09-01

In 1992, the mission of the Idaho Chemical Processing Plant was changed from reprocessing of spent nuclear fuels to development of technologies for conditioning of spent nuclear fuels and other high-level wastes for disposal in a geologic repository. In addition, the Department of Energy (DOE) directed Idaho National Engineering Laboratory (INEL) to develop a program plan addressing the management of radioactive contaminated scrap metal (RSM) within the DOE complex. Based on discussions with the EM-30 organization, the INEL Metal Recycle program plan was developed to address all issues of RSM management. Major options considered for RSM management were engineered interim storage, land disposal as low-level waste, and beneficial reuse/recycle. From its inception, the Metal Recycle program has emphasized avoidance of storage and disposal costs through beneficial reuse of RSM. The Metal Recycle program plan includes three major activities: Site-by-site inventory of RSM resources; validation of technologies for conversion of RSM to usable products; and identification of parties prepared to participate in development of a RSM recycle business

Latex-modified grouts for in-situ stabilization of buried transuranic/mixed waste

International Nuclear Information System (INIS)

Allan, M.L.

1996-06-01

The Department of Applied Science at Brookhaven national Laboratory was requested to investigate latex-modified grouts for in-situ stabilization of buried TRU/mixed waste for INEL. The waste exists in shallow trenches that were backfilled with soil. The objective was to formulate latex-modified grouts for use with the jet grouting technique to enable in-situ stabilization of buried waste. The stabilized waste was either to be left in place or retrieved for further processing. Grouting prior to retrieval reduces the potential release of contaminants. Rheological properties of latex-modified grouts were investigated and compared with those of conventional neat cement grouts used for jet grouting

IP and resistivity survey at the INEL cold test pit

International Nuclear Information System (INIS)

Frangos, W.

1997-01-01

Induced polarization (IP) is a technique for detection of diffuse occurrences of metallic material. The Idaho National Laboratory (INEL) Cold Test Pit (CTP) has been carefully constructed to simulate stored hazardous waste occurrences. IP and resistivity surveys of the CTP show a very strong IP response and a modest resistivity response associated with the simulated waste. Several false positive resistivity anomalies are noted. 2-D inversion of the data accurately determine the lateral limits of the waste zone. The depth of burial indicated is deeper than reported by the construction engineers. Limited depth extent is recognized, in distinction to results from other, resistivity-based, methods, but it also appears too deep. IP holds promise as a method for locating buried waste

Buried Waste Integrated Demonstration Plan

International Nuclear Information System (INIS)

Kostelnik, K.M.

1991-12-01

This document presents the plan of activities for the Buried Waste Integrated Demonstration (BWID) program which supports the environmental restoration (ER) objectives of the Department of Energy (DOE) Complex. Discussed in this plan are the objectives, organization, roles and responsibilities, and the process for implementing and managing BWID. BWID is hosted at the Idaho National Engineering Laboratory (INEL), but involves participants from throughout the DOE Complex, private industry, universities, and the international community. These participants will support, demonstrate, and evaluate a suite of advanced technologies representing a comprehensive remediation system for the effective and efficient remediation of buried waste. The processes for identifying technological needs, screening candidate technologies for applicability and maturity, selecting appropriate technologies for demonstration, field demonstrating, evaluation of results and transferring technologies to environmental restoration programs are also presented. This document further describes the elements of project planning and control that apply to BWID. It addresses the management processes, operating procedures, programmatic and technical objectives, and schedules. Key functions in support of each demonstration such as regulatory coordination, safety analyses, risk evaluations, facility requirements, and data management are presented

INEL environmental characterization report. Volume II. Appendices A-D

International Nuclear Information System (INIS)

1984-09-01

This volume contains appendices: (1) a socioeconomic data base for southeastern Idaho; (2) an ecological characterization of the INEL; (3) site-specific climatology summary, NPR primary and alternate sites; (4) NPR site borehole completion; (5) an investigation of the principal lineament at the INEL; (6) an investigation of Clay Butte, Idaho; (7) Arco and Howe fault study; (8) seismology of the INEL; (9) geologic map of the INEL; and (1) geologic ages of the INEL

INEL D ampersand D long-range plan

International Nuclear Information System (INIS)

Buckland, R.J.; Kenoyer, D.J.; LaBuy, S.A.

1995-09-01

This Long-Range Plan presents the Decontamination and Dismantlement (D ampersand D) Program planning status for facilities at the Idaho National Engineering Laboratory (INEL). The plan provides a general description of the D ampersand D Program objectives, management criteria, and policy; discusses current activities; and documents the INEL D ampersand D Program cost and schedule estimate projections for the next 15 years. Appendices are included that provide INEL D ampersand D project historical information, a comprehensive descriptive summary of each current D ampersand D surplus facility, and a summary database of all INEL contaminated facilities awaiting or undergoing the facility transition process

INEL environmental characterization report. Volume III. Appendices E-H

International Nuclear Information System (INIS)

1984-09-01

This volume contains the following appendices: (1) INEL subsurface hydrology; (2) cultural resources assessment of two study areas on the INEL; (3) description of INEL facilities; and (4) effluent measurements and environmental monitoring programs

INEL environmental characterization report. Volume I. Summary

International Nuclear Information System (INIS)

1984-09-01

This environmental characterization report contains general information on environmental aspects of the INEL, and specific information on two areas within the INEL which have been tentatively selected for NPR siting. The objective is to present environmental information but not assess environmental impacts. Impacts will be addressed specifically at a later date when an EIS is prepared. The information in this report will be used to evaluate the siting of various reactor types at each of the three reservation alternatives. The report covers geography, physiography, and demography of the INEL, ecology, climatology overview, geology and seismology, hydrology, cultural resources assessment, baseline socioeconomic data, description of INEL facilities and capabilities, effluent and environmental measurements and monitoring programs, exposure pathways, and environmental laws and regulations

Buried waste remote survey of the Idaho National Engineering Laboratory subsurface disposal area

International Nuclear Information System (INIS)

Richardson, B.S.; Noakes, M.W.; Griebenow, B.E.; Josten, N.E.

1991-01-01

Burial site characterization is an important first step in the restoration of subsurface disposal sites. Testing and demonstration of technology for remote buried waste site characterization were performed at the Idaho National Engineering Laboratory (INEL) by a team from five US Department of Energy (DOE) laboratories. The US Army's Soldier Robot Interface Project (SRIP) vehicle, on loan to the Oak Ridge National Laboratory (ORNL), was used as a remotely operated sensor platform. The SRIP was equipped with an array of sensors including terrain conductivity meter, magnetometer, ground-penetrating radar (GPR), organic vapor detector, gamma-based radar detector, and spectrum analyzer. The testing and demonstration were successfully completed and provided direction for future work in buried waste site characterization

TNX Burying Ground: Environmental information document

International Nuclear Information System (INIS)

Dunaway, J.K.W.; Johnson, W.F.; Kingley, L.E.; Simmons, R.V.; Bledsoe, H.W.

1987-03-01

The TNX Burying Ground, located within the TNX Area of the Savannah River Plant (SRP), was originally built to dispose of debris from an experimental evaporator explosion at TNX in 1953. This evaporator contained approximately 590 kg of uranyl nitrate. From 1980 to 1984, much of the waste material buried at TNX was excavated and sent to the SRP Radioactive Waste Burial Grounds for reburial. An estimated 27 kg of uranyl nitrate remains buried at TNX. The TNX Burying Ground consists of three sites known to contain waste and one site suspected of containing waste material. All four sites are located within the TNX security fenceline. Groundwater at the TNX Burying Ground was not evaluated because there are no groundwater monitoring wells installed in the immediate vicinity of this waste site. The closure options considered for the TNX Burying Ground are waste removal and closure, no waste removal and closure, and no action. The predominant pathways for human exposure to chemical and/or radioactive constituents are through surface, subsurface, and atmospheric transport. Modeling calculations were made to determine the risks to human population via these general pathways for the three postulated closure options. An ecological assessment was conducted to predict the environmental impacts on aquatic and terrestrial biota. The relative costs for each of the closure options were estimated

1994 INEL site-specific plan

International Nuclear Information System (INIS)

Couch, B.

1994-01-01

This report presents plans for environmental restoration and waste management activities at the Idaho National Engineering Laboratory for fiscal year 1994. This years's plan focuses on issues affecting the Environmental Restoration and Waste Management Programs. The Environmental Restoration Program is concerned with all aspects of assessment and cleanup of inactive operations. It involves assessing and cleaning up (where necessary) inactive INEL waste areas that could release harmful substances into the environment, as well as safely managing surplus nuclear facilities. The Waste Management program involves treatment, storage, and disposal of radioactive, hazardous, mixed, and industrial waste by DOE activities. This program is designed to protect the safety of INEL employees, the public, and the environment in the design, construction, maintenance, and operation of INEL treatment, storage, and disposal facilities. It operates facilities in a cost-effective, environmentally sound, regulatory compliant, and publicly acceptable manner

INEL D ampersand D Long-Range Plan

International Nuclear Information System (INIS)

Buckland, R.J.; Kenoyer, D.J.; Preussner, D.H.

1993-10-01

This Long-Range Plan presents the Decontamination and Decommissioning (D ampersand D) Program planning status for facilities at the Idaho National Engineering Laboratory (INEL). The plan provides a general description of the D ampersand D Program objectives, management criteria, and philosophy; discusses current activities; and documents the INEL D ampersand D Program cost and schedule estimate projections for the next 15 years. appendices are included that provide INEL D ampersand D project historical information and a comprehensive descriptive summary of each current surplus facility

1994 INEL site-specific plan

Energy Technology Data Exchange (ETDEWEB)

Couch, B.

1994-05-01

This report presents plans for environmental restoration and waste management activities at the Idaho National Engineering Laboratory for fiscal year 1994. This years`s plan focuses on issues affecting the Environmental Restoration and Waste Management Programs. The Environmental Restoration Program is concerned with all aspects of assessment and cleanup of inactive operations. It involves assessing and cleaning up (where necessary) inactive INEL waste areas that could release harmful substances into the environment, as well as safely managing surplus nuclear facilities. The Waste Management program involves treatment, storage, and disposal of radioactive, hazardous, mixed, and industrial waste by DOE activities. This program is designed to protect the safety of INEL employees, the public, and the environment in the design, construction, maintenance, and operation of INEL treatment, storage, and disposal facilities. It operates facilities in a cost-effective, environmentally sound, regulatory compliant, and publicly acceptable manner.

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

International Nuclear Information System (INIS)

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

1995-09-01

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

Philosophy and overview of the INEL waste management program

International Nuclear Information System (INIS)

Gertz, C.P.; Whitsett, J.B.; Hamric, J.P.

1986-01-01

The INEL philosophy of ''get the job done; do it right--the first time'' is described as it applies to all phases of waste management activities. In addition, an overview of INEL's waste management programs and projects--low-level waste management operations and technology development; transuranic waste management operations and technology development; high-level waste management operations and technology development; spent fuel storage operations and equipment/technology development; transportation operations, technology development, and prototype cask procurements--are discussed. Emphasis is placed on the application of the INEL philosophy to the successful initiation and continuation of INEL waste management activities

PDP cycle 1 tests at INEL

Energy Technology Data Exchange (ETDEWEB)

Harker, Y.D.; Twedell, G.W. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-11-01

The Idaho National Engineering Laboratory (INEL) is a participant in the nondestructive assay Performance Demonstration Program (PDP) as part of the U.S. TRU Waste Characterization Program. The PDP program was designed to help ensure compliance with the quality assurance objectives (QAO`s) in the TRU Waste Characterization Program Plan. In June, 1996, cycle 1 of PDP program was completed at the Stored Waste Examination Pilot Plant (SWEPP) at INEL. The assay capability at INEL/SWEPP consists of a passive active neutron (PAN) radioassay system (for bulk fissile material assay) and a passive gamma spectrometry system (for isotopic mass ratio determination). The results from the two systems are combined to produce a single assay report which contains isotopic information ({sup 238}Pu, {sup 239}Pu), density, total activity, alpha activity, TRU activity, TRU activity concentration, Pu equivalent Curies and fissile gram equivalent. The PDP cycle 1 tests were expected to test bias and precision of the assay systems under nearly ideal conditions; ie., non-interfering matrices and little or no source self shielding. The test consisted of two drums in which the source loading was not known by the site. One drum was essentially empty and the other was filled with ethafoam. As per PDP`s instructions, the tests were to be conducted using the same procedures and equipment that normally would be used by SWEPP to assay real waste drums. This paper will discuss the lessons learned from these tests and INEL`s plans to improve the capabilities of the SWEPP assay systems. 7 refs., 6 tabs.

Technology status report: Transuranic contamination control at INEL

International Nuclear Information System (INIS)

Loomis, G.G.

1991-09-01

This report summarizes proposed FY-92 work at the Idaho National Engineering Laboratory (INEL) in the field of contamination control during transuranic waste handling operations. The proposed work is both applied research and demonstration testing. The INEL needs for contamination control applied research and demonstration testing are listed along with a description of past accomplishments. The INEL proposal is compared to other proposals for contamination control work that are under consideration for funding by the Department of Energy. Benefits of this work and impacts of not sponsoring this work are also given. 21 refs

TMI-2 fuel canister interface requirements for INEL. Revision 1

International Nuclear Information System (INIS)

Wilkins, D.E.; Martz, D.E.; Reno, H.W.

1984-06-01

This report focuses on fuel canister interface requirements at INEL which should be incorporated into the canister design criteria. The requirements will ensure compatibility with existing INEL structures and equipment to be used for receipt, unloading, and storage of fuel canisters. INEL can and does receive and store radioactive materials in many different forms, including reactor fuel. INEL requires detailed descriptions of canisters and casks. Therefore, requirements listed represent engineering design features which will simplify the handling and storage operations; consequently, they are not to be viewed as absolute or non-negotiable. However, the core acquisition contract was negotiated with certain storage assumptions which effect costs of storage. Deviations from those assumptions which significantly effect costs would require approval by DOE-Idaho. If some stated requirements are too restrictive, modifications based on sound engineering principles may be negotiated with INEL. 11 figures

Decision analysis for INEL hazardous waste storage

Energy Technology Data Exchange (ETDEWEB)

Page, L.A.; Roach, J.A.

1994-01-01

In mid-November 1993, the Idaho National Engineering Laboratory (INEL) Waste Reduction Operations Complex (WROC) Manager requested that the INEL Hazardous Waste Type Manager perform a decision analysis to determine whether or not a new Hazardous Waste Storage Facility (HWSF) was needed to store INEL hazardous waste (HW). In response to this request, a team was formed to perform a decision analysis for recommending the best configuration for storage of INEL HW. Personnel who participated in the decision analysis are listed in Appendix B. The results of the analysis indicate that the existing HWSF is not the best configuration for storage of INEL HW. The analysis detailed in Appendix C concludes that the best HW storage configuration would be to modify and use a portion of the Waste Experimental Reduction Facility (WERF) Waste Storage Building (WWSB), PBF-623 (Alternative 3). This facility was constructed in 1991 to serve as a waste staging facility for WERF incineration. The modifications include an extension of the current Room 105 across the south end of the WWSB and installing heating, ventilation, and bay curbing, which would provide approximately 1,600 ft{sup 2} of isolated HW storage area. Negotiations with the State to discuss aisle space requirements along with modifications to WWSB operating procedures are also necessary. The process to begin utilizing the WWSB for HW storage includes planned closure of the HWSF, modification to the WWSB, and relocation of the HW inventory. The cost to modify the WWSB can be funded by a reallocation of funding currently identified to correct HWSF deficiencies.

Decision analysis for INEL hazardous waste storage

International Nuclear Information System (INIS)

Page, L.A.; Roach, J.A.

1994-01-01

In mid-November 1993, the Idaho National Engineering Laboratory (INEL) Waste Reduction Operations Complex (WROC) Manager requested that the INEL Hazardous Waste Type Manager perform a decision analysis to determine whether or not a new Hazardous Waste Storage Facility (HWSF) was needed to store INEL hazardous waste (HW). In response to this request, a team was formed to perform a decision analysis for recommending the best configuration for storage of INEL HW. Personnel who participated in the decision analysis are listed in Appendix B. The results of the analysis indicate that the existing HWSF is not the best configuration for storage of INEL HW. The analysis detailed in Appendix C concludes that the best HW storage configuration would be to modify and use a portion of the Waste Experimental Reduction Facility (WERF) Waste Storage Building (WWSB), PBF-623 (Alternative 3). This facility was constructed in 1991 to serve as a waste staging facility for WERF incineration. The modifications include an extension of the current Room 105 across the south end of the WWSB and installing heating, ventilation, and bay curbing, which would provide approximately 1,600 ft 2 of isolated HW storage area. Negotiations with the State to discuss aisle space requirements along with modifications to WWSB operating procedures are also necessary. The process to begin utilizing the WWSB for HW storage includes planned closure of the HWSF, modification to the WWSB, and relocation of the HW inventory. The cost to modify the WWSB can be funded by a reallocation of funding currently identified to correct HWSF deficiencies

High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report

Energy Technology Data Exchange (ETDEWEB)

Sternberg, B.K.; Poulton, M.M.

1997-01-26

A high-frequency, high-resolution electromagnetic (EM) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHz), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) The authors tested the system over targets buried in soil. (3) The authors conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) The authors ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit.

High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report

International Nuclear Information System (INIS)

Sternberg, B.K.; Poulton, M.M.

1997-01-01

A high-frequency, high-resolution electromagnetic (EM) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHz), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) The authors tested the system over targets buried in soil. (3) The authors conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) The authors ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit

An integrated systems approach to remote retrieval of buried transuranic waste using a telerobotic transport vehicle, innovative end effector, and remote excavator

International Nuclear Information System (INIS)

Smith, A.M.; Rice, P.; Hyde, R.; Peterson, R.

1995-02-01

Between 1952 and 1970, over two million cubic feet of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. Commingled with this two million cubic feet of waste is up to 10 million cubic feet of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate technologies for excavating, and transporting buried transuranic wastes at the INEL, and other hazardous or radioactive waste sites throughout the US Department of Energy complex. The full-scale demonstration, conduced at RAHCO Internationals facilities in Spokane, Washington, in the summer of 1994, evaluated equipment performance and techniques for digging, dumping, and transporting buried waste. Three technologies were evaluated in the demonstration: an Innovative End Effector for dust free dumping, a Telerobotic Transport Vehicle to convey retrieved waste from the digface, and a Remote Operated Excavator to deploy the Innovative End Effector and perform waste retrieval operations. Data were gathered and analyzed to evaluate retrieval performance parameters such as retrieval rates, transportation rates, human factors, and the equipment's capability to control contamination spread

Radiologically contaminated lead shot reuse at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Heileson, W.M.; Grant, R.P.

1995-01-01

This project involved the utilization of radioactively contaminated lead shot located at the Radioactive Waste Management Complex (RWMC) for radiation shielding on a radioactive liquid process tank located at Argonne National Laboratory-West (ANL-W). The use of previously contaminated shot precludes the radioactive contamination of clean shot. With limited treatment and disposal options for contaminated lead shot, the reuse of lead for shielding is significant due to the inherent characteristic of becoming a mixed waste when radiologically contaminated. The INEL conducted a lead cleanup campaign in 1990. This was designed to ensure control of potential Resource Conservation and Recovery Act (RCRA) regulated waste. Contaminated lead from throughout the INEL, was containerized per the lead Waste Acceptance Criteria at the generator sites. Limited areas at the INEL are designated for mixed waste storage. As a result, some of the lead was stored at the RWMC in the air support weather shield (ASWS). This lead was contaminated with small amounts of fission product contamination. The lead was in the form of shot, brick, sheet, casks, and other various sized pieces. In 1993, ANL-W identified a need for lead shot to be used as shielding in a radioactive liquid waste storage and processing tank at the Fuel Cycle Facility (FCF). The contaminated lead used on this project had been in storage as mixed waste at the RWMC. This paper will focus on the processes and problems encountered to utilize the contaminated lead shot

BWID System Design Study

International Nuclear Information System (INIS)

O'Brien, M.C.; Rudin, M.J.; Morrison, J.L.; Richardson, J.G.

1991-01-01

The mission of the Buried Waste Integrated Demonstration (BWID) System Design Study is to identify and evaluate technology process options for the cradle-to-grave remediation of Transuranic (TRU)-Contaminated Waste Pits and Trenches buried at the Idaho National Engineering Laboratory (INEL). Emphasis is placed upon evaluating system configuration options and associated functional and operational requirements for retrieving and treating the buried wastes. A Performance-Based Technology Selection Filter was developed to evaluate the identified remediation systems and their enabling technologies based upon system requirements and quantification of technical Comprehensive Environmental Response, Compensation, and Liability (CERCLA) balancing criteria. Remediation systems will also be evaluated with respect to regulatory and institutional acceptance and cost-effectiveness

High-resolution subsurface imaging and neural network recognition: Non-intrusive buried substance location. Final report, January 26, 1997

International Nuclear Information System (INIS)

Sternberg, B.K.; Poulton, M.M.

1998-01-01

A high-frequency, high-resolution electromagnetic (EIVI) imaging system has been developed for environmental geophysics surveys. Some key features of this system include: (1) rapid surveying to allow dense spatial sampling over a large area, (2) high-accuracy measurements which are used to produce a high-resolution image of the subsurface, (3) measurements which have excellent signal-to-noise ratio over a wide bandwidth (31 kHz to 32 MHZ), (4) elimination of electric-field interference at high frequencies, (5) large-scale physical modeling to produce accurate theoretical responses over targets of interest in environmental geophysics surveys, (6) rapid neural network interpretation at the field site, and (7) visualization of complex structures during the survey. Four major experiments were conducted with the system: (1) Data were collected for several targets in our physical modeling facility. (2) We tested the system over targets buried in soil. (3) We conducted an extensive survey at the Idaho National Engineering Laboratory (INEL) Cold Test Pit (CTP). The location of the buried waste, category of waste, and thickness of the clay cap were successfully mapped. (4) We ran surveys over the acid pit at INEL. This was an operational survey over a hot site. The interpreted low-resistivity region correlated closely with the known extent of the acid pit

INEL BNCT Program

International Nuclear Information System (INIS)

Ackermann, A.L.; Dorn, R.V. III.

1991-03-01

This Bulletin presents a summary of accomplishments and highlights in the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program for March 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, a milestone summary, and animal data charts

INEL BNCT Program

Energy Technology Data Exchange (ETDEWEB)

Ackermann, A.L. (ed.)

1991-08-01

This Bulletin presents a summary of accomplishments and highlights in the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for August 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

TMI-2 core-examination program: INEL facilities readiness study

International Nuclear Information System (INIS)

McLaughlin, T.B.

1983-02-01

This report reviews the capability and readiness of remote handling facilities at the Idaho National Engineering Laboratory (INEL) to receive, and store the TMI-2 core, and to examine and analyze TMI-2 core samples. To accomplish these objectives, the facilities must be able to receive commercial casks, unload canisters from the casks, store the canisters, open the canisters, handle the fuel debris and assemblies, and perform various examinations. The report identifies documentation, including core information, necessary to INEL before receiving the entire TMI-2 core. Also identified are prerequisites to INEL's receipt of the first canister: costs, schedules, and a preliminary project plan for the tasks

Remote technologies for buried waste retrieval

International Nuclear Information System (INIS)

Smith, A.M.; Rice, P.

1995-01-01

The DOE is evaluating what should be done with this buried waste. Although the radioactive waste is not particularly mobile unless airborne, some of it was buried with volatile organics and/or other substances that tend to spread easily to surrounding soil or water tables. Volatile organics are hazardous materials (such as trichloroethylene) and require clean-up at certain levels in drinking water. There is concern that the buried volatile organics will spread into the water table and contaminate drinking water. Because of this, the DOE is considering options for handling this buried waste and reducing the risks of spreading or exposure. There are two primary options: containment and stabilization, or retrieval. Containment and stabilization systems would include systems that would leave the waste where it is, but contain and stabilize it so that the radioactive and hazardous materials would not spread to the surrounding soil, water, or air. For example, an in situ vitrification system could be used to melt the waste into a composite glass-like material that would not leach into the surrounding soil, water, or air. Retrieval systems are those that would remove the waste from its burial location for treatment and/or repackaging for long term storage. The objective of this project was to develop and demonstrate remote technologies that would minimize dust generation and the spread of airborne contaminants during buried waste retrieval. Remote technologies are essential for the retrieval of buried waste because they remove workers from the hazardous environment and provide greater automation, reducing the chances of human error. Minimizing dust generation is also essential to increased safety for the workers and the environment during buried waste retrieval. The main contaminants within the waste are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides, which are easily suspended in air and spread if disturbed

INEL experience and capabilities in design, operation, and maintenance of nuclear systems

International Nuclear Information System (INIS)

Leatham, J.; Masson, L.S.

1982-07-01

This study provides an overview of the experience, hardware, and managerial expertise available at the INEL for design, fabrication, and operation of tools and facilities for remote maintenance. The survey demonstrates that the INEL's fission reactor experience is directly applicable to the design of remote handling hardware which must be developed for fusion reactors, and that the experience and facilities are available at INEL to begin that work

Using the INEL site-specific plan as a community relations tool

International Nuclear Information System (INIS)

Hart, Michael; Macdonald, Don; Couch, Brad; Reuel Smith, M.

1992-01-01

Idaho National Engineering Laboratory (INEL) activities have affected, or have the potential to affect the environment. For this reason) the issues surrounding INEL activities are of interest to a broad range of people. The preparation of the INEL Site-Specific Plan (SSP) reflects the U.S. Department of Energy Idaho Field Office's (DOE-ID'S) initiative for open and clear communications with the public. The INEL SSP describes for the public DOE-ID'S plan to clean up inactive facilities and locations that were contaminated due to past waste management practices. It also discusses waste management strategies for avoiding future contamination by active operations. The SSP is an over-arching document and supplies 'the big picture' of environmental restoration and waste management activities to the public, including budget information and long-range plans. DOE-ID has been using the INEL Site-Specific Plan and its associated public comment period as a primary tool for public involvement and as way to get meaningful citizen input into DOE-ID planning. Public involvement in the INBL Site-Specific Plan has four main objectives: To inform public officials, Indian Tribes, interest groups, businesses, and individuals about current plans for environmental restoration and waste management activities at INEL; To ensure that public concerns and interests relating to environmental restoration and waste management are reflected in the SSP and DOE-ID planning; To provide flexibility so modifications can be made to DOE-ID plans and the SSP in response to changing concerns within the community, and; To ensure that DOE-ID and INEL contractors are given feedback regarding public interest in, and concerns about, the DOE-ID'S plans. To carry out these objectives, DOE-ID has implemented an aggressive public outreach effort that provides multiple opportunities for public participation in cleanup and waste management decisions. (author)

INEL test plan for evaluating waste assay systems

International Nuclear Information System (INIS)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP

INEL test plan for evaluating waste assay systems

Energy Technology Data Exchange (ETDEWEB)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

Low enrichment fuel development at INEL

International Nuclear Information System (INIS)

Newton, D.G.

1993-01-01

EG and G Idaho, Inc. is under contract to the Department of Energy to operate the Idaho National Engineering Laboratory (INEL). The INEL is located in southeastern Idaho. This facility has been operating since 1949 and was originally called the National Reactor Testing Station. Several contractors manage projects on this facility. Most projects at INEL are concerned with either reactor safety or irradiation testing. At Test Area North, for example, experiments are being conducted on the effects of loss of coolant. At the Test Reactor Area the ATR (Advanced Test Reactor) and ETR (Engineering Test Reactor) are used for irradiation testing and, of course, those of you working at Argonne will recognize the Experimental Breeder Reactors I and II. SPERT is an acronym for Special Power Excursion Reactor Test. A part of this former reactor facility has been converted into a fuel fabrication laboratory facility. At SPERT IV a miniature fabrication facility has been set up to duplicate the aluminide plate fuel processing line at Atomics International. In other words, a model of the supplier's processing has been created, so that what process changes are developed here can then be scaled up to production. The process is described showing: making UAI x powder, making compact for fuel core, making experimental fuel plate and compact assembly, inspection and testing the fuel plate. Main concern was related to possible swelling

ISDMS, Inel Scientific Data Management System

International Nuclear Information System (INIS)

Bruestle, H.R.; Russell, K.D.; Snider, D.M.; Stewart, H.D.

1993-01-01

Description of program or function: The Idaho National Engineering Laboratory (INEL) Scientific Data Management System, ISDMS, is a generalized scientific data processing system designed to meet the needs of the various organizations at the INEL. It consists of a set of general and specific processors running under the control of an executive processor which serves as the interface between the system and the user. The data requirements at the INEL are primarily for times series analyses. Data acquired at various site facilities are processed on the central CDC CYBER computers. This processing includes: data conversion, data calibration, computed parameter calculations, time series plots, and sundry other applications. The data structure used in ISDMS is CWAF, a common word addressable format. A table driven command language serves as the ISDMS control language. Execution in both batch and interactive mode is possible. All commands and their input arguments are specified in free form. ISDMS is a modular system both at the top executive or MASTER level and in the independent lower or sub-level modules. ISDMS processors were designed and isolated according to their function. This release of ISDMS, identified as 1.3A by the developers, includes processors for data conversion and reformatting for applications programs (e.g. RELAP4), interactive and batch graphics, data analysis, data storage, and archival and development aids

INEL Operable Unit 7-13 containment and stabilization configuration option

International Nuclear Information System (INIS)

Raivo, B.D.; Richardson, J.G.; Nickelson, D.F.

1993-05-01

A containment and stabilization configuration option has been developed for the Idaho National Engineering Laboratory's Subsurface Disposal Area Operable Unit 7-13, the transuranic (TRU)-contaminated waste pits and trenches. The configuration option is presented as an end-to-end system block diagram. Functional subelements are separately discussed, and technical background information, assumptions, input, high-level subelement requirements, and output are presented for each option

INEL cold test pit demonstration of improvements in information derived from non-intrusive geophysical methods over buried waste sites

International Nuclear Information System (INIS)

1993-01-01

The objectives of this research project were to lay the foundation for further improvement in the use of geophysical methods for detection of buried wastes, and to increase the information content derived from surveys. Also, an important goal was to move from mere detection to characterization of buried wastes. The technical approach to achieve these objectives consisted of: (1) Collect a data set of high spatial density; (2) Acquire data with multiple sensors and integrate the interpretations inferred from the various sensors; (3) Test a simplified time domain electromagnetic system; and (4) Develop imaging and display formats of geophysical data readily understood by environmental scientists and engineers. The breadth of application of this work is far reaching. Not only are uncontrolled waste pits and trenches, abandoned underground storage tanks, and pipelines found throughout most US DOE facilities, but also at military installations and industrial facilities. Moreover, controlled land disposal sites may contain ''hot spots'' where drums and hazardous material may have been buried. The technologies addressed by the R ampersand D will benefit all of these activities

Buried waste integrated demonstration technology integration process

International Nuclear Information System (INIS)

Ferguson, J.S.; Ferguson, J.E.

1992-04-01

A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE's Office of Technology Development (OTD)

INEL Waste and Environmental Information Integration Project approach and concepts

International Nuclear Information System (INIS)

Dean, L.A.; Fairbourn, P.J.; Randall, V.C.; Riedesel, A.M.

1994-06-01

The Idaho National Engineering, Laboratory (INEL) Waste and Environmental Information integration Project (IWEIIP) was established in December 1993 to address issues related to INEL waste and environmental information including: Data quality; Data redundancy; Data accessibility; Data integration. This effort includes existing information, new development, and acquisition activities. Existing information may not be a database record; it may be an entire document (electronic, scanned, or hard-copy), a video clip, or a file cabinet of information. The IWEIIP will implement an effective integrated information framework to manage INEL waste and environmental information as an asset. This will improve data quality, resolve data redundancy, and increase data accessibility; therefore, providing more effective utilization of the dollars spent on waste and environmental information

In-situ stabilization of TRU/mixed waste project at the INEEL

International Nuclear Information System (INIS)

Milian, L.W.; Heiser, J.H.; Adams, J.W.; Rutenkroeger, S.P.

1997-08-01

Throughout the DOE complex, buried waste poses a threat to the environment by means of contaminant transport. Many of the sites contain buried waste that is untreated, prior to disposal, or insufficiently treated, by today's standards. One option to remedy these disposal problems is to stabilize the waste in situ. This project was in support of the Transuranic/Mixed Buried Waste - Arid Soils product line of the Landfill Focus Area, which is managed currently by the Idaho National Engineering Laboratory (BNL) provided the analytical laboratory and technical support for the various stabilization activities that will be performed as part of the In Situ Stabilization of TRU/Mixed Waste project at the INEL. More specifically, BNL was involved in laboratory testing that included the evaluation of several grouting materials and their compatibility, interaction, and long-term durability/performance, following the encapsulation of various waste materials. The four grouting materials chosen by INEL were: TECT 1, a two component, high density cementious grout, WAXFIX, a two component, molten wax product, Carbray 100, a two component elastomeric epoxy, and phosphate cement, a two component ceramic. A simulated waste stream comprised of sodium nitrate, Canola oil, and INEL soil was used in this study. Seven performance and durability tests were conducted on grout/waste specimens: compressive strength, wet-dry cycling, thermal analysis, base immersion, solvent immersion, hydraulic conductivity, and accelerated leach testing

Nuclear plant analyzer development at INEL

International Nuclear Information System (INIS)

Laats, E.T.; Russell, K.D.; Stewart, H.D.

1983-01-01

The Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC) has sponsored development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes the status of the NPA project at the INEL after one year of development. When completed, the NPA will be an integrated network of analytical tools for performing reactor plant analyses. Development of the NPA in FY-1983 progressed along two parallel pathways; namely, conceptual planning and software development. Regarding NPA planning, and extensive effort was conducted to define the function requirements of the NPA, conceptual design, and hardware needs. Regarding software development conducted in FY-1983, all development was aimed toward demonstrating the basic concept and feasibility of the NPA. Nearly all software was developed and resides on the INEL twin Control Data Corporation 176 mainframe computers

End effectors and attachments for buried waste excavation equipment

International Nuclear Information System (INIS)

King, R.H.

1993-09-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that form a comprehensive remediation system for the effective and efficient remediation of buried waste. Their efforts are identified and coordinated in support of the U.S. Department of Energy (DOE), Environmental Restoration and Waste Management (ER ampersand WM) Department's needs and objectives. The present focus of BWID is to support retrieval and ex-situ treatment configuration options. Future activities will explore and support containment, and stabilization efforts in addition to the retrieval/ex situ treatment options. This report presents a literature search on the state-of-the-art in end effectors and attachments in support of excavator of buried transuranic waste. Included in the report are excavator platforms and a discussion of the various attachments. Also included is it list of vendors and specifications

Treatment of simulated INEL buried wastes using a graphite electrode DC arc furnace

International Nuclear Information System (INIS)

Surma, J.E.; Lawrence, W.E.; Titus, C.H.; Wittle, J.K.; Hamilton, R.A.; Cohn, D.R.; Rhea, D.; Thomas, P.; Woskov, P.P.

1994-08-01

A program has been established under the auspices of the Department of Energy (DOE), Office of Technology Development (OTD), to develop the graphite electrode DC arc technology for the application of treating buried heterogenous solid wastes. A three way open-quotes National Laboratory-University-Industryclose quotes partnership was formed to develop this technology in the most timely and cost effective manner. This program is presently testing a newly fabricated pilot-scale DC arc furnace with associated diagnostics at the Plasma Fusion Center at the Massachusetts Institute of Technology. Initial testing in a smaller engineering scale furnace has established the viability of this technology for the treatment of solid heterogeneous wastes. Two diagnostic tools were developed under this program which support the evaluation of the DC arc technology. The diagnostics provide for both spatially resolved temperature measurements within the furnace and real time monitoring of the furnace metal emissions

Buried Waste Integrated Demonstration Strategy Plan

International Nuclear Information System (INIS)

Kostelnik, K.M.

1993-02-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy (DOE), Environmental Restoration and Waste Management (ERWM) needs and objectives. The present focus of BWID is to support retrieval and ex situ treatment configuration options. Future activities will explore and support containment and stabilization efforts in addition to the retrieval/ex situ treatment options. Long and short term strategies of the BWID are provided. Processes for identifying technological needs, screening candidate technologies for BWID applicability, researching technical issues, field demonstrating technologies, evaluating demonstration results to determine each technology's threshold of capability, and commercializing successfully demonstrated technologies for implementation for environmental restoration also are presented in this report

Transporting fuel debris from TMI-2 to INEL

International Nuclear Information System (INIS)

Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

1986-06-01

Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 2

International Nuclear Information System (INIS)

1995-05-01

This is the second volume of this comprehensive report of the inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the Idaho National Engineering Laboratory. Appendix B contains a complete printout of contaminant inventory and other information from the CIDRA Database and is presented in volumes 2 and 3 of the report

A User's Guide to the SNF ampersand INEL EIS

International Nuclear Information System (INIS)

1995-01-01

This User's Guide is intended to help you find information in the SNF and INEL EIS (that's short for US Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement). The first section of this Guide gives you a brief overview of the SNF ampersand INEL EIS., The second section is organized to help you find specific information in the Environmental Impact Statement -- whether you're interested in a management alternative, a particular site (such as Hanford), or a discipline (such as land use or water quality)

Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

International Nuclear Information System (INIS)

Scarpellino, C.D.; Sill, C.W.

1986-01-01

The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

Environment, Safety and Health progress assessment of the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

1993-08-01

The ES ampersand H Progress Assessments are part of the Department's continuous improvement process throughout DOE and its contractor organizations. The purpose of the INEL ES ampersand H Progress Assessment is to provide the Department with concise independent information on the following: (1) change in culture and attitude related to ES ampersand H activities; (2) progress and effectiveness of the ES ampersand H corrective actions resulting from previous Tiger Team Assessments; (3) adequacy and effectiveness of the ES ampersand H self-assessment programs of the DOE line organizations and the site management and operating contractor; and (4) effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems. It is not intended that this Progress Assessment be a comprehensive compliance assessments of ES ampersand H activities. The points of reference for assessing programs at the INEL were, for the most part, the 1991 INEL Tiger Team Assessment, the INEL Corrective Action Plan, and recent appraisals and self-assessments of INEL. Horizontal and vertical reviews of the following programmatic areas were conducted: Management: Corrective action program; self-assessment; oversight; directives, policies, and procedures; human resources management; and planning, budgeting, and resource allocation. Environment: Air quality management, surface water management, groundwater protection, and environmental radiation. Safety and Health: Construction safety, worker safety and OSHA, maintenance, packaging and transportation, site/facility safety review, and industrial hygiene

Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL

International Nuclear Information System (INIS)

Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

1996-09-01

The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035

The Stored Waste Examination Pilot Plant program at the INEL

International Nuclear Information System (INIS)

McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

1983-01-01

Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

INEL metal recycle radioactive scrap metal survey report

International Nuclear Information System (INIS)

Funk, D.M.

1994-09-01

DOE requested that inventory and characterization of radioactive scrap metal (RSM) be conducted across the DOE complex. Past studies have estimated the metal available from unsubstantiated sources. In meetings held in FY-1993, with seven DOE sites represented and several DOE-HQ personnel present, INEL personnel discovered that these numbers were not reliable and that large stockpiles did not exist. INEL proposed doing in-field measurements to ascertain the amount of RSM actually available. This information was necessary to determine the economic viability of recycling and to identify feed stock that could be used to produce containers for radioactive waste. This inventory measured the amount of RSM available at the selected DOE sites. Information gathered included radionuclide content and chemical form, general radiation field, alloy type, and mass of metal

Alternative disposal options for transuranic waste

International Nuclear Information System (INIS)

Loomis, G.G.

1994-01-01

Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lens around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area

RELAP5/MOD1-EUR evaluation. Comparison with the INEL original version

International Nuclear Information System (INIS)

Mazzantini, O.A.

1990-01-01

In this work, the values calculated from two versions of the RELAP5/MOD1 code are compared with those measured in different tests. The first version of RELAP5 is the cycle 19 of the original version of INEL (RELAP5/MOD1-INEL) and the second version improved by EURATOM (RELAP5/MOD1-EUR) which was transferred to ENACE through agreements made with SIEMENS/KWU. (Author) [es

Human applications of the INEL patient treatment planning system

International Nuclear Information System (INIS)

Wheeler, F.; Wessol, D.; Atkinson, C.; Nigg, D.

1995-01-01

During the past few years, murine and large animal research, as well as human studies have provided data to the point where human clinical trials have been initiated at the BMRR using BPA-F for gliomas and at the Massachusetts Institute of Technology Reactor (MITR) using BPA for melanomas of the extremeties. It is expected that glioma trials using BSH will proceed soon at the Petten High Flux Reactor (HFR) in the Netherlands. The first human glioma epithermal boron neutron capture therapy application was performed at the BMRR in the fall of 1994. This was a collaborative effort by BNL, Beth Israel Manhattan hospital, and INEL. The INEL planning system was chosen to perform dose predictions for this application

1990 INEL national emission standards for hazardous air pollutants

International Nuclear Information System (INIS)

1990-05-01

The Environmental Protection Agency issued on December 15, 1989 final rules governing air emissions of radionuclides. Requirements concerning radionuclide emissions from Department of Energy Facilities are addressed under Title 40, Code Federal Regulations (CFR) 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides other Than Radon From Department of Energy Facilities.'' Section 61.94 of the regulations require that each DOE facility submit on an annual basis a report documenting compliance with the Subpart H requirements. This report addresses the section 61.94 reporting requirements for operations at the Idaho National Engineering Laboratory (INEL) for calendar year 1990. The Idaho Operations Office of the Department of Energy is the primary contact concerning NESHAPs compliance at the INEL

TMI-2 core-examination program: INEL facilities-readiness study

International Nuclear Information System (INIS)

McLaughlin, T.B.

1982-09-01

This document is a review of the Idaho National Engineering Laboratory's (INEL) remote handling facilities. Their availability and readiness to conduct examination and analyses of TMI-2 core samples was determined. Examination of these samples require that the facilities be capable of receiving commercial casks, unloading canisters from the casks, opening the canisters, handling the fuel debris and assemblies, and performing various examinations. The documentation that was necessary for the INEL to have before the receipt of the core material was identified. The core information was also required for input to these documents. The costs, schedules, and a preliminary-project plan are presented for the tasks which are identified as prerequisites to the receipt of the first core sample

Processing and certification of defense transuranic waste at the INEL

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cargo, C.H.; McKinley, K.B.; Smith, T.H.; Anderson, B.C.

1984-01-01

Since 1970, defense-generated transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the US Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste form the INEL. To support this objective, the Stored Waste Examination Pilot Plant (SWEPP) and the Process Experimental Pilot Plant (PREPP) are currently being constructed. SWEPP will certify waste, using nondestructive examination techniques, for shipment to the Waste Isolation Pilot Plant (WIPP). PREPP will process uncertifiable waste into a certifiable waste form. 3 references

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

International Nuclear Information System (INIS)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

Energy Technology Data Exchange (ETDEWEB)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

The INEL approach: Environmental Restoration Program management and implementation methodology

International Nuclear Information System (INIS)

1996-01-01

The overall objectives of the INEL Environmental Restoration (ER) Program management approach are to facilitate meeting mission needs through the successful implementation of a sound, and effective project management philosophy. This paper outlines the steps taken to develop the ER program, and explains further the implementing tools and processes used to achieve what can be viewed as fundamental to a successful program. The various examples provided will demonstrate how the strategies for implementing these operating philosophies are actually present and at work throughout the program, in spite of budget drills and organizational changes within DOE and the implementing contractor. A few of the challenges and successes of the INEL Environmental Restoration Program have included: a) completion of all enforceable milestones to date, b) acceleration of enforceable milestones, c) managing funds to reduce uncosted obligations at year end by utilizing greater than 99% of FY-95 budget, d) an exemplary safety record, e) developing a strategy for partial Delisting of the INEL by the year 2000, f) actively dealing with Natural Resource Damages Assessment issues, g) the achievement of significant project cost reductions, h) and implementation of a partnering charter and application of front end quality principles

Evaluation of seismic criteria used in design of INEL facilities

International Nuclear Information System (INIS)

Young, G.A.

1977-01-01

This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities

Computer modeling of jet mixing in INEL waste tanks

International Nuclear Information System (INIS)

Meyer, P.A.

1994-01-01

The objective of this study is to examine the feasibility of using submerged jet mixing pumps to mobilize and suspend settled sludge materials in INEL High Level Radioactive Waste Tanks. Scenarios include removing the heel (a shallow liquid and sludge layer remaining after tank emptying processes) and mobilizing and suspending solids in full or partially full tanks. The approach used was to (1) briefly review jet mixing theory, (2) review erosion literature in order to identify and estimate important sludge characterization parameters (3) perform computer modeling of submerged liquid mixing jets in INEL tank geometries, (4) develop analytical models from which pump operating conditions and mixing times can be estimated, and (5) analyze model results to determine overall feasibility of using jet mixing pumps and make design recommendations

INEL BNCT Program: Volume 5, No. 9

Energy Technology Data Exchange (ETDEWEB)

Ackermann, A.L. (ed.)

1991-01-01

This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory's (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

INEL oversight program. Quarterly technical progress report, January 1993--December 1993

International Nuclear Information System (INIS)

1994-01-01

Idaho's successful lawsuit over shipments of spent nuclear fuel is a major milestone for 1993. The challenge forced the U.S. Department of Energy to cease all shipments of spent nuclear fuel to the Idaho National Engineering Laboratory until a site-wide environmental impact statement is completed. This agreement is a significant victory in Idaho's battle to hold the federal government responsible for its actions and force compliance with applicable laws. Much of the State's INEL-related activity in 1993 focused on ensuring that INEL operations are conducted in a manner that protects public health and the environment

Ventral Slit Scrotal Flap: A New Outpatient Surgical Option for Reconstruction of Adult Buried Penis Syndrome.

Science.gov (United States)

Westerman, Mary E; Tausch, Timothy J; Zhao, Lee C; Siegel, Jordan A; Starke, Nathan; Klein, Alexandra K; Morey, Allen F

2015-06-01

We present a novel technique using ventral slit with scrotal skin flaps (VSSF) for the reconstruction of adult buried penis without skin grafting. An initial ventral slit is made in the phimotic ring, and the penis is exposed. To cover the defect in the ventral shaft skin, local flaps are created by making a ventral midline scrotal incision with horizontal relaxing incisions. The scrotal flaps are rotated to resurface the ventral shaft. Clinical data analyzed included preoperative diagnoses, length of stay, blood loss, and operative outcomes. Complications were also recorded. Fifteen consecutive patients with a penis trapped due to lichen sclerosus (LS) or phimosis underwent repair with VSSF. Each was treated in the outpatient setting with no perioperative complications. Mean age was 51 years (range, 26-75 years), and mean body mass index was 42.6 kg/m(2) (range, 29.8-53.9 kg/m(2)). The majority of patients (13 of 15, 87%) had a pathologic diagnosis of LS. Mean estimated blood loss was 57 cc (range, 25-200 cc), mean operative time was 83 minutes (range, 35-145 minutes), and all patients were discharged on the day of surgery. The majority of patients (11 of 15, 73.3%) remain satisfied with their results and have required no further intervention. Recurrences in 3 of 15 (20.0%) were due to LS, panniculus migration, and concealment by edematous groin tissue; 2 of these patients underwent subsequent successful skin grafting. VSSF is a versatile, safe, and effective reconstructive option in appropriately selected patients with buried penis, which enables reconstruction of penile shaft skin defects without requiring complex skin grafting. Copyright © 2015 Elsevier Inc. All rights reserved.

Design of buried concrete encasements

International Nuclear Information System (INIS)

Drake, R.M.

1989-01-01

The operation of many Department of Energy (DOE) sites requires the transfer of radioactive liquid products from one location to another. DOE Order 6430.1A requires that the transfer pipelines be designed and constructed so that any leakage can be detected and contained before it reaches the environment. One design option often considered to meet this requirement is to place the pipeline in a stainless steel-lined, buried concrete encasement. This provides the engineer with the design challenge to integrate standard structural design principles with unique DOE requirements. The complete design of a buried concrete encasement must consider seismic effects, leak detection, leak confinement, radiation shielding, thermal effects, pipe supports, and constructability. This paper contains a brief discussion of each of these design considerations, based on experience gained during the design of concrete encasements for the Process Facilities Modifications (PFM) project at Hanford

Development of waste chargeback systems at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Piscitella, R.R.

1996-02-01

Chargeback systems have been discussed (and cussed), tried, modified, and in some cases, successfully implemented in the DOE complex over the years. With the current emphasis on ''Doing business like a private company,'' there has been renewed interest at the Idaho National Engineering Laboratory (INEL) in implementing chargeback systems for waste management activities. The most recent activities relating to chargeback at the INEL started the summer of 1995 with direction from waste operations management to develop and pilot test a chargeback system. This paper presents the results of this effort to date

DOE complex buried waste characterization assessment

International Nuclear Information System (INIS)

Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

1993-01-01

The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m 3 of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993)

The INEL Tritium Research Facility

International Nuclear Information System (INIS)

Longhurst, G.R.

1990-01-01

The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.)

The INEL Tritium Research Facility

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R. (Idaho National Engineering Lab., Idaho Falls (USA))

1990-06-01

The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.).

Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Garcia, E.C.; Porter, C.L.; Wallace, M.T.

1993-01-01

August 18, 1992 the EPA published the final revised treatment standards for hazardous debris, including mixed debris. Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were evaluated against the debris rule to determine an overall treatment strategy for the INEL. Seven types of debris were identified: Combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

Managing previously disposed waste to today's standards

International Nuclear Information System (INIS)

1990-01-01

A Radioactive Waste Management Complex (RWMC) was established at the Idaho National Engineering Laboratory (INEL) in 1952 for controlled disposal of radioactive waste generated at the INEL. Between 1954 and 1970 waste characterized by long lived, alpha emitting radionuclides from the Rocky Flats Plant was also buried at this site. Migration of radionuclides and other hazardous substances from the buried Migration of radionuclides and other hazardous substances from the buried waste has recently been detected. A Buried Waste Program (BWP) was established to manage cleanup of the buried waste. This program has four objectives: (1) determine contaminant sources, (2) determine extent of contamination, (3) mitigate migration, and (4) recommend an alternative for long term management of the waste. Activities designed to meet these objectives have been under way since the inception of the program. The regulatory environment governing these activities is evolving. Pursuant to permitting activities under the Resource Conservation and Recovery Act (RCRA), the Department of Energy (DOE) and the Environmental Protection Agency (EPA) entered into a Consent Order Compliance Agreement (COCA) for cleanup of past practice disposal units at the INEL. Subsequent to identification of the RWMC as a release site, cleanup activities proceeded under dual regulatory coverage of RCRA and the Atomic Energy Act. DOE, EPA, and the State of Idaho are negotiating a RCRA/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interagency Agreement (IAG) for management of waste disposal sites at the INEL as a result of the November 1989 listing of the INEL on the National Priority List (NPL). Decision making for selection of cleanup technology will be conducted under the CERCLA process supplemented as required to meet the requirements of the National Environmental Policy Act (NEPA). 7 figs

INEL integrated spent nuclear fuel consolidation task team report

International Nuclear Information System (INIS)

Henry, R.N.; Clark, J.H.; Chipman, N.A.

1994-01-01

This document describes a draft plan and schedule to consolidate spent nuclear fuel (SNF) and special nuclear material (SNW) from aging storage facilities throughout the Idaho National Engineering Laboratory (INEL) to the Idaho Chemical Processing Plant (ICPP) in a safe, cost-effective, and expedient manner. A fully integrated and resource-loaded schedule was developed to achieve consolidation as soon as possible. All of the INEL SNF and SNM management task, projects, and related activities from fiscal year 1994 to the end of the consolidation period are logic-tied and integrated with each other. The schedule and plan are presented to initiate discussion of their implementation, which is expected to generate alternate concepts that can be evaluated using the methodology described in this report. Three perturbations to consolidating SNF as soon as possible are also explored. If the schedule is executed as proposed, the new and on-going consolidation activities will require about 6 years to complete and about $25.3M of additional funding. Reduced annual operating costs are expected to recover the additional investment in about 6.4 years. The total consolidation program as proposed will cost about $66.8M and require about 6 years to recover via reduced operating costs from retired SNF/SNM storage facilities. Detailed schedules and cost estimates for the Test Reactor Area Materials Test Reactor canal transfers are included as an example of the level of detail that is typical of the entire schedule (see Appendix D). The remaining work packages for each of the INEL SNF consolidation transfers are summarized in this document. Detailed cost and resource information is available upon request for any of the SNF consolidation transfers

Removal of overburden soils from buried waste sites

International Nuclear Information System (INIS)

Rice, P.M.

1994-01-01

Transuranic (TRU) waste buried in pits and trenches is covered with a soil cap, or overburden, to shed water. During retrieval operations, the overburden (expected to be clean) must be removed carefully to avoid breaching the soil/waste matrix within a pit or trench and to confine any possible local spot contamination. This necessitates removal in precise (7.6- to 15.25-cm) increments with a high degree of accuracy. In addition, during overburden removal the overburden must be characterized to a depth that exceeds each cut of soil. A field demonstration was conducted to evaluate a technology for removing overburden soils a the Radioactive Waste Management Complex (RWMC), Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL). The demonstration evaluated equipment performance and techniques for removing overburden soil and controlling contamination and dust. To evaluate the performance of these techniques during removal operations, personnel took air particulate samples, physical measurements of the soil cuts, maneuverability measurements, and rate of soil removal data. The overburden was spiked at specific locations and depths with rare earth tracers to provide a medium for evaluating samples. Analysis to determine the precision and accuracy of the soil removal, amount of dust generated, and potential spread of contamination was performed

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INEL Oversight Committee

International Nuclear Information System (INIS)

King, B.; Bloomsburg, G.; Horn, D.; Liou, J.; Finnie, J.

1992-01-01

During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these locations. The RWMC has received much attention in the last few years as the result of being priority No. 1 in the superfund clean up of the INEL. A considerable amount of data are available describing the unsaturated zone at the RWMC. These data have been collected to field calibrate a radionuclide migration model for the RWMC

A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 1

International Nuclear Information System (INIS)

1995-05-01

This report presents a comprehensive inventory of the radiological and nonradiological contaminants in waste buried or projected to be buried from 1984 through 2003 in the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The project to compile the inventory is referred to as the recent and projected data task. The inventory was compiled primarily for use in a baseline risk assessment under the Comprehensive Environmental Response, Compensation, and Liability Act. The compiled information may also be useful for environmental remediation activities that might be necessary at the RWMC. The information that was compiled has been entered into a database termed CIDRA-the Contaminant Inventory Database for Risk Assessment. The inventory information was organized according to waste generator and divided into waste streams for each generator. The inventory is based on waste information that was available in facility operating records, technical and programmatic reports, shipping records, and waste generator forecasts. Additional information was obtained by reviewing the plant operations that originally generated the waste, by interviewing personnel formerly employed as operators, and by performing nuclear physics and engineering calculations. In addition to contaminant inventories, information was compiled on the physical and chemical characteristics and the packaging of the 99 waste streams. The inventory information for waste projected to be buried at the SDA in the future was obtained from waste generator forecasts. The completeness of the contaminant inventories was confirmed by comparing them against inventories in previous reports and in other databases, and against the list of contaminants detected in environmental monitoring performed at the RWMC

INEL studies concerning solidification of low-level waste in cement

International Nuclear Information System (INIS)

Mandler, J.W.

1989-01-01

The Idaho National Engineering Laboratory (INEL) has performed numerous studies addressing issues concerning the solidification of low-level radioactive waste in cement. These studies have been performed for both the Nuclear Regulatory Commission (NRC) and the Department of Energy (DOE). This short presentation will only outline the major topics addressed in some of these studies, present a few conclusions, and identify some of the technical concerns we have. More details of the work and pertinent results will be given in the Working Group sessions. The topics that have been addressed at the INEL which are relevant to this Workshop include (1) solidification of ion-exchange resins and evaporator waste in cement at commercial nuclear power plants, (2) leachability and compressive strength of power plant waste solidified in cement, (3) suggested guidelines for preparation of a solid waste process control program (PCP), (4) cement solidification of EPICOR-II resin wastes, and (5) performance testing of cement-solidified EPICOR-II resin wastes

1983 Borah Peak earthquake and INEL structural performance

International Nuclear Information System (INIS)

Gorman, V.W.; Guenzler, R.C.

1983-12-01

At 8:06 a.m. Mountain Daylight Time on October 28, 1983 an earthquake registering 7.3 on the Richter Magnitude scale occurred about 30 km northwest of the town of Mackay, in central Idaho. This report describes the event and associated effects and the responses of facilities at Idaho National Engineering Laboratory (INEL), located approximately 100 km. from the epicenter, to ground motion. 21 references, 36 figures, 5 tables

Buried waste remediation: A new application for in situ vitrification

International Nuclear Information System (INIS)

Kindle, C.H.; Thompson, L.E.

1991-04-01

Buried wastes represent a significant environmental concern and a major financial and technological challenge facing many private firms, local and state governments, and federal agencies. Numerous radioactive and hazardous mixed buried waste sites managed by the US Department of Energy (DOE) require timely clean up to comply with state or federal environmental regulations. Hazardous wastes, biomedical wastes, and common household wastes disposed at many municipal landfills represent a significant environmental health concern. New programs and regulations that result in a greater reduction of waste via recycling and stricter controls regarding generation and disposal of many wastes will help to stem the environmental consequences of wastes currently being generated. Groundwater contamination, methane generation, and potential exposures to biohazards and chemically hazardous materials from inadvertent intrusion will continue to be potential environmental health consequences until effective and permanent closure is achieved. In situ vitrification (ISV) is being considered by the DOE as a permanent closure option for radioactive buried waste sites. The results of several ISV tests on simulated and actual buried wastes conducted during 1990 are presented here. The test results illustrate the feasibility of the ISV process for permanent remediation and closure of buried waste sites in commercial landfills. The tests were successful in immobilizing or destroying hazardous and radioactive contaminants while providing up to 75 vol % waste reduction. 6 refs., 7 figs., 5 tabs

The proposed INEL intense slow positron source, beam line, and positron microscope facility

International Nuclear Information System (INIS)

Makowitz, H.; Denison, A.B.; Brown, B.

1993-01-01

A program is currently underway at the Idaho National Engineering Laboratory (INEL) to design and construct an Intense Slow Positron Beam Facility with an associated Positron Microscope. Positron beams have been shown to be valuable research tools and have potential application in industrial processing and nondestructive evaluation (microelectronics, etc.). The limit of resolution or overall usefulness of the technique has been limited because of lack of sufficient intensity. The goal of the INEL positron beam is ≥ 10 12 slow e+/s over a 0.03 cm diameter which represents a 10 3 to 10 4 advancement in beam current over existing beam facilities. The INEL is an ideal site for such a facility because of the nuclear reactors capable of producing intense positron sources and the personnel and facilities capable of handling high levels of radioactivity. A design using 58 Co with moderators and remoderators in conjunction with electrostatic positron beam optics has been reached after numerous computer code studies. Proof-of-principle electron tests have demonstrated the feasibility of the large area source focusing optics. The positron microscope development is occurring in conjunction with the University of Michigan positron microscope group. Such a Beam Facility and associated Intense Slow Positron Source (ISPS) can also be utilized for the generation and study of positron, and positron electron plasmas at ≤ 10 14 particles/cm 3 with plasma temperatures ranging from an eV to many keV, as well as an intense x-ray source via positron channeling radiation. The possibility of a tunable x-ray laser based on channeling positron radiation also exists. In this discussion the authors will present a progress report on various activities associated with the INEL ISPS

Final report for the cryogenic retrieval demonstration

International Nuclear Information System (INIS)

Valentich, D.J.; Yokuda, E.L.

1992-09-01

This report documents a demonstration of a proposed buried transuranic waste retrieval concept that uses cryogenic ground freezing and remote excavation. At the Idaho National Engineering Laboratory (INEL), there are over 8 million ft 3 of intermingled soil and transuranic (TRU) wastes in shallow land burial, and retrieval of the material is one of the options being considered by the Buried Waste Integrated Demonstration for the Environmental Restoration program. Cryogenically freezing contaminated soil and buried waste has been proposed as a way to greatly reduce or eliminate the climate the threat of contamination spread during retrieval activities. In support of this idea, a demonstration of an innovative ground freezing and retrieval technology was performed at the INEL. This initial demonstration was held near the Radioactive Waste Management Complex at a ''cold test pit'' that was built in 1988 as a test bed for the demonstration of retrieval contamination control technologies. This pit is not contaminated with any radioactive or hazardous wastes. Barrels and boxes filled with metals, plastics, tools, paper, cloth, etc. configured in the same manner as expected in contaminated pits and trenches are buried at the cold test pit. After design, fabrication, and shop testing, Sonsub mobilized to the field in early July 1992 to perform the field demonstration. It was planned to freeze and extract four pits, each 9 x 9 x 10 ft. Each pit represented a different configuration of buried waste (stacked boxes, stacked barrels, random dumped barrels and boxes, and random dumped barrels). Sonsub's proposed technology consisted of driving a series of freeze pipes into the soil and waste, using liquid nitrogen to freeze the mass, and extracting the soil and debris using a series of remote operated, bridge crane mounted tools. In conjunction with the freezing and removal activities, temperature and moisture measurements, and air monitoring were performed

Final report for the cryogenic retrieval demonstration

Energy Technology Data Exchange (ETDEWEB)

Valentich, D.J.; Yokuda, E.L.

1992-09-01

This report documents a demonstration of a proposed buried transuranic waste retrieval concept that uses cryogenic ground freezing and remote excavation. At the Idaho National Engineering Laboratory (INEL), there are over 8 million ft{sup 3} of intermingled soil and transuranic (TRU) wastes in shallow land burial, and retrieval of the material is one of the options being considered by the Buried Waste Integrated Demonstration for the Environmental Restoration program. Cryogenically freezing contaminated soil and buried waste has been proposed as a way to greatly reduce or eliminate the climate the threat of contamination spread during retrieval activities. In support of this idea, a demonstration of an innovative ground freezing and retrieval technology was performed at the INEL. This initial demonstration was held near the Radioactive Waste Management Complex at a ``cold test pit`` that was built in 1988 as a test bed for the demonstration of retrieval contamination control technologies. This pit is not contaminated with any radioactive or hazardous wastes. Barrels and boxes filled with metals, plastics, tools, paper, cloth, etc. configured in the same manner as expected in contaminated pits and trenches are buried at the cold test pit. After design, fabrication, and shop testing, Sonsub mobilized to the field in early July 1992 to perform the field demonstration. It was planned to freeze and extract four pits, each 9 {times} 9 {times} 10 ft. Each pit represented a different configuration of buried waste (stacked boxes, stacked barrels, random dumped barrels and boxes, and random dumped barrels). Sonsub`s proposed technology consisted of driving a series of freeze pipes into the soil and waste, using liquid nitrogen to freeze the mass, and extracting the soil and debris using a series of remote operated, bridge crane mounted tools. In conjunction with the freezing and removal activities, temperature and moisture measurements, and air monitoring were performed.

Final report for the cryogenic retrieval demonstration

Energy Technology Data Exchange (ETDEWEB)

Valentich, D.J.; Yokuda, E.L.

1992-09-01

This report documents a demonstration of a proposed buried transuranic waste retrieval concept that uses cryogenic ground freezing and remote excavation. At the Idaho National Engineering Laboratory (INEL), there are over 8 million ft[sup 3] of intermingled soil and transuranic (TRU) wastes in shallow land burial, and retrieval of the material is one of the options being considered by the Buried Waste Integrated Demonstration for the Environmental Restoration program. Cryogenically freezing contaminated soil and buried waste has been proposed as a way to greatly reduce or eliminate the climate the threat of contamination spread during retrieval activities. In support of this idea, a demonstration of an innovative ground freezing and retrieval technology was performed at the INEL. This initial demonstration was held near the Radioactive Waste Management Complex at a cold test pit'' that was built in 1988 as a test bed for the demonstration of retrieval contamination control technologies. This pit is not contaminated with any radioactive or hazardous wastes. Barrels and boxes filled with metals, plastics, tools, paper, cloth, etc. configured in the same manner as expected in contaminated pits and trenches are buried at the cold test pit. After design, fabrication, and shop testing, Sonsub mobilized to the field in early July 1992 to perform the field demonstration. It was planned to freeze and extract four pits, each 9 [times] 9 [times] 10 ft. Each pit represented a different configuration of buried waste (stacked boxes, stacked barrels, random dumped barrels and boxes, and random dumped barrels). Sonsub's proposed technology consisted of driving a series of freeze pipes into the soil and waste, using liquid nitrogen to freeze the mass, and extracting the soil and debris using a series of remote operated, bridge crane mounted tools. In conjunction with the freezing and removal activities, temperature and moisture measurements, and air monitoring were

A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

1993-07-01

The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

A document review to characterize Atomic International SNAP fuels shipped to INEL 1966--1973

International Nuclear Information System (INIS)

Wahnschaffe, S.D.; Lords, R.E.; Kneff, D.W.; Nagel, W.E.; Pearlman, H.; Schaubert, V.J.

1995-09-01

This report provides the results of a document search and review study to obtain information on the spent fuels for the following six Nuclear Auxiliary Power (SNAP) reactor cores now stored at the Idaho National Engineering Laboratory (INEL): SNAP-2 Experimental Reactor, SNAP-2 Development Reactor, SNAP-10A Ground Test Reactor, SNAP-8 Experimental Reactor, SNAP-8 Development Reactor, and Shield Test Reactor. The report also covers documentation on SNAP fuel materials from four in-pile materials tests: NAA-82-1, NAA-115-2, NAA-117-1, and NAA-121. Pieces of these fuel materials are also stored at INEL as part of the SNAP fuel shipments

Modeling in situ vitrification

International Nuclear Information System (INIS)

Mecham, D.C.; MacKinnon, R.J.; Murray, P.E.; Johnson, R.W.

1990-01-01

In Situ Vitrification (ISV) process is being assessed by the Idaho National Engineering Laboratory (INEL) to determine its applicability to transuranic and mixed wastes buried at INEL'S Subsurface Disposal Area (SDA). This process uses electrical resistance heating to melt waste and contaminated soil in place to produce a durable glasslike material that encapsulates and immobilizes buried wastes. This paper outlines the requirements for the model being developed at the INEL which will provide analytical support for the ISV technology assessment program. The model includes representations of the electric potential field, thermal transport with melting, gas and particulate release, vapor migration, off-gas combustion and process chemistry. The modeling objectives are to help determine the safety of the process by assessing the air and surrounding soil radionuclides and chemical pollution hazards, the nuclear criticality hazard, and the explosion and fire hazards, help determine the suitability of the ISV process for stabilizing the buried wastes involved, and help design laboratory and field tests and interpret results. 3 refs., 2 figs., 1 tab

INEL BNCT Program: Volume 5, No. 9. Bulletin, September 1991

Energy Technology Data Exchange (ETDEWEB)

Ackermann, A.L. [ed.

1991-12-31

This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory`s (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.

INEL RCRA [Resource Conservation and Recovery Act] permit for incineration of hazardous waste: Status report

International Nuclear Information System (INIS)

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

1987-01-01

The Waste Experimental Reduction Facility (WERF) was constructed to reduce the volume of low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). To address the problem of radioactively contaminated ignitable hazardous waste resulting from INEL activities, a development program was carried out to evaluate WERF's ability to meet the regulated criteria for incinerating liquid and solid ignitable waste. Concurrently, INEL submitted its hazardous waste Part B application under the Resource Conservation and Recovery Act (RCRA). As required, and as a major step in the permitting process, the WERF incinerator portion of the permit application included a proposed trial burn, which is a demonstration test of the incinerator's ability to destroy hazardous materials. The trial burn plan was designed to demonstrate the system performance for liquid and solid ignitable wastes at three operating conditions, using a prepared mix of materials representative of waste to be processed. EPA Region X reviewed and commented on the plan prior to the trial burn. Results of the liquid feed trial burn showed a greater than 97% probability of meeting the RCRA-dictated DRE value for chlorinated solvents and a greater than 99% probability for nonchlorinated solvents. Nonchlorinated solid waste results were calculated at a 93% probability of meeting the required DRE, with a 75% probability for chlorinated solid wastes. In addition, the incinerator DRE continued to improve long after the assumed pre-test equilibrium period had ended. The trial burn demonstrates that the WERF incinerator can safely and adequately destroy ignitable hazardous and mixed waste and provides a significant enhancement of the INEL's waste management system

Preparation and leaching of radioactive INEL waste forms

International Nuclear Information System (INIS)

Schuman, R.P.; Welch, J.M.; Staples, B.A.

1982-01-01

The purpose of this study is to prepare and leach test ceramic and glass waste form specimens produced from actual transuranic waste sludges and high-level waste calcines, respectively. Description of wastes, specimen fabrication, leaching procedure, analysis of leachates and results are discussed. The conclusion is that radioactive waste stored at INEL can be readily incorporated in fused ceramic and glass forms. Initial leach testing results indicate that these forms show great promise for safe long-term containment of radioactive wastes

Summary of INEL research on the iron-enriched basalt waste form

International Nuclear Information System (INIS)

Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1992-01-01

This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B 2 0 3 , Na, and SiO 2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

ISOCELL trademark proof-of-concept for retrieval of wastes and contaminated soil

International Nuclear Information System (INIS)

Chatwin, T.D.; Krieg, R.K.

1992-01-01

ISOCELL TM cryogenic technology is designed to immobilize buried hazardous, radioactive, and mixed waste and contaminated soil by creating a block of frozen waste and soil that can be safely retrieved, stored, transported, and treated with a minimum of dust or aerosol production. A ''proof-of-concept'' test of the ISOCELL process was conducted in clean soil by RKK, Ltd., for the Idaho National Engineering Laboratory (INEL). Results indicate ISOCELL technology successfully froze moist soil into a solid block capable of being lifted and retrieved. Test conditions were compared to characteristics of possible buried waste sites in the INEL

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1991-12-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. This document, Volume 1, identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues

Use of an isotope separator at the INEL

International Nuclear Information System (INIS)

Anderl, R.A.

1977-01-01

An electromagnetic isotope separator with a retardation lens as a collector was used to prepare highly enriched samples of Nd-143, -144, -145, -146, -148, -150, Sm-147, -149; Eu-151, -152, -153, -154. The 50 μg to 75 μg samples, deposited on 1 mil nickel foil or 0.5 mil vanadium foil, are part of a sample set to be irradiated in EBR-II as part of an integral-capture cross-section measurement program at the INEL. The isotope separator and the apparatus used for the sample preparation are described

Summary of ground water and surface water flow and contaminant transport computer codes used at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Bandy, P.J.; Hall, L.F.

1993-03-01

This report presents information on computer codes for numerical and analytical models that have been used at the Idaho National Engineering Laboratory (INEL) to model ground water and surface water flow and contaminant transport. Organizations conducting modeling at the INEL include: EG ampersand G Idaho, Inc., US Geological Survey, and Westinghouse Idaho Nuclear Company. Information concerning computer codes included in this report are: agency responsible for the modeling effort, name of the computer code, proprietor of the code (copyright holder or original author), validation and verification studies, applications of the model at INEL, the prime user of the model, computer code description, computing environment requirements, and documentation and references for the computer code

The Intense Slow Positron Source concept: A theoretical perspective on a proposed INEL Facility

International Nuclear Information System (INIS)

Makowitz, H.; Abrashoff, J.D.; Landman, W.H.; Albano, R.K.; Tajima, T.

1992-01-01

An analysis has been performed of the INEL Intense Slow Positron Source (ISPS) concept. The results of the theoretical study are encouraging. A full-scale device with a monoenergetic 5 KeV positron beam of ≥10 12 e + /s on a ≤0.03-cmdiameter target appears feasible and can be obtained within the existing infrastructure of INEL reactor facilities. A 30.0-cm-diameter, large area source dish, moderated at first with thin crystalline W films and later by solid Ne, is proposed as the initial device in order to explore problems with a facility scale system. A demonstration scale beam at ≥10 10 slow e + /s is proposed using a 58 Co source plated on a 6-cm-diameter source dish insert, placed in a 30- cm adapter

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

International Nuclear Information System (INIS)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

Energy Technology Data Exchange (ETDEWEB)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

Management of Pit 9 - highlights of accomplishments and lessons learned to date

International Nuclear Information System (INIS)

Schwartz, F.G.

1995-01-01

The Pit 9 project is a U.S. Department of Energy prototype full scale demonstration to retrieve and treat buried mixed transuranic waste. The project is being managed by the DOE-Idaho Environmental Restoration Program, in conjunction with the Environmental Protection Agency Region 10 and the state of Idaho, under the Idaho National Engineering Laboratory Federal Facility Agreement and Consent Order. Pit 9 is located in the northeast corner of the Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). The Pit 9 project was conceived out of the need to determine capabilities to cost effectively retrieve and treat buried radioactive and radioactive mixed waste, and obtain characterization and contaminant migration data for buried waste at the INEL. Waste was disposed in Pit 9 from November 1967 to June 1969. Pit 9, at about 380 feet by 125 feet, represents approximately one acre of surface area of the 88 acre SDA. The pit contains approximately 350,000 ft 3 of soil beneath and between the buried waste and about 250,000 ft 3 of overburden soil. The average depth of the pit from soil surface to bedrock is approximately 17.5 feet. Approximately 110,000 ft 3 of transuranic (TRU) contaminated mixed wastes from Rocky Flats and approximately 40,000 ft 3 of low level and mixed wastes from the INEL were buried in Pit 9 during this period. Pit 9 is estimated to contain over 30,000 gallons of organics (over 30% of the total organic inventory in the SDA) and approximately 66 pounds of TRU radionuclides (between 3% and 4% of the total TRU inventory in the SDA). Pit 9 was selected as a demonstration site because it was one of the last disposal pits at the INEL to receive Rocky Flats waste, disposal records are better for Pit 9 than for disposal pits and trenches from earlier points in time, and the wastes in Pit 9 are representative of the wastes disposed in the SDA

Criticality safety for TMI-2 canister storage at INEL

International Nuclear Information System (INIS)

Jones, R.R.; Briggs, J.B.; Ayers, A.L. Jr.

1986-01-01

Canisters containing Three Mile Island Unit 2 (TMI-2) core debris will be researched, stored, and prepared for final disposition at the Idaho National Engineering Laboratory (INEL). The canisters will be placed into storage modules and assembled into a storage rack, which will be located in the Test Area North (TAN) storage pool. Criticality safety calculations were made (a) to ensure that the storage rack is safe for both normal and accident conditions and (b) to determine the effects of degradation of construction materials (Boraflex and polyethylene) on criticality safety

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

International Nuclear Information System (INIS)

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

Buried Waste Integrated Demonstration

International Nuclear Information System (INIS)

1994-03-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that offer promising solutions to the problems associated with the remediation of buried waste. BWID addresses the difficult remediation problems associated with DOE complex-wide buried waste, particularly transuranic (TRU) contaminated buried waste. BWID has implemented a systems approach to the development and demonstration of technologies that will characterize, retrieve, treat, and dispose of DOE buried wastes. This approach encompasses the entire remediation process from characterization to post-monitoring. The development and demonstration of the technology is predicated on how a technology fits into the total remediation process. To address all of these technological issues, BWID has enlisted scientific expertise of individuals and groups from within the DOE Complex, as well as experts from universities and private industry. The BWID mission is to support development and demonstration of a suite of technologies that, when integrated with commercially-available technologies, forms a comprehensive, remediation system for the effective and efficient remediation of buried waste throughout the DOE Complex. BWID will evaluate and validate demonstrated technologies and transfer this information and equipment to private industry to support the Office of Environmental Restoration (ER), Office of Waste Management (WM), and Office of Facility Transition (FT) remediation planning and implementation activities

INEL BNCT Research Program, May/June 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (IBPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, September--October 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-12-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotain. carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophonylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT research program, July--August 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-10-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, March/April 1992

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murino screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronopheoylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, September--October 1992

International Nuclear Information System (INIS)

Venhuizen, J.R.

1992-12-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotain. carboranyl alanine, and liposome boron containing compounds. Pituitary tumor call culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophonylalanine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

INEL BNCT Research Program, January/February 1993

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1993-04-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed.

INEL BNCT Research Program, January/February 1993

International Nuclear Information System (INIS)

Venhuizen, J.R.

1993-04-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (BPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

INEL BNCT Research Program, May/June 1992

International Nuclear Information System (INIS)

Venhuizen, J.R.

1992-09-01

This report presents summaries for two months of current research of the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Program. Information is presented on development and murine screening experiments of low-density lipoprotein, carboranyl alanine, and liposome boron containing compounds. Pituitary tumor cell culture studies are described. Drug stability, pharmacology and toxicity evaluation of borocaptate sodium (BSH) and boronophenylaianine (IBPA) are described. Treatment protocol development via the large animal (canine) model studies and physiological response evaluation in rats are discussed. Supporting technology development and technical support activities for boron drug biochemistry and purity, analytical and measurement dosimetry, and noninvasive boron quantification activities are included for the current time period. Current publications for the two months are listed

INEL BNCT research program: Annual report, 1995

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1996-04-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1995. Contributions from the principal investigators about their individual projects are included, specifically, physics (treatment planning software, real-time neutron beam measurement dosimetry), and radiation biology (large animal models efficacy studies). Design of a reactor based epithermal neutron extraction facility is discussed in detail. Final results of boron magnetic resonance imagining is included for both borocaptate sodium (BSH) and boronophenylalanine (BPA) in rats, and BSH in humans. Design of an epithermal neutron facility using electron linear accelerators is presented, including a treatise on energy removal from the beam target. Information on the multiple fraction injection of BSH in rats is presented.

INEL BNCT research program: Annual report, 1995

International Nuclear Information System (INIS)

Venhuizen, J.R.

1996-04-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1995. Contributions from the principal investigators about their individual projects are included, specifically, physics (treatment planning software, real-time neutron beam measurement dosimetry), and radiation biology (large animal models efficacy studies). Design of a reactor based epithermal neutron extraction facility is discussed in detail. Final results of boron magnetic resonance imagining is included for both borocaptate sodium (BSH) and boronophenylalanine (BPA) in rats, and BSH in humans. Design of an epithermal neutron facility using electron linear accelerators is presented, including a treatise on energy removal from the beam target. Information on the multiple fraction injection of BSH in rats is presented

INEL/USNRC pipe damping experiments and studies

International Nuclear Information System (INIS)

Ware, A.G.

1987-08-01

Since the previous paper on this subject presented at the 8th SMiRT Conference, the Idaho National Engineering Laboratory (INEL) has conducted further research on piping system damping for the United States Nuclear Regulatory Commission (USNRC). These efforts have included vibration tests on two laboratory piping systems at response frequencies up to 100 Hz, and damping data calculations from both of these two systems and from a third laboratory piping system test series. In addition, a statistical analysis was performed on piping system damping data from tests representative of seismic and hydrodynamic events of greater than minimal excitation. The results of this program will be used to assist regulators in establishing suitable damping values for use in dynamic analyses of nuclear piping systems, and in revising USNRC Regulatory Guide (RG) 1.61

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-01-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. Volume 1 identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues. This document Volume 2 and Volume 3 discusses each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTs, respectively

Treatability studies for polyethylene encapsulation of INEL low-level mixed wastes. Final report

International Nuclear Information System (INIS)

Lageraaen, P.R.; Patel, B.R.; Kalb, P.D.; Adams, J.W.

1995-10-01

Treatability studies for polyethylene encapsulation of Idaho National Engineering Laboratory (INEL) low-level mixed wastes were conducted at Brookhaven National Laboratory. The treatability work, which included thermal screening and/or processibility testing, was performed on priority candidate wastes identified by INEL to determine the applicability of polyethylene encapsulation for the solidification and stabilization of these mixed wastes. The candidate wastes selected for this preliminary study were Eutectic Salts, Ion Exchange Resins, Activated Carbons, Freon Contaminated Rags, TAN TURCO Decon 4502, ICPP Sodium Bearing Liquid Waste, and HTRE-3 Acid Spill Clean-up. Thermal screening was conducted for some of these wastes to determine the thermal stability of the wastes under expected pretreatment and processing conditions. Processibility testing to determine whether the wastes were amenable to extrusion processing included monitoring feed consistency, extruder output consistency, waste production homogeneity, and waste form performance. Processing parameters were not optimized within the scope of this study. However, based on the treatability results, polyethylene encapsulation does appear applicable as a primary or secondary treatment for most of these wastes

Defense Waste Management Plan for buried transuranic-contaminated waste, transuranic-contaminated soil, and difficult-to-certify transuranic waste

International Nuclear Information System (INIS)

1987-06-01

GAO recommended that DOE provide specific plans for permanent disposal of buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; cost estimates for permanent disposal of all TRU waste, including the options for the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; and specific discussions of environmental and safety issues for the permanent disposal of TRU waste. Purpose of this document is to respond to the GAO recommendations by providing plans and cost estimates for the long-term isolation of the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste. This report also provides cost estimates for processing and certifying stored and newly generated TRU waste, decontaminating and decommissioning TRU waste processing facilities, and interim operations

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

Energy Technology Data Exchange (ETDEWEB)

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

1992-02-01

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

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

International Nuclear Information System (INIS)

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

1992-02-01

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

Compliance agreements at the INEL: A success story

International Nuclear Information System (INIS)

McBath, W.H.

1995-01-01

The Radioactive Waste Management Complex (RWMC), located at the Idaho National Engineering Laboratory (INEL), is the storage facility for approximately 135,000 containers of radioactive mixed waste that must be stored in accordance with Resource Conservation and Recovery Act (RCRA) requirements. Collectively, the compliance and safety basis documents governing the operation of the storage facility contain approximately 2,500 specific, identifiable requirements. Critical to the compliance with these 2,500 requirements was the development of a process which converted these requirements to a form and format that allowed implementation at the operator level. Additionally, to ensure continued compliance, a method of identifying and controlling implementing documents is imperative. This paper discusses the methods employed to identify, implement, and control these requirements

Environmental and other evaluations of alternatives for management of defense transuranic waste at the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1982-04-01

The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive wastes. In connection with this responsibility, the DOE is formulating a program for the long-term management of transuranic (TRU) waste buried and stored at the Idaho National Engineering Laboratory (INEL). This report has been prepared to document the results of environmental and other evaluations for three decisions that the DOE is considering: (1) the selection of a general method for the long-term management of the buried TRU waste; (2) the selection of a method for processing the stored waste and for processing the buried waste, if it is retrieved; (3) the selection of a location for the waste-processing facility. This document pertains only to the contact-handled TRU waste buried in pits and trenches and the contact-handled TRU waste held in aboveground storage at the INEL. A decision has previously been made on a method for the long-term management of the stored waste; it will be retrieved and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The WIPP is also used in this report as a reference repository for evaluation purposes for the buried waste. This report is contained in two volumes. Volume I is arranged as follows: the summary is an overview of the analyses contained in this document. Section 1 is a statement of the underlying purpose and need to which the report is responding. Section 2 describes the alterntives. Section 3 describes the affected environment at the INEL and the WIPP sites. Section 4 analyzes the environmental effects of each alternative. The appendices in Volume II contain data and discussions supporting the material presented in Volume I

A case study for evaluating ecological risks at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Peterson, S.; Brewer, R.; Morris, R.; VanHorn, R.

1994-01-01

A case study was conducted as a component of the development of guidance for ecological risk assessment at the Department of Energy's Idaho National Engineering Laboratory (INEL). The INEL is a large facility in southeastern Idaho, encompassing expanses of sagebrush-steppe that harbor numerous wildlife species. Nuclear research and waste disposal activities have resulted in releases of radionuclides at various sites. Due to the size and number of potentially contaminated areas, a cost-effective method was needed to evaluate ecological risks and to identify data needs for remedial investigations. Screening-level assessment approaches were developed to evaluate data collected from previous site investigations. Above-background concentrations of radionuclides and other contaminants in media were compared to risk-based criteria, which were derived from sources such as recent publications of the International Atomic Energy Agency (IAEA) and National Council on Radiation Protection and Measurements (NCRP). Site-specific risks to plants and wildlife were estimated for contaminants exceeding criteria. Dose rates derived using various estimation methods were compared to reference doses for wildlife obtained from IAEA, NCRP, and other publications

Material and geometry options and performance characteristics for a test reactor

International Nuclear Information System (INIS)

Jahshan, S.N.; Fletcher, C.D.; Terry, W.K.

1993-01-01

For the past 3 yr, an Idaho National Engineering Laboratory (INEL) design team has studied design options for a new test reactor to provide continued testing services after several aging test reactors in the United States are decommissioned. This new reactor, the Broad Application Test Reactor (BATR), would also fill other currently unmet needs, such as medical isotope production and space reactor component testing. Consideration of user needs, safety requirements, developmental uncertainties, and other factors led to the selection of an evolutionary design with plate fuel and several independently cooled test loops. The fuel would be cooled by light water, but most neutron moderation would come from heavy water or beryllium. The BATR design was tentatively scaled to the Advanced Test Reactor (ATR), an existing reactor at INEL: The power output of BATR is 250 MW(thermal), and the active core heights is 1 m. For safety in loss-of-flow events, the coolant flows upward through the core. The BATR design has one large test loop (with a test space diameter of 15.0 cm) along the central axis of the core and six smaller test loops (with test space diameters of 8.0 cm) centered at 6-deg azimuthal intervals on a 24.71-cm-diam circle around the central core axis

Sampling and instrumentation requirements for long-range D and D activities at INEL

International Nuclear Information System (INIS)

Ahlquist, A.J.

1985-01-01

Assistance was requested to help determine sampling and instrumentation requirements for the long-range decontamination and decommissioning activities at the Idaho National Engineering Laboratory. Through a combination of literature review, visits to other DOE contractors, and a determination of the needs for the INEL program, a draft report has been prepared that is now under review. The final report should be completed in FY 84

Buried Craters of Utopia

Science.gov (United States)

2003-01-01

MGS MOC Release No. MOC2-365, 19 May 2003Beneath the northern plains of Mars are numerous buried meteor impact craters. One of the most heavily-cratered areas, although buried, occurs in Utopia Planitia, as shown in this Mars Global Surveyor (MGS) Mars Orbiter Camera (MOC) image. The history of Mars is complex; impact craters provide a tool by which to understand some of that history. In this case, a very ancient, cratered surface was thinly-buried by younger material that is not cratered at all. This area is near 48.1oN, 228.2oW; less than 180 km (112 mi) west of the Viking 2 lander site. Sunlight illuminates the scene from the lower left.

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

International Nuclear Information System (INIS)

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

1982-09-01

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

Failure analysis of buried tanks

International Nuclear Information System (INIS)

Watkins, R.K.

1994-01-01

Failure of a buried tank can be hazardous. Failure may be a leak through which product is lost from the tank; but also through which contamination can occur. Failures are epidemic -- because buried tanks are out of sight, but also because designers of buried tanks have adopted analyses developed for pressure tanks. So why do pressure tanks fail when they are buried? Most failures of buried tanks are really soil failures. Soil compresses, or slips, or liquefies. Soil is not only a load, it is a support without which the tank deforms. A high water table adds to the load on the tank. It also reduces the strength of the soil. Based on tests, structural analyses are proposed for empty tanks buried in soils of various quality, with the water table at various levels, and with internal vacuum. Failure may be collapse tank. Such collapse is a sudden, audible inversion of the cylinder when the sidefill soil slips. Failure may be flotation. Failure may be a leak. Most leaks are fractures in the welds in overlap seams at flat spots. Flat spots are caused by a hard bedding or a heavy surface wheel load. Because the tank wall is double thick at the overlap, shearing stress in the weld is increased. Other weld failures occur when an end plate shears down past a cylinder; or when the tank is supported only at its ends like a beam. These, and other, failures can be analyzed with justifiable accuracy using basic principles of mechanics of materials. 10 figs

Immobilization of INEL low-level radioactive wastes in ceramic containment materials

International Nuclear Information System (INIS)

Seymour, W.C.; Kelsey, P.V.

1978-11-01

INEL low-level radioactive wastes have an overall chemical composition that lends itself to self-containment in a ceramic-based material. Fewer chemical additives would be needed to process the wastes than to process high-level wastes or use a mixture containment method. The resulting forms of waste material could include a basalt-type glass or glass ceramic and a ceramic-type brick. Expected leach resistance is discussed in relationshp to data found in the literature for these materials and appears encouraging. An overview of possible processing steps for the ceramic materials is presented

Transuranic waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

Smith, T.H.; Tolman, C.R.

1980-12-01

This document summarizes the objectives and technical achievements of the transuranic (TRU) waste research and development program conducted at EG and G Idaho, Inc., during fiscal year 1980. The TRU waste activities covered in this report include: INEL TRU Waste EIS (Environmental Impact Statement), including preparation of the EIS, Support Studies, and the Public Participation Program; INEL TRU Waste Projects, including System Analysis, Stored Waste projects, and Buried Waste projects; and Waste Management Materials Studies, including Process Control and Durability studies

INEL BNCT Research Program annual report 1994

International Nuclear Information System (INIS)

Venhuizen, J.R.

1995-11-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1994. Contributions from the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, ICP-AES analysis of biological samples), physics (treatment planning software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of BSH and BPA is presented and results of 21 spontaneous tumor bearing dogs that have been treated with BNCT at Brookhaven National Laboratory (BNL) are discussed. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Highlights from the First International Workshop on Accelerator-Based Neutron Sources for BNCT are included

Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at I.N.E.L

International Nuclear Information System (INIS)

Gougar, M.L.D.; Scheetz, B.E.; Siemer, D.D.

1996-01-01

A cement capable of being Hot Isostatically Pressed (HIP'ed) into a glass-ceramic has been proposed for use as the waste form for SNF reprocessing wastes at the Idaho National Engineering Laboratories. Such an ''intermediate'' cement, with a composition based on that of common glasses, has been designed and tested. The cement formulations included mixed I.N.E.L. wastes, blast furnace flag, reactive silica, alumina, and I.N.E.L. soil or vermiculite, which was activated with potassium or sodium hydroxide. Modified FUETAP processing was performed and the cement was subsequently characterized. Results of compressive strength testing ranged from 1,452 psi to 4,163 psi, exceeding the NRC-suggested standard of >500 psi. Total dissolved solids concentrations in waste form leachates were calculated from a static leach test in which leachate conductivity was measured. Effective diffusivities for radioisotopes Cs and Sr were calculated from leachate analysis data. Diffusivity values were on the order of 10 -15 to 10 -10 cm 2 /sec, which compare favorably with diffusivities in other materials

Test plan for FY-94 digface characterization field experiments

International Nuclear Information System (INIS)

Josten, N.E.; Roybal, L.G.

1994-08-01

The digface characterization concept has been under development at the Idaho National Engineering Laboratory (INEL) since fiscal year (FY) 1992 through the support of the Buried Waste Integrated Demonstration Program. A digface characterization system conducts continuous subsurface characterization simultaneously with retrieval of hazardous and radioactive waste from buried waste sites. The system deploys multiple sensors at the retrieval operation digface and collects data that provide a basis for detecting, locating, and classifying buried materials and hazardous conditions before they are disturbed by the retrieval equipment. This test plan describes ongoing efforts to test the digface characterization concept at the INEL's Cold Test Pit using a simplified prototype deployment apparatus and off-the-shelf sensors. FY-94 field experiments will explore problems in object detection and classification. Detection and classification of objects are fundamental to three of the four primary functions of digface characterization during overburden removal. This test plan establishes procedures for collecting and validating the digface characterization data sets. Analysis of these data will focus on testing and further developing analysis methods for object detection and classification during overburden removal

Annual report on monitoring of the unsaturated zone and recharge areas at INEL to the state of Idaho INLEL Oversight COmmittee

International Nuclear Information System (INIS)

Horn, D.; Liou, J.; Finnie, J.

1993-03-01

This project, begun in March 1991, was originally structured as two separate research efforts: An investigation of the recharge phenomenon and surface water-ground water interactions at the INEL; and a study of water and contaminant movement through the unsaturated zone, including a review of computer models used to described this process. During the initial months of work, it became obvious to those involved in these studies that the two topic areas were intimately related, and work since that time has proceeded with no firm boundaries between the two efforts. Much of the Phase I work (March 1991--March 1992) consisted of a detailed review of available literature pertinent to the two research topics and to the INEL site. This Annual Report summarizes the other project activities during Phase III, and is organized into three sections: Section I -- an overview of the ongoing efforts related to computer model algorithms and data requirements for modeling the transport process in the unsaturated zone (Dr. Jim Liou). Section H -- a review of ongoing work to predict the growth and decay of the ground water mound beneath the INEL spreading basins, using the computer model UNSAT-2 (Dr. John Finnie). Section M -- a final report of the completed study effort examining the recharge rates associated with stream flow in the Big Lost River, and the effects of this recharge on ground water levels at the INEL site (Dr. Dennis Horn). Phase M of the project has now begun, and will conclude in December 1993 with two final reports documenting the work that has been briefly described in Sections I and H of this report

The Blackfoot 111 buried geophone experiment

Energy Technology Data Exchange (ETDEWEB)

Cieslewicz, D.; Lawton, D.C. [Calgary Univ., AB (Canada). Dept. of Geology and Geophysics

1999-07-01

As an important difference between a VSP and a conventional survey is the presence of the near-surface layer in the latter, it is possible that overburden materials are particularly attenuative to shear waves, causing an observed narrower bandwidth of converted waves in a seismic experiment conducted in the Blackfoot oil field. The Blackfoot III buried geophone experiment tested this hypothesis by recording data with three component geophones buried to various depths in the near surface. By avoiding a portion of the near surface, buried geophones might avoid a certain amount of attenuation, resulting in a better bandwidth and hence vertical resolution for P-S reflections in particular. Accessory seismic studies of near-surface velocity and impedance were made using the buried geophone data, made possible by the unique geometry of the experiment. The P-P processed data had comparable data quality at all geophone depths, whereas the processed surface P-S data had superior quality over data from the buried phones. This was a result of greater amounts of mode leakage and lower raw reflection amplitudes in the buried phones. No systematic improvement in P-S or P-P reflection bandwidth was noted for deeper geophones; inconsistent geophone coupling was partly a factor in this observation. Raw reflection amplitudes through the near surface are controlled mainly by the impedance of near-surface sediments. Near-surface velocities are typical for unconsolidated overburden for the western 2/3 of the buried receiver line, but increases to values more typical of unweathered bedrock for the eastern 1/3. This probably shows a thinning of the overburden layer in this area. 2 refs.

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

International Nuclear Information System (INIS)

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

1988-01-01

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

Preliminary systems design study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1991-09-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept

The INEL Human Reliability Program: The first two years of experience

International Nuclear Information System (INIS)

Minner, D.E.

1986-01-01

This paper provides a review of the design, implementation, and operation of the INEL Human Reliability Program from January 1984 through June of 1986. Human Reliability Programs are defined in terms of the ''insider threat'' to security of nuclear facilities. The design of HRP's are discussed with special attention given the special challenge of the disgruntled employee. Each component of an HRP is reviewed noting pitfalls and opportunities with each: drug testing of applicants and incumbents, psychological evaluation by management, security clearance procedures and administration including the use of an Employee Review Board to recommend action prior to final management decision

INEL test reactor facility alarms: descriptions, technical specifications, and modification procedure

International Nuclear Information System (INIS)

Potash, L.M.; Boone, M.P.

1980-04-01

This report identifies standards, procedures, and practices which will affect any attempt to integrate or introduce human engineering principles into nuclear power plant alarm systems. Additional information concerning type of signal used, expected reaction, type of sensor, etc., is presented because of its relevance to future work on alarm system integration. The INEL test reactors were studied. Interviews were conducted with operators, designers, and management personnel. Additional information was obtained from available documentation. Only fire-alarm systems, and to a lesser extent, criticality alarms, have detailed industry-wide standards. One general standard has been written for control-room annunciators

Robotic systems for the high level waste tank farm replacement project at INEL

International Nuclear Information System (INIS)

Berger, A.; White, D.; Thompson, B.; Christensen, M.

1993-01-01

Westinghouse Idaho Nuclear Company (WINCO) is specifying and designing a new high level waste tank farm at the Idaho National Engineering Laboratory (INEL). The farm consists of four underground storage tanks, which replace the existing tanks. The new facility includes provisions for remote operations. One of the planned remote operations is robotic inspection of the tank from the interior and exterior. This paper describes the process used to design the robotic system for the inspection tasks

TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

1987-01-01

This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

Project Management Plan for the INEL technology logic diagrams

International Nuclear Information System (INIS)

Rudin, M.J.

1992-10-01

This Project Management Plan (PjMP) describes the elements of project planning and control that apply to activities outlined in Technical Task Plan (TTP) ID-121117, ''Technology Logic Diagrams For The INEL.'' The work on this project will be conducted by personnel in EG ampersand G Idaho, Inc.'s Waste Technology Development Program. Technology logic diagrams represent a formal methodology to identify technology gaps or needs within Environmental Restoration/Waste Management Operations, which will focus on Office of Environmental Restoration and Waste Management (EM-50) research and development, demonstration, test, and evaluation efforts throughout the US Department of Energy complex. This PjMP describes the objectives, organization, roles and responsibilities, workscope and processes for implementing and managing the technology logic diagram for the Idaho National Engineering Laboratory project

TIDBIT - the INEL database of BNCT information and treatment

International Nuclear Information System (INIS)

Mancuso, C.A.

1995-01-01

The INEL Database of BNCT Information and Treatment (TIDBIT) has been under development for several years. Late in 1993, a new software development team took over the project and did and assessment of the current implementation status, and determined that the user interface was unsatisfactory for the expected users and that the data structures were out of step with the current state of reality. The team evaluated several tools that would improve the user interface to make the system easier to use. Uniface turned out to be the product of choice. During 1994, TIDBIT got its name, underwent a complete change of appearance, had a major overhaul to the data structures that support the application, and system documentation was begun. A prototype of the system was demonstrated in September 1994

Implementation of the buried waste integrated demonstration

International Nuclear Information System (INIS)

Kostelnik, K.M.; Merrill, S.K.

1992-01-01

The Department of Energy (DOE), Office of Technology Development (OTD) has initiated the Buried Waste Integrated Demonstration (BWID) to resolve technological deficiencies associated with the remediation of radioactive and hazardous buried waste. The BWID mission is to identify, demonstrate, and transfer innovative technologies for the remediation of DOE buried waste. To accomplish the mission, BWID is using a systems approach which supports the development of a suite of advanced and innovative technologies for the effective and efficient remediation of buried waste. This systems approach includes technologies for theentire remediation cycle. Specifically, BWID sponsors technology development in the following technology categories: site and waste characterization, retrieval, preprocessing, ex situ treatment, packaging, transportation, storage, disposal, and post-disposal monitoring

INEL BNCT Research Program annual report 1994

Energy Technology Data Exchange (ETDEWEB)

Venhuizen, J.R. [ed.

1995-11-01

This report is a summary of the progress and research produced for the Idaho National Engineering Laboratory (INEL) Boron Neutron Capture Therapy (BNCT) Research Program for calendar year 1994. Contributions from the principal investigators about their individual projects are included, specifically, chemistry (pituitary tumor studies, boron drug development including liposomes, lipoproteins, and carboranylalanine derivatives), pharmacology (murine screenings, toxicity testing, ICP-AES analysis of biological samples), physics (treatment planning software, neutron beam and filter design, neutron beam measurement dosimetry), and radiation biology (small and large animal models tissue studies and efficacy studies). Information on the potential toxicity of BSH and BPA is presented and results of 21 spontaneous tumor bearing dogs that have been treated with BNCT at Brookhaven National Laboratory (BNL) are discussed. Several boron carrying drugs exhibiting good tumor uptake are described. Significant progress in the potential of treating pituitary tumors is presented. Highlights from the First International Workshop on Accelerator-Based Neutron Sources for BNCT are included. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

The 1988 INEL [Idaho National Engineering Laboratory] microearthquake survey near the western edge of the eastern Snake River Plain

International Nuclear Information System (INIS)

Jackson, S.M.; Anderson, D.M.; Carpenter, G.S.; Gilbert, H.K.; Martin, S.M.; Permann, P.J.

1989-08-01

A network of seventeen analog recording seismograph, spaced approximately 2 km apart, were operated from May to November, 1988 near the western edge of the eastern Snake River Plain (ESRP) to record small magnitude microearthquakes. Two three-component digital seismographs were also installed to record the microearthquake activity for analysis of earthquake source parameters and any regional earthquakes for possible analysis of the localized site and crustal effects of the ESRP on earthquake ground motions. We determined near-surface crustal velocities for this area that were slightly lower than the near-surface crustal velocities presently used in routine locations of events recorded by the INEL Seismic Network from five 100 lb surface blasts. During the survey period, only two earthquakes were located near the network area. One of the events occurred in May and was recorded by four of the portable seismic stations and two of the permanent INEL Seismic Network stations. It had a coda magnitude (M c ) of approximately 0.3. The other event was recorded by seventeen portable analog stations and three of the permanent INEL Seismic Network stations. We located this microearthquake, M c =0.5, about 2 km west of Howe, Idaho, off of the ESRP. We determined an unconstrained focal mechanism for this event, which could be interpreted as normal faulting striking N 44 degree W or strike-slip faulting on a plane striking either N 44 degree W or N 47 degree E. 26 refs., 10 figs., 3 tabs

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

International Nuclear Information System (INIS)

McQuary, J.

1991-01-01

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

DOE's plan for buried transuranic (TRU) contaminated waste

International Nuclear Information System (INIS)

Mathur, J.; D'Ambrosia, J.; Sease, J.

1987-01-01

Prior to 1970, TRU-contaminated waste was buried as low-level radioactive waste. In the Defense Waste Management Plan issued in 1983, the plan for this buried TRU-contaminated waste was to monitor the buried waste, take remedial actions, and to periodically evaluate the safety of the waste. In March 1986, the General Accounting Office (GAO) recommended that the Department of Energy (DOE) provide specific plans and cost estimates related to buried TRU-contaminated waste. This plan is in direct response to the GAO request. Buried TRU-contaminated waste and TRU-contaminated soil are located in numerous inactive disposal units at five DOE sites. The total volume of this material is estimated to be about 300,000 to 500,000 m 3 . The DOE plan for TRU-contaminated buried waste and TRU-contaminated soil is to characterize the disposal units; assess the potential impacts from the waste on workers, the surrounding population, and the environment; evaluate the need for remedial actions; assess the remedial action alternatives; and implement and verify the remedial actions as appropriate. Cost estimates for remedial actions for the buried TRU-contaminated waste are highly uncertain, but they range from several hundred million to the order of $10 billion

In situ vitrification of buried waste sites

International Nuclear Information System (INIS)

Shade, J.W.; Thompson, L.E.; Kindle, C.H.

1991-04-01

In situ vitrification (ISV) is a remedial technology initially developed to treat soils contaminated with a variety of organics, heavy metals, and/or radioactive materials. Recent tests have indicated the feasibility of applying the process to buried wastes including containers, combustibles, and buried metals. In addition, ISV is being considered for application to the emplacement of barriers and to the vitrification of underground tanks. This report provides a review of some of the recent experiences of applying ISV in engineering-scale and pilot-scale tests to wastes containing organics, the Environmental Protection Agency (EPA) Toxic metals buried in sealed containers, and buried ferrous metals, with emphasis on the characteristics of the vitrified product and adjacent soil. 9 refs., 2 figs., 3 tabs

Evaluation of airborne thermal, magnetic, and electromagnetic characterization technologies

Energy Technology Data Exchange (ETDEWEB)

Josten, N.E.

1992-03-01

The identification of Buried Structures (IBS) or Aerial Surveillance Project was initiated by the US Department of Energy (DOE) Office of Technology Development to demonstrate airborne methods for locating and identifying buried waste and ordnance at the Idaho National Engineering Laboratory (INEL). Two technologies were demonstrated: (a) a thermal infrared imaging system built by Martin Marietta Missile Systems and (b) a magnetic and electromagnetic (EM) geophysical surveying system operated by EBASCO Environmental. The thermal system detects small differences in ground temperature caused by uneven heating and cooling of the ground by the sun. Waste materials on the ground can be detected when the temperature of the waste is different than the background temperature. The geophysical system uses conventional magnetic and EM sensors. These sensors detect disturbances caused by magnetic or conductive waste and naturally occurring magnetic or conductive features of subsurface soils and rock. Both systems are deployed by helicopter. Data were collected at four INEL sites. Tests at the Naval Ordnance Disposal Area (NODA) were made to evaluate capabilities for detecting ordnance on the ground surface. Tests at the Cold Simulated Waste Demonstration Pit were made to evaluate capabilities for detecting buried waste at a controlled site, where the location and depth of buried materials are known. Tests at the Subsurface Disposal Area and Stationary Low-Power Reactor-1 burial area were made to evaluate capabilities for characterizing hazardous waste at sites that are typical of DOE buried waste sites nationwide.

Evaluation of airborne thermal, magnetic, and electromagnetic characterization technologies

International Nuclear Information System (INIS)

Josten, N.E.

1992-03-01

The identification of Buried Structures (IBS) or Aerial Surveillance Project was initiated by the US Department of Energy (DOE) Office of Technology Development to demonstrate airborne methods for locating and identifying buried waste and ordnance at the Idaho National Engineering Laboratory (INEL). Two technologies were demonstrated: (a) a thermal infrared imaging system built by Martin Marietta Missile Systems and (b) a magnetic and electromagnetic (EM) geophysical surveying system operated by EBASCO Environmental. The thermal system detects small differences in ground temperature caused by uneven heating and cooling of the ground by the sun. Waste materials on the ground can be detected when the temperature of the waste is different than the background temperature. The geophysical system uses conventional magnetic and EM sensors. These sensors detect disturbances caused by magnetic or conductive waste and naturally occurring magnetic or conductive features of subsurface soils and rock. Both systems are deployed by helicopter. Data were collected at four INEL sites. Tests at the Naval Ordnance Disposal Area (NODA) were made to evaluate capabilities for detecting ordnance on the ground surface. Tests at the Cold Simulated Waste Demonstration Pit were made to evaluate capabilities for detecting buried waste at a controlled site, where the location and depth of buried materials are known. Tests at the Subsurface Disposal Area and Stationary Low-Power Reactor-1 burial area were made to evaluate capabilities for characterizing hazardous waste at sites that are typical of DOE buried waste sites nationwide

Integrated test schedule for buried waste integrated demonstration

International Nuclear Information System (INIS)

Brown, J.T.; McDonald, J.K.

1992-05-01

The Integrated Test Schedule incorporates the various schedules the Buried Waste Integrated Demonstration (BWID) supports into one document. This document contains the Federal Facilities Agreement and Consent Order schedules for the Idaho National Engineering Laboratory, Hanford Reservation, Oak Ridge Reservation, and Fernald Environmental Materials Center. Included in the Integrated Test Schedule is the Buried Waste Integrated Demonstration ''windows of opportunity'' schedule. The ''windows of opportunity'' schedule shows periods of time in which Buried Waste Integrated Demonstration Program-sponsored technology demonstrations could support key decisions in the Federal Facilities Agreement and Consent Order. Schedules for the Buried Waste Integrated Demonstration-sponsored technology task plans are categorized by technology area and divided by current fiscal year and out-year. Total estimated costs for Buried Waste Integrated Demonstration-sponsored Technology Task Plans for FY-92 through FY-97 are $74.756M

Energy and costs scoping study for plasma pyrolysis thermal processing system

International Nuclear Information System (INIS)

Sherick, K.E.; Findley, J.E.

1992-01-01

The purpose of this study was to provide information in support of an investigation of thermal technologies as possible treatment process for buried wastes at the INEL. Material and energy balances and a cost estimate were generated for a representative plasma torch-based thermal waste treatment system operating in a pyrolysis mode. Two waste streams were selected which are representative of INEL buried wastes, large in volume, and difficult to treat by other technologies. These streams were a solidified nitrate sludge waste stream and a waste/soil mix of other buried waste components. The treatment scheme selected includes a main plasma chamber operating under pyrolyzing conditions; a plasma afterburner to provide additional residence time at high temperature to ensure complete destruction of hazardous organics; an off-gas treatment system; and a incinerator and stack to oxidize carbon monoxide to carbon dioxide and vent the clean, oxidized gases to atmosphere. The material balances generated provide materials flow and equipment duty information of sufficient accuracy to generate initial rough-order-of-magnitude (ROM) system capital and operating cost estimates for a representative plasma thermal processing system

Track 2 sites: Guidance for assessing low probability hazard sites at the INEL

International Nuclear Information System (INIS)

1994-01-01

This document presents guidance for assessment of Track 2 low probability hazard sites (LPHS) at the Idaho National Engineering Laboratory (INEL). The Track 2 classification was developed specifically for the INEL to streamline the implementation of Comprehensive Environmental Response, Compensation, and Liability Act. Track 2 LPHSs are described as sites where insufficient data are available to make a decision concerning the risk level or to select or design a remedy. As such, these types of sites are not described in the National Contingency Plan or existing regulatory guidance. The goal of the Track 2 process is to evaluate LPHSs using existing qualitative and quantitative data to minimize the collection of new environmental data. To this end, this document presents a structured format consisting of a series of questions and tables. A qualitative risk assessment is used. The process is iterative, and addresses an LPHS from multiple perspectives (i.e., historical, empirical, process) in an effort to generate a reproducible and defensible method. This rigorous approach follows the data quality objective process and establishes a well organized, logical approach to consolidate and assess existing data, and set decision criteria. If necessary, the process allows for the design of a sampling and analysis strategy to obtain new environmental data of appropriate quality to support decisions for each LPHS. Finally, the guidance expedites consensus between regulatory parties by emphasizing a team approach to Track 2 investigations

Compact Buried Ducts in a Hot-Humid Climate House

Energy Technology Data Exchange (ETDEWEB)

Mallay, Dave [Home Innovation Research Labs, Upper Marlboro, MD (United States)

2016-01-07

"9A system of compact, buried ducts provides a high-performance and cost-effective solution for delivering conditioned air throughout the building. This report outlines research activities that are expected to facilitate adoption of compact buried duct systems by builders. The results of this research would be scalable to many new house designs in most climates and markets, leading to wider industry acceptance and building code and energy program approval. The primary research question with buried ducts is potential condensation at the outer jacket of the duct insulation in humid climates during the cooling season. Current best practices for buried ducts rely on encapsulating the insulated ducts with closed-cell spray polyurethane foam insulation to control condensation and improve air sealing. The encapsulated buried duct concept has been analyzed and shown to be effective in hot-humid climates. The purpose of this project is to develop an alternative buried duct system that performs effectively as ducts in conditioned space - durable, energy efficient, and cost-effective - in a hot-humid climate (IECC warm-humid climate zone 3A) with three goals that distinguish this project: 1) Evaluation of design criteria for buried ducts that use common materials and do not rely on encapsulation using spray foam or disrupt traditional work sequences; 2) Establishing design criteria for compact ducts and incorporate those with the buried duct criteria to further reduce energy losses and control installed costs; 3) Developing HVAC design guidance for performing accurate heating and cooling load calculations for compact buried ducts.

Addition of liquid waste incineration capability to the INEL's low-level waste incinerator

International Nuclear Information System (INIS)

Steverson, E.M.; Clark, D.P.; McFee, J.N.

1986-01-01

A liquid waste system has recently been installed in the Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering Laboratory (INEL). In this paper, aspects of the incineration system such as the components, operations, capabilities, capital cost, EPA permit requirements, and future plans are discussed. The principal objective of the liquid incineration system is to provide the capability to process hazardous, radioactively contaminated, non-halogenated liquid wastes. The system consists primarily of a waste feed system, instrumentation and controls, and a liquid burner, which were procured at a capital cost of $115,000

A novel natural analog in situ stabilization agent

International Nuclear Information System (INIS)

Shaw, P.

1995-01-01

This report summarizes the laboratory-scale test results on a synthetic analog of natural hematite cement for potential as an in situ treatment and stabilization agent for buried hazardous and radioactive waste. The concept is based on the principle that the ideal waste isolation materials are synthetic analogs of those natural encapsulating materials (cements), which are in equilibrium with the environment in which they occur. If equilibrium is achieved, then such materials will remain intact as long as the natural environment remains unchanged. The specific waste application is long-term stabilization of transuranic-contaminated waste pits and trenches at the Idaho National Engineering Laboratory (INEL). Six properties of the natural analog agent and resulting wasteforms are discussed to access the agent's effectiveness and implementability: hydraulic conductivity; compressive strength; mineralogy and microstructure; compatibility with possible waste materials, nitrates, machine cutting oil, and metallic iron; leachability of hazardous metals; and field application parameters. Data indicated that the iron waste encapsulation materials tested are appropriate choices for buried waste mixed with INEL soil. Iron oxide/gypsum INEL soil wasteforms have hydraulic conductivity values close to the regulatory limit. Wasteforms with soil and wastes have compressive strength greater than the regulatory minimum. Gypsum/iron oxide removes hazardous metals from solution by adsorption and would pass Toxicity Characteristic Leaching Procedure limits for most toxic metals. It appears to be chemically and physically inert with respect to the bulk of the waste materials likely to be found at INEL, and has properties conducive to jet grouting

Space nuclear thermal propulsion test facilities accommodation at INEL

International Nuclear Information System (INIS)

Hill, T.J.; Reed, W.C.; Welland, H.J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway

Space nuclear thermal propulsion test facilities accommodation at INEL

Science.gov (United States)

Hill, Thomas J.; Reed, William C.; Welland, Henry J.

1993-01-01

The U.S. Air Force (USAF) has proposed to develop the technology and demonstrate the feasibility of a particle bed reactor (PBR) propulsion system that could be used to power an advanced upper stage rocket engine. The U.S. Department of Energy (DOE) is cooperating with the USAF in that it would host the test facility if the USAF decides to proceed with the technology demonstration. Two DOE locations have been proposed for testing the PBR technology, a new test facility at the Nevada Test Site, or the modification and use of an existing facility at the Idaho National Engineering Laboratory. The preliminary evaluations performed at the INEL to support the PBR technology testing has been completed. Additional evaluations to scope the required changes or upgrade needed to make the proposed USAF PBR test facility meet the requirements for testing Space Exploration Initiative (SEI) nuclear thermal propulsion engines are underway.

Concealed epispadias associated with a buried penis.

Science.gov (United States)

Sol Melgar, Ricardo; Gorduza, Daniela; Demède, Delphine; Mouriquand, Pierre

2016-12-01

The aim was to describe the clinical presentation and the surgical management of penile epispadias associated with a buried penis in five children. This is a 5-year retrospective review of patients presenting with a buried penis, a congenital defect of the penile skin shaft associated with an unretractable foreskin for whom a penile epispadias was found at the time of surgery. All had undergone surgery combining a Cantwell-Ransley procedure and refashioning of the penile skin following the authors' technique. Three children had a glanular epispadias and two had a midshaft epispadias. Four had a satisfactory outcome, and one required a complementary urethroplasty for glanular dehiscence. Buried penis and epispadias are usually isolated congenital anomalies, although they can be associated. It is therefore recommended to warn parents about the possibility of underlying penile anomaly in children with buried penises and unretractable foreskin. Careful palpation of the dorsum of the glans through the foreskin looking for a dorsal cleft could indicate an associated epispadiac urethra. Surgical correction of both anomalies can be done at the same time. Parents of boys with buried penises should be warned that underlying penile anomaly may exist. Copyright © 2016 Journal of Pediatric Urology Company. Published by Elsevier Ltd. All rights reserved.

How Burying Biomass Can Contribute to CO2 Stabilization

Science.gov (United States)

Cook, B.; Zeng, N.; Zaitchik, B.; Gregg, J.

2008-12-01

To mitigate global climate change, a portfolio of strategies will be needed to keep the atmospheric CO2 concentration below a dangerous level. Here a carbon sequestration strategy is proposed in which certain dead or live trees are harvested via collection or selective cutting, then buried in trenches or stowed away in above-ground shelters. The largely anaerobic condition under a sufficiently thick layer of soil will prevent the decomposition of the buried wood. Because a large flux of CO2 is constantly being assimilated into the world's forests via photosynthesis, cutting off its return pathway to the atmosphere forms an effective carbon sink. It is estimated that a sustainable long-term carbon sequestration potential for wood burial is 10 ± 5 GtC y-1, and currently about 65 GtC is on the world's forest floors in the form of coarse woody debris suitable for burial. The potential is largest in tropical forests (4.2 GtC y-1), followed by temperate (3.7 GtC y-1) and boreal forests (2.1 GtC y-1). Burying wood has other benefits including minimizing CO2 source from deforestation, extending the lifetime of reforestation carbon sink, and reducing fire danger. There are possible environmental impacts such as nutrient lock-up which nevertheless appears manageable, but other environmental concerns and factors will likely set a limit so that only part of the full potential can be realized. Based on data from North American logging industry, the cost for wood burial is estimated to be 14/tCO2 (50/tC), lower than the typical cost for power plant CO2 capture with geological storage. The low cost for carbon sequestration with wood burial is possible because the technique uses the natural process of photosynthesis to remove carbon from the atmosphere. The technique is low tech, distributed, safe, and can be stopped at any time, thus an attractive option for large-scale implementation in a world-wide carbon market.

Exposed versus buried wires for fixation of lateral humeral condyle fractures in children: a comparison of safety and efficacy.

Science.gov (United States)

Chan, Lester Wai Mon; Siow, Hua Ming

2011-10-01

Displaced fractures of the lateral condyle of the humerus are usually treated with open reduction and fixation with smooth Kirschner wires. These may be passed through the skin and left exposed or buried subcutaneously. Exposed wires may be removed in the outpatient clinic, whereas buried wires require a formal procedure under anaesthesia. This advantage may be offset if there is a higher rate of complications with exposed wires. The aim of this study was to compare the safety and efficacy of exposed and buried wires. Retrospective cohort. Children with lateral condyle fractures of the humerus who had undergone surgery were identified from our departmental database. Case records and X-rays of 75 patients were reviewed. Forty-two patients had buried wires and 33 had exposed wires. There were no serious complications in either group. In the exposed wires group, 1 patient had a superficial wound infection that was treated effectively with 1 week of oral antibiotics, while 2 patients had hypergranulation of pin tracts treated with topical silver nitrate. None of the patients showed loss of reduction, deep infection, or any other complications requiring additional procedures. There was no statistically significant difference in the rate of complications between the buried and exposed groups. We conclude that open reduction and exposed wiring is a safe and effective option for lateral condyle fractures, and recommend a period of 4 weeks of K-wire fixation followed by 2 weeks of backslab immobilisation as adequate for union with minimal risk of infection.

Dual-band infrared capabilities for imaging buried object sites

Energy Technology Data Exchange (ETDEWEB)

Del Grande, N.K.; Durbin, P.F.; Gorvad, M.R.; Perkins, D.E.; Clark, G.A.; Hernandez, J.E.; Sherwood, R.J.

1993-04-02

We discuss dual-band infrared (DBIR) capabilities for imaging buried object sizes. We identify physical features affecting thermal contrast needed to distinguish buried object sites from undisturbed sites or surface clutter. Apart from atmospheric transmission and system performance, these features include: object size, shape, and burial depth; ambient soil, disturbed soil and object site thermal diffusivity differences; surface temperature, emissivity, plant-cover, slope, albedo and roughness variations; weather conditions and measurement times. We use good instrumentation to measure the time-varying temperature differences between buried object sites and undisturbed soil sites. We compare near surface soil temperature differences with radiometric infrared (IR) surface temperature differences recorded at 4.7 {plus_minus} 0.4 {mu}m and at 10.6 {plus_minus} 1.0 {mu}m. By producing selective DBIR image ratio maps, we distinguish temperature-difference patterns from surface emissivity effects. We discuss temperature differences between buried object sites, filled hole site (without buried objects), cleared (undisturbed) soil sites, and grass-covered sites (with and without different types of surface clutter). We compare temperature, emissivity-ratio, visible and near-IR reflectance signatures of surface objects, leafy plants and sod. We discuss the physical aspects of environmental, surface and buried target features affecting interpretation of buried targets, surface objects and natural backgrounds.

Initial tests on in situ vitrification using electrode feeding techniques

International Nuclear Information System (INIS)

Farnsworth, R.K.; Oma, K.H.; Bigelow, C.E.

1990-05-01

This report summarizes the results of an engineering-scale in situ vitrification (ISV) test conducted to demonstrate the potential for electrode feeding in soils with a high concentration of metals. The engineering-scale test was part of a Pacific Northwest Laboratory (PNL) program to assist Idaho National Engineering Laboratory (INEL) in conducting treatability studies of the potential for applying ISV to the mixed transuranic waste buried at the INEL subsurface disposal area. The purpose of this test was to evaluate the effectiveness of both gravity fed and operator-controlled electrode feeding in reducing or eliminating many of the potential problems associated with fixed-electrode processing of soils with high concentrations of metal. Actual site soils from INEL were mixed with representative concentrations of carbon steel and stainless steel for this engineering-scale test. 18 refs., 14 figs., 3 tabs

Plasma treatment of INEL soil contaminated with heavy metals

International Nuclear Information System (INIS)

Detering, B.A.; Batdorf, J.A.

1992-01-01

INEL soil spiked with inorganic salts of chromium, lead, mercury, silver, and zinc was melted in a 150 kW plasma furnace to produce a glassy slag product. This glassy slag is an environmentally safe waste form. In order to reduce the melting temperature of the soil, sodium carbonate was added to half of the test batches. Random sample from each batch of glassy slag product were analyzed by an independent laboratory for total metals concentration and leachability of metals via the Environmental Protection Agency (EPA) toxicity characterization leaching procedure (RCLP) tests. These tests showed the residual metals were very tightly bound to the slag matrix and were within EPA TCLP limits under these test conditions. Additionally, scanning electron microscopy (SEM) and emissions dispersive spectroscopy (EDS) analysis of the vitrified soil also confirmed that the added metals present in the vitrified soil were totally contained in the crystalline phase as distinct oxide crystallites

NRC nuclear-plant-analyzer concept and status at INEL

International Nuclear Information System (INIS)

Aguilar, F.; Wagner, R.J.

1982-01-01

The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

Mixed debris treatment at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Garcia, E.C.; Porter, C.L.; Wallace, M.T.

1993-01-01

August 18, 1992 the Environmental Protection Agency (EPA) published the final revised treatment standards for hazardous debris, including mixed debris. (1) Whereas previous standards had been concentration based, the revised standards are performance based. Debris must be treated prior to land disposal, using specific technologies from one or more of the following families of debris treatment technologies: Extraction, destruction, or immobilization. Seventeen specific technologies with generic application are discussed in the final rule. The existing capabilities and types of debris at the INEL were scrubbed against the debris rule to determine an overall treatment strategy. Seven types of debris were identified: combustible, porous, non-porous, inherently hazardous, HEPA filters, asbestos contaminated, and reactive metals contaminated debris. With the exception of debris contaminated with reactive metals treatment can be achieved utilizing existing facilities coupled with minor modifications

Heat transfer correlation development and assessment: a summary and assessment of return to nucleate boiling phenomena during blowdown tests conducted at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Eaton, A.M.; Tolman, E.L.

1979-04-01

The data are presented which were obtained in Loss-of-Coolant Experiments (LOCE) at Idaho National Engineering Laboratory (INEL) which demonstrate the presence of cladding rewetting after the critical heat flux has been exceeded as a viable cooling mechanism during the blowdown phase of a LOCE. A brief review of the mechanisms associated with the boiling crisis and rewetting is also provided. The relevance of INEL LOCE rewetting data to nuclear reactor licensing Evaluation Model Requirements is considered, and the conclusion is made that the elimination of rewetting and return to nucleate boiling (RNB) in Evaluation Models represents a definite conservatism

Transuranic waste management program and facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

Transuranic Waste Management Program and Facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-02-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

Electrical properties and radiation hardness of SOI systems with multilayer buried dielectric

International Nuclear Information System (INIS)

Barchuk, I.P.; Kilchitskaya, V.I.; Lysenko, V.S.

1997-01-01

In this work SOI structures with buried SiO 2 -Si 3 N 4 -SiO 2 layers have been fabricated by the ZMR-technique with the aim of improving the total dose radiation hardness of the buried dielectric layer. To optimize the fabrication process, buried layers were investigated by secondary ion mass spectrometry before and after the ZMR process, and the obtained results were compared with electrical measurements. It is shown that optimization of the preparation processes of the initial buried dielectric layers provides ZMR SOI structures with multilayer buried isolation, which are of high quality for both Si film interfaces. Particular attention is paid to the investigation of radiation-induced charge trapping in buried insulators. Buried isolation structures with a nitride layer exhibit significant reduction of radiation-induced positive charge as compared to classical buried SiO 2 layers produced by either the ZMR or the SIMOX technique

Buried nodules from the central Indian Ocean basin

Digital Repository Service at National Institute of Oceanography (India)

Pattan, J.N.; Parthiban, G.

. Of these, 13 buried nodules are from two sediment cores in siliceous ooze and seven from two sediment cores in a red clay area. The morphology, size, surface texture and chemical composition of buried nodules from two different sediment type have been...

Electromagnetic scattering from buried objects

International Nuclear Information System (INIS)

Brock, B.C.; Sorensen, K.W.

1994-10-01

Radar imaging and detection of objects buried in soil has potentially important applications in the areas of nonproliferation of weapons, environmental monitoring, hazardous-waste site location and assessment, and even archeology. In order to understand and exploit this potential, it is first necessary to understand how the soil responds to an electromagnetic wave, and how targets buried within the soil scatter the electromagnetic wave. We examine the response of the soil to a short pulse, and illustrate the roll of the complex dielectric permittivity of the soil in determining radar range resolution. This leads to a concept of an optimum frequency and bandwidth for imaging in a particular soil. We then propose a new definition for radar cross section which is consistent with the modified radar equation for use with buried targets. This radar cross section plays the same roll in the modified radar equation as the traditional radar cross section does in the free-space radar equation, and is directly comparable to it. The radar cross section of several canonical objects in lossy media is derived, and examples are given for several object/soil combinations

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

International Nuclear Information System (INIS)

1992-01-01

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

Performance-Based Technology Selection Filter description report

International Nuclear Information System (INIS)

O'Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

1992-05-01

A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL)

Performance-Based Technology Selection Filter description report

Energy Technology Data Exchange (ETDEWEB)

O' Brien, M.C.; Morrison, J.L.; Morneau, R.A.; Rudin, M.J.; Richardson, J.G.

1992-05-01

A formal methodology has been developed for identifying technology gaps and assessing innovative or postulated technologies for inclusion in proposed Buried Waste Integrated Demonstration (BWID) remediation systems. Called the Performance-Based Technology Selection Filter, the methodology provides a formalized selection process where technologies and systems are rated and assessments made based on performance measures, and regulatory and technical requirements. The results are auditable, and can be validated with field data. This analysis methodology will be applied to the remedial action of transuranic contaminated waste pits and trenches buried at the Idaho National Engineering Laboratory (INEL).

Track 2 sites: Guidance for assessing low probability hazard sites at the INEL. Revision 6

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

This document presents guidance for assessment of Track 2 low probability hazard sites (LPHS) at the Idaho National Engineering Laboratory (INEL). The Track 2 classification was developed specifically for the INEL to streamline the implementation of Comprehensive Environmental Response, Compensation, and Liability Act. Track 2 LPHSs are described as sites where insufficient data are available to make a decision concerning the risk level or to select or design a remedy. As such, these types of sites are not described in the National Contingency Plan or existing regulatory guidance. The goal of the Track 2 process is to evaluate LPHSs using existing qualitative and quantitative data to minimize the collection of new environmental data. To this end, this document presents a structured format consisting of a series of questions and tables. A qualitative risk assessment is used. The process is iterative, and addresses an LPHS from multiple perspectives (i.e., historical, empirical, process) in an effort to generate a reproducible and defensible method. This rigorous approach follows the data quality objective process and establishes a well organized, logical approach to consolidate and assess existing data, and set decision criteria. If necessary, the process allows for the design of a sampling and analysis strategy to obtain new environmental data of appropriate quality to support decisions for each LPHS. Finally, the guidance expedites consensus between regulatory parties by emphasizing a team approach to Track 2 investigations.

Seismic response of buried pipelines: a state-of-the-art review

International Nuclear Information System (INIS)

Datta, T.K.

1999-01-01

A state-of-the-art review of the seismic response of buried pipelines is presented. The review includes modeling of soil-pipe system and seismic excitation, methods of response analysis of buried pipelines, seismic behavior of buried pipelines under different parametric variations, seismic stresses at the bends and intersections of network of pipelines. pipe damage in earthquakes and seismic risk analysis of buried pipelines. Based on the review, the future scope of work on the subject is outlined. (orig.)

Use of Monte Carlo methods in environmental risk assessments at the INEL: Applications and issues

Energy Technology Data Exchange (ETDEWEB)

Harris, G.; Van Horn, R.

1996-06-01

The EPA is increasingly considering the use of probabilistic risk assessment techniques as an alternative or refinement of the current point estimate of risk. This report provides an overview of the probabilistic technique called Monte Carlo Analysis. Advantages and disadvantages of implementing a Monte Carlo analysis over a point estimate analysis for environmental risk assessment are discussed. The general methodology is provided along with an example of its implementation. A phased approach to risk analysis that allows iterative refinement of the risk estimates is recommended for use at the INEL.

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

International Nuclear Information System (INIS)

1979-12-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that data are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

Use of Monte Carlo methods in environmental risk assessments at the INEL: Applications and issues

International Nuclear Information System (INIS)

Harris, G.; Van Horn, R.

1996-06-01

The EPA is increasingly considering the use of probabilistic risk assessment techniques as an alternative or refinement of the current point estimate of risk. This report provides an overview of the probabilistic technique called Monte Carlo Analysis. Advantages and disadvantages of implementing a Monte Carlo analysis over a point estimate analysis for environmental risk assessment are discussed. The general methodology is provided along with an example of its implementation. A phased approach to risk analysis that allows iterative refinement of the risk estimates is recommended for use at the INEL

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

Energy Technology Data Exchange (ETDEWEB)

1979-02-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed.

Environmental and other evaluations of alternatives for long-term management of stored INEL transuranic waste

International Nuclear Information System (INIS)

1979-02-01

This study identifies, develops, and evaluates, in a preliminary manner, alternatives for long-term management of TRU waste stored at the Radioactive Waste Management Complex (RWMC) at the INEL. The evaluations concern waste currently at the RWMC and waste expected to be received by the beginning of the year 1985. The effects of waste that might be received after that date are addressed in an appendix. The technology required for managing the waste, the environmental effects, the risks to the public, the radiological and nonradiological hazards to workers, and the estimated costs are discussed

Buried oxide layer in silicon

Science.gov (United States)

Sadana, Devendra Kumar; Holland, Orin Wayne

2001-01-01

A process for forming Silicon-On-Insulator is described incorporating the steps of ion implantation of oxygen into a silicon substrate at elevated temperature, ion implanting oxygen at a temperature below 200.degree. C. at a lower dose to form an amorphous silicon layer, and annealing steps to form a mixture of defective single crystal silicon and polycrystalline silicon or polycrystalline silicon alone and then silicon oxide from the amorphous silicon layer to form a continuous silicon oxide layer below the surface of the silicon substrate to provide an isolated superficial layer of silicon. The invention overcomes the problem of buried isolated islands of silicon oxide forming a discontinuous buried oxide layer.

Buried topography of Utopia, Mars: Persistence of a giant impact depression

International Nuclear Information System (INIS)

McGill, G.E.

1989-01-01

Knobs, partially buried craters, ring fractures, and some mesas permit a qualitative determination of the topography buried beneath younger northern plains materials. These features are widely distributed in the Utopia area but are absent in a large, roughly circular region centered at about 48 degree N, 240 degree W. This implies the existence of a circular depression about 3,300 km in diameter buried beneath Utopia Planitia that is here interpreted to represent the central part of a very large impact basin. The presence of buried curved massifs around part of this depression, and a roughly coincident mascon, lend further support. Present topography, areal geology, and paleotopography of buried surfaces all point to the persistence of this major depression for almost the entire history of Mars

Statistical survey of the buried waters in the Protein Data Bank.

Science.gov (United States)

Carugo, Oliviero

2016-01-01

The structures of buried water molecules were studied in an ensemble of high-quality and non-redundant protein crystal structures. Buried water molecules were clustered and classified in lake-like clusters, which are completely isolated from the bulk solvent, and bay-like clusters, which are in contact with the bulk solvent through a surface water molecule. Buried water molecules are extremely common: lake-like clusters are found in 89 % of the protein crystal structures and bay-like clusters in 93 %. Clusters with only one water molecule are much more common than larger clusters. Both cluster types incline to be surrounded by loop residues, and to a minor extent by residues in extended secondary structure. Helical residues on the contrary do not tend to surround clusters of buried water molecules. One buried water molecule is found every 30-50 amino acid residues, depending on the secondary structures that are more abundant in the protein. Both main- and side-chain atoms are in contact with buried waters; they form four hydrogen bonds with the first water and 1-1.5 additional hydrogen bond for each additional water in the cluster. Consequently, buried water molecules appear to be firmly packed and rigid like the protein atoms. In this regard, it is remarkable to observe that prolines often surround water molecules buried in the protein interior. Interestingly, clusters of buried water molecules tend to be just beneath the protein surface. Moreover, water molecules tend to form a one-dimensional wire rather than more compact arrangements. This agrees with recent evidence of the mechanisms of solvent exchange between internal cavities and bulk solvent.

Virtual environmental applications for buried waste characterization technology evaluation report

International Nuclear Information System (INIS)

1995-05-01

The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year

Virtual environmental applications for buried waste characterization technology evaluation report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year.

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

International Nuclear Information System (INIS)

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: sm-bullet Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) sm-bullet Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as open-quotes lowclose quotes hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with open-quotes moderateclose quotes or open-quotes highclose quotes hazard classifications

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

Solute travel time in the vadose zone under RWMC at INEL

International Nuclear Information System (INIS)

Liou, J.C.P.; Tian, J.

1995-01-01

Solute transport in the vadose zone under the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL) is considered. The objective is to assess the relative importance of variables involved in modeling the travel time of a conservative solute from ground surface to water table. The vadose zone under RWMC is composed of several layers of basalt flows interceded with sediment layers. The thickness of the layers varies with location. The hydraulic properties also vary. The extents of the variations are large, with standard deviations exceed mean in some instances. The vadose zone is idealized as composed of horizontal layers. Solute transport starts at the ground surface and moves vertically downwards to the water table. The perceived process is one-dimensional. This study used VS2DT, a computer code developed by the US Geological Survey, for simulating solute transport in variably saturated porous media

Experimental investigation of buried tritium in plant and animal tissues

International Nuclear Information System (INIS)

Kim, S. B.; Workman, W. J. G.; Davis, P. A.

2008-01-01

Buried exchangeable tritium appears as part of organically bound tritium (OBT) in the traditional experimental determination of OBT. Since buried tritium quickly exchanges with hydrogen atoms in the body following ingestion, assuming that it is part of OBT rather than part of tritiated water (HTO) could result in a significant overestimate of the ingestion dose. This paper documents an experimental investigation into the existence, amount and significance of buried tritium in plant and fish samples. OBT concentrations in the samples were determined in the traditional way and also following denaturing with five chemical solutions that break down large molecules and expose buried tritium to exchange with free hydrogen atoms. A comparison of the OBT concentrations before and after denaturing, together with the concentration of HTO in the supernatant obtained after denaturing, suggests that buried OBT may exist but makes up less than 5% of the OBT concentration in plants and at most 20% of the OBT concentration in fish. The effects of rinse time and rinse water volumes were investigated to optimize the removal of exchangeable OBT from the samples. (authors)

The surgical correction of buried penis: a new technique

NARCIS (Netherlands)

Boemers, T. M.; de Jong, T. P.

1995-01-01

We report a new surgical technique for the correction of buried penis. The study comprised 10 boys with buried penis. The technique consisted of resection of abnormal dartos attachments, unfurling of the prepuce and correction of the deficient shaft skin by reapproximation of the preputial skin

Detection and mapping of buried waste

International Nuclear Information System (INIS)

Stahl, G.; Odenweller, J.; Huff, D.

1996-01-01

A major environmental concern today is the characterization, remediation, and monitoring of Federal waste sites, such as those operated by the Department of Energy (DOE). A significant amount of hazardous waste is buried at known sites on DOE reservations. Determining the exact location of buried waste trenches is an important step in the characterization and remediation of these sites. Remotely sensed imagery offers a rich source of information for accomplishing this task. This paper presents a case study conducted at Solid Waste Storage Area 4 (SWSA 4) at Oak Ridge National Laboratory. Historical aerial photography and recently collected multispectral imagery were analyzed to determine the precise locations of the buried trenches. A comparison of the results to recent ground measurements indicates the strengths and weaknesses of the remote sensing approach. Further analysis of these ground data also provides an understanding of the phenomenology that gives rise to the imagery signatures associated with the trenches. Application of these techniques can significantly reduce the costs of site remediation. By knowing the trench locations precisely, rather than the general locations, remediation alternatives to contain and isolate the waste materials can be tailored appropriately

In situ vitrification: Application to buried waste

International Nuclear Information System (INIS)

Callow, R.A.; Thompson, L.E.

1991-01-01

Two in situ vitrification field tests were conducted in June and July 1990 at Idaho National Engineering Laboratory. In situ vitrification is a technology for in-place conversion of contaminated soils into a durable glass and crystalline waste form and is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to assess the general suitability of the process to remediate buried waste structures found at Idaho National Engineering Laboratory. In particular, these tests were designed as part of a treatability study to provide essential information on field performance of the process under conditions of significant combustible and metal wastes, and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology provided valuable operational control for successfully processing the high metal content waste. The results indicate that in situ vitrification is a feasible technology for application to buried waste. 2 refs., 5 figs., 2 tabs

Hazards assessment for the INEL Landfill Complex

International Nuclear Information System (INIS)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG ampersand G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility's operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment

Hazards assessment for the INEL Landfill Complex

Energy Technology Data Exchange (ETDEWEB)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG&G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility`s operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment.

Numerical Modeling of Mechanical Behavior for Buried Steel Pipelines Crossing Subsidence Strata.

Directory of Open Access Journals (Sweden)

J Zhang

Full Text Available This paper addresses the mechanical behavior of buried steel pipeline crossing subsidence strata. The investigation is based on numerical simulation of the nonlinear response of the pipeline-soil system through finite element method, considering large strain and displacement, inelastic material behavior of buried pipeline and the surrounding soil, as well as contact and friction on the pipeline-soil interface. Effects of key parameters on the mechanical behavior of buried pipeline were investigated, such as strata subsidence, diameter-thickness ratio, buried depth, internal pressure, friction coefficient and soil properties. The results show that the maximum strain appears on the outer transition subsidence section of the pipeline, and its cross section is concave shaped. With the increasing of strata subsidence and diameter-thickness ratio, the out of roundness, longitudinal strain and equivalent plastic strain increase gradually. With the buried depth increasing, the deflection, out of roundness and strain of the pipeline decrease. Internal pressure and friction coefficient have little effect on the deflection of buried pipeline. Out of roundness is reduced and the strain is increased gradually with the increasing of internal pressure. The physical properties of soil have a great influence on the mechanical properties of buried pipeline. The results from the present study can be used for the development of optimization design and preventive maintenance for buried steel pipelines.

Nuclear decay data measurements at the INEL ISOL facility

International Nuclear Information System (INIS)

Greenwood, R.C.; Helmer, R.G.; Putnam, M.H.; Struttmann, D.A.; Watts, K.D.

1991-01-01

In recent years, the use of the mass separation technique coupled on-line to a source of fission product nuclides has provided a wealth of new information on the nuclear decay properties of such nuclides. In addition to their relevance in basic studies of nuclear properties of neutron-rich nuclei, the fission product nuclides as a group, because of their intimate link with energy production in fission reactors, occupy a unique position in the field of applied nuclear decay data. Further, in addition to their critical role in nuclear reactor technology (decay heat source term, environmental concerns, etc.), such data have important applications in astrophysical calculations involving the rapid neutron capture process (r-process) of elemental synthesis in stellar environments. The scope of the nuclear decay data measurements being undertaken using the Idaho National Engineering Laboratory's (INEL) isotope separation on-line (ISOL) facility is focused on a systematic study of the gross nuclear decay properties of short-lived fission product isotopes, i.e., ground-state half-lives, beta-decay energies and beta-decay feeding (or beta-strength) distributions. In this paper, the authors discuss the results of new measurements of beta-decay energies and feeding distributions

Performance of buried pipe installation.

Science.gov (United States)

2010-05-01

The purpose of this study is to determine the effects of geometric and mechanical parameters : characterizing the soil structure interaction developed in a buried pipe installation located under : roads/highways. The drainage pipes or culverts instal...

Aging management and life assessment of buried commodities in nuclear power plants

International Nuclear Information System (INIS)

Park, J. H.; Jung, I. S.; Jo, H. S.; Kim, M. G.; Kim, S. T.; Lee, S. S.

2000-01-01

General field survey, inspection and life assessment were performed to establish effective aging management program of buried commodities in nuclear power plant. Basic informations on material characteristics, aging degradation experiences and maintenance history were gathered. Considering their degradation effects on power operation or safety, buried commodities were screened for the aging management priority. Various inspection techniques were applied in field survey and inspection, and their results were incorporated in the life assessment of buried commodities. In the aspect of aging degradation, general status of buried commodities were considered still sound while some revealed local degradation

Integrated safeguards and security for the INEL Special Isotope Separation Plant

International Nuclear Information System (INIS)

Warner, G.F.; Zack, N.R.

1990-01-01

This paper describes the development of the safeguards and security system that was to be used for the Special Isotope Separation (SIS) Production Plant. The US Department of Energy has postponed the construction of the SIS Plant that was to be built at the Idaho National Engineering Laboratory (INEL) site near Idaho Falls, Idaho. The Plant was designed to produce weapons grade plutonium from DOE owned fuel grade plutonium by converting off-spec. plutonium dioxide into metal buttons that would meet required chemical and isotopic specifications. Because this was to be a completely new facility there was a unique opportunity to provide an in-depth, ''state-of-the- art'' safeguards and security system without attempting to overlay upon an existing, older system. This facility was being designed to be in complete compliance with the new DOE Orders by integrating safeguards and security into the plant operating system and by providing graded protection to the areas of varying sensitivity within the plant

Response of steel buried pipeline to the three dimensional fault movement

International Nuclear Information System (INIS)

Zia Tohidi, R.; Shakib, H.

2003-01-01

Fault movement during an earthquake may have severe effect on buried pipelines as a lifeline element. A few studies are carried out on the behaviour of buried pipelines to this kind of damage and disruption. In most of these studies, the fault movements are modeled as two-dimensional. In this study, by modeling the pipe as a beam and the surrounding soil as nonlinear springs, the effect of three dimensional movement of fault on buried pipelines is investigated. Some important parameters such as; fault movement, depth of buried, geometrical characteristics of the pipe, angle of pipe- soil friction, angle of pipe- fault crossing, and the fault slip are considered in this study

Electron spin resonance characterization of trapping centers in Unibond reg-sign buried oxides

International Nuclear Information System (INIS)

Conley, J.F. Jr.; Lenahan, P.M.; Wallace, B.D.

1996-01-01

Electron spin resonance and capacitance vs. voltage measurements are used to evaluate the radiation response of Unibond buried oxides. When damaged by hole injection, it is found that Unibond reg-sign buried oxides exhibit a rough correspondence between E' centers and positive charge as well as generation of P b centers at the Unibond buried oxide/Si interface. In these respects, Unibond buried oxides qualitatively resemble thermal SiO 2 . However, a hydrogen complexed E' center known as the 74 G doublet is also detected in the Unibond buried oxides. This defect is not detectable in thermal SiO 2 under similar circumstances. Since the presence of 74 G doublet center is generally indicative of very high hydrogen content and since hydrogen is clearly a significant participant in radiation damage, this result suggests a qualitative difference between the radiation response of Unibond and thermal SiO 2 . Unibond results are also compared and contrasted with similar investigations on separation-by-implanted-oxygen (SIMOX) buried oxides. Although the charge trapping response of Unibond buried oxides may be inferior to that of radiation hardened thermal SiO 2 , it appears to be more simple and superior to that of SIMOX buried oxides

Total dose hardening of buried insulator in implanted silicon-on-insulator structures

International Nuclear Information System (INIS)

Mao, B.Y.; Chen, C.E.; Pollack, G.; Hughes, H.L.; Davis, G.E.

1987-01-01

Total dose characteristics of the buried insulator in implanted silicon-on-insulator (SOI) substrates have been studied using MOS transistors. The threshold voltage shift of the parasitic back channel transistor, which is controlled by charge trapping in the buried insulator, is reduced by lowering the oxygen dose as well as by an additional nitrogen implant, without degrading the front channel transistor characteristics. The improvements in the radiation characteristics of the buried insulator are attributed to the decrease in the buried oxide thickness or to the presence of the interfacial oxynitride layer formed by the oxygen and nitrogen implants

Sexual and Overall Quality of Life Improvements After Surgical Correction of "Buried Penis".

Science.gov (United States)

Hughes, Duncan B; Perez, Edgar; Garcia, Ryan M; Aragón, Oriana R; Erdmann, Detlev

2016-05-01

"Buried penis" is an increasing burden in our population with many possible etiologies. Although surgical correction of buried penis can be rewarding and successful for the surgeon, the psychological and functional impact of buried penis on the patient is less understood. The study's aim was to evaluate the sexual satisfaction and overall quality of life before and after buried penis surgery in a single-surgeon's patient population using a validated questionnaire (Changes in Sexual Functioning Questionnaire short-form). Using Likert scales generated from the questionnaire and 1-tailed paired t test analysis, we found that there was significantly improved sexual function after correction of a buried penis. Variables individually showed that there was significant improvement with sexual pleasure, urinating, and with genital hygiene postoperatively. There were no significant differences concerning frequency of pain with orgasms. Surgical correction of buried penis significantly improves the functional, sexual, and psychological aspects of patient's lives.

Quality assurance on the Idaho National Engineering Laboratory Buried Waste Program

International Nuclear Information System (INIS)

Rasmussen, T.L.

1989-01-01

This paper discusses the clean-up of an Idaho National Engineering Laboratory (INEL) site utilized for disposal of transuranic contaminated waste from 1954 until 1970. The author presents requirements of the environmental protection statutes that have generated quality assurance requirements in addition to those historically implemented as a part of facility design, construction and operation. A hierarchy of program guidance quality documentation and procedures is discussed. Data qualification and computer database management are identified as requirements

Test plan for buried waste containment system materials

International Nuclear Information System (INIS)

Weidner, J.; Shaw, P.

1997-03-01

The objectives of the FY 1997 barrier material work at the Idaho National Engineering and Environmental Laboratory are to (1) select a waste barrier material and verify that it is compatible with the Buried Waste Containment System Process, and (2) determine if, and how, the Buried Waste Containment System emplacement process affects the material properties and performance (on proof of principle scale). This test plan describes a set of measurements and procedures used to validate a waste barrier material for the Buried Waste Containment System. A latex modified proprietary cement manufactured by CTS Cement Manufacturing Company will be tested. Emplacement properties required for the Buried Waste Containment System process are: slump between 8 and 10 in., set time between 15 and 30 minutes, compressive strength at set of 20 psi minimum, and set temperature less than 100 degrees C. Durability properties include resistance to degradation from carbonate, sulfate, and waste-site soil leachates. A set of baseline barrier material properties will be determined to provide a data base for comparison with the barrier materials when tested in the field. The measurements include permeability, petrographic analysis to determine separation and/or segregation of mix components, and a set of mechanical properties. The measurements will be repeated on specimens from the field test material. The data will be used to determine if the Buried Waste Containment System equipment changes the material. The emplacement properties will be determined using standard laboratory procedures and instruments. Durability of the barrier material will be evaluated by determining the effect of carbonate, sulfate, and waste-site soil leachates on the compressive strength of the barrier material. The baseline properties will be determined using standard ASTM procedures. 9 refs., 1 fig., 2 tabs

47 CFR 32.2423 - Buried cable.

Science.gov (United States)

2010-10-01

... FOR TELECOMMUNICATIONS COMPANIES Instructions for Balance Sheet Accounts § 32.2423 Buried cable. (a... of cleaning manholes and ducts in connection with construction work and the cost of permits and...

Straddle-packer determination of the vertical distribution of hydraulic properties in the Snake River Plain Aquifer at well USGS-44, Idaho Chemical Processing Plant, INEL

International Nuclear Information System (INIS)

Monks, J.I.

1994-01-01

Many of the monitor wells that penetrate the upper portion of the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL) are open over large intervals that include multiple water-bearing zones. Most of these wells are equipped with dedicated submersible pumps. Water of varying quality from different water-bearing zones is mixed within the wells. The hydrologic properties of individual water bearing zones are difficult to determine. Water quality and water-level data on organic, heavy metal, and radioactive contaminants have been collected, reported, and interpreted from these monitor wells for more than forty years. The problems associated with well completions over large intervals through multiple water-bearing zones raise significant questions about the data. A straddle-packer system was developed and applied at the INEL site to investigate the monitor well network. The straddle-packer system, hydraulic testing methods, data analysis procedures, and testing results are described in this report. The straddle-packer system and the straddle-packer testing and data evaluation procedures can be improved for future testing at the INEL site. Recommended improvements to the straddle-packer system are: (1) improved transducer pressure sensing systems, (2) faster opening riser valve, and (3) an in-line flowmeter in the riser pipe. Testing and data evaluation recommended improvements are: (1) simultaneous valve opening during slug tests, (2) analysis of the ratio of the times for head change and recovery to occur, (3) constant-drawdown tests of high transmissivity intervals, (4) multiple-well aquifer tests, and (5) long term head monitoring

Preliminary systems design study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1992-01-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each. This volume contains the descriptions and other relevant information of the four subsystems required for most of the ex situ processing systems. This volume covers the metal decontamination and sizing subsystem, soils processing subsystem, low-level waste subsystem, and retrieval subsystem

Buried injector logic, a vertical IIL using deep ion implantation

NARCIS (Netherlands)

Mouthaan, A.J.

1987-01-01

A vertically integrated alternative for integrated injection logic has been realized, named buried injector logic (BIL). 1 MeV ion implantations are used to create buried layers. The vertical pnp and npn transistors have thin base regions and exhibit a limited charge accumulation if a gate is

Risk and cost tradeoffs for remote retrieval of buried waste

International Nuclear Information System (INIS)

Hyde, R.A.; Grienbenow, B.E.; Nickelson, D.F.

1994-01-01

The Buried Waste Integrated Demonstration is supporting the development, demonstration, testing, and evaluation of a suite of technologies that, when integrated with commercially available technologies, form a comprehensive system for the remediation of radioactive and hazardous buried waste. As a part of the program's technology development, remote retrieval equipment is being developed and tested for the remediation of buried waste. During remedial planning, several factors are considered when choosing remote versus manual retrieval systems. Time that workers are exposed to radioactivity, chemicals, air particulate, and industrial hazards is one consideration. The generation of secondary waste is also a consideration because it amounts to more waste to treat and some wastes may require special handling or treatment. Cost is also a big factor in determining whether remote or manual operations will be used. Other considerations include implementability, effectiveness, and the number of required personnel. This paper investigates each of these areas to show the risk and cost benefits and limitations for remote versus manual retrieval of buried waste

Thermal treatment technology at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hillary, J.M.

1994-01-01

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

Factors affecting thermal infrared images at selected field sites

International Nuclear Information System (INIS)

Sisson, J.B.; Ferguson, J.S.

1993-07-01

A thermal infrared (TIR) survey was conducted to locate surface ordnance in and around the Naval Ordnance Disposal Area, and a thermal anomaly was found. This report documents studies conducted to identify the position of cause of the thermal anomaly. Also included are results of a long path Fourier transform infrared survey, soil sampling activities, soil gas surveys, and buried heater studies. The results of these studies indicated that the thermal anomaly was caused by a gravel pad, which had thermal properties different than those of the surrounding soil. Results from this investigation suggest that TIR is useful for locating surface objects having a high thermal inertia compared to the surrounding terrain, but TIR is of very limited use for characterizing buried waste or other similar buried objects at the INEL

Buried Object Detection Method Using Optimum Frequency Range in Extremely Shallow Underground

Science.gov (United States)

Sugimoto, Tsuneyoshi; Abe, Touma

2011-07-01

We propose a new detection method for buried objects using the optimum frequency response range of the corresponding vibration velocity. Flat speakers and a scanning laser Doppler vibrometer (SLDV) are used for noncontact acoustic imaging in the extremely shallow underground. The exploration depth depends on the sound pressure, but it is usually less than 10 cm. Styrofoam, wood (silver fir), and acrylic boards of the same size, different size styrofoam boards, a hollow toy duck, a hollow plastic container, a plastic container filled with sand, a hollow steel can and an unglazed pot are used as buried objects which are buried in sand to about 2 cm depth. The imaging procedure of buried objects using the optimum frequency range is given below. First, the standardized difference from the average vibration velocity is calculated for all scan points. Next, using this result, underground images are made using a constant frequency width to search for the frequency response range of the buried object. After choosing an approximate frequency response range, the difference between the average vibration velocity for all points and that for several points that showed a clear response is calculated for the final confirmation of the optimum frequency range. Using this optimum frequency range, we can obtain the clearest image of the buried object. From the experimental results, we confirmed the effectiveness of our proposed method. In particular, a clear image of the buried object was obtained when the SLDV image was unclear.

Buried Waste Integrated Demonstration stakeholder involvement model

International Nuclear Information System (INIS)

Kaupanger, R.M.; Kostelnik, K.M.; Milam, L.M.

1994-04-01

The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy (DOE) Office of Technology Development. BWID supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. Stakeholder participation in the DOE Environmental Management decision-making process is critical to remediation efforts. Appropriate mechanisms for communication with the public, private sector, regulators, elected officials, and others are being aggressively pursued by BWID to permit informed participation. This document summarizes public outreach efforts during FY-93 and presents a strategy for expanded stakeholder involvement during FY-94

Buried Landmines in Libya and Detection Technologies

International Nuclear Information System (INIS)

El-Bakkoush, F.A.

2015-01-01

In this Article, presentation and discussion of the impact of detonated buried land mines in vast areas of land in Libya are given, especially from economical and social point of view. The methods and techniques which are currently used to allocate the positions of buried land mines during de mining operations are mentioned and discussed with emphasize on their strength and weakness. These include mechanical removing methods, prodders, metal detectors, ground penetrating radar and sniffing dogs. Furthermore, the novel and most developed detection techniques invented to detect land mines using SQUDS and neutron techniques based on thermal neutron backscattering and elemental analysis by fast and thermal neutrons are given and discussed.

Detection of a buried object with pulse-compensated wire antennas

NARCIS (Netherlands)

Vossen, S.H.J.A.; Tijhuis, A.G.; Lepelaars, E.S.A.M.; Zwamborn, A.P.M.

2003-01-01

For the detection of a buried object we consider two straight thin-wire antennas above an interface between two homogeneous dielectric half spaces. One antenna is a transmitting wire and the other is a receiving wire. Our aim is to use this simple antenna set up for the detection of buried objects

Imaging of buried phosphorus nanostructures in silicon using scanning tunneling microscopy

Energy Technology Data Exchange (ETDEWEB)

Oberbeck, Lars [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); TOTAL Marketing Services, New Energies, La Défense 10, 92069 Paris La Défense Cedex (France); Reusch, Thilo C. G.; Hallam, Toby; Simmons, Michelle Y., E-mail: n.curson@ucl.ac.uk, E-mail: michelle.simmons@unsw.edu.au [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); Schofield, Steven R. [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); London Centre for Nanotechnology, UCL, London WC1H 0AH (United Kingdom); Department of Physics and Astronomy, UCL, London WC1E 6BT (United Kingdom); Curson, Neil J., E-mail: n.curson@ucl.ac.uk, E-mail: michelle.simmons@unsw.edu.au [Centre for Quantum Computation and Communication Technology, School of Physics, University of New South Wales, Sydney, New South Wales 2052 (Australia); London Centre for Nanotechnology, UCL, London WC1H 0AH (United Kingdom); Department of Electronic and Electrical Engineering, UCL, London WC1E 7JE (United Kingdom)

2014-06-23

We demonstrate the locating and imaging of single phosphorus atoms and phosphorus dopant nanostructures, buried beneath the Si(001) surface using scanning tunneling microscopy. The buried dopant nanostructures have been fabricated in a bottom-up approach using scanning tunneling microscope lithography on Si(001). We find that current imaging tunneling spectroscopy is suited to locate and image buried nanostructures at room temperature and with residual surface roughness present. From these studies, we can place an upper limit on the lateral diffusion during encapsulation with low-temperature Si molecular beam epitaxy.

Ultra thin buried oxide layers formed by low dose Simox process

Energy Technology Data Exchange (ETDEWEB)

Aspar, B.; Pudda, C.; Papon, A.M. [CEA Centre d`Etudes de Grenoble, 38 (France). Lab. d`Electronique et d`Instrumentation; Auberton Herve, A.J.; Lamure, J.M. [SOITEC, 38 - Grenoble (France)

1994-12-31

Oxygen low dose implantation is studied for two implantation energies. For 190 keV, a continuous buried oxide layer is obtained with a high dislocation density in the top silicon layer due to SiO{sub 2} precipitates. For 120 keV, this silicon layer is free of SiO{sub 2} precipitate and has a low dislocation density. Low density of pin-holes is observed in the buried oxide. The influence of silicon islands in the buried oxide on the breakdown electric fields is discussed. (authors). 6 refs., 5 figs.

Ultra thin buried oxide layers formed by low dose Simox process

International Nuclear Information System (INIS)

Aspar, B.; Pudda, C.; Papon, A.M.

1994-01-01

Oxygen low dose implantation is studied for two implantation energies. For 190 keV, a continuous buried oxide layer is obtained with a high dislocation density in the top silicon layer due to SiO 2 precipitates. For 120 keV, this silicon layer is free of SiO 2 precipitate and has a low dislocation density. Low density of pin-holes is observed in the buried oxide. The influence of silicon islands in the buried oxide on the breakdown electric fields is discussed. (authors). 6 refs., 5 figs

Imaging of buried phosphorus nanostructures in silicon using scanning tunneling microscopy

International Nuclear Information System (INIS)

Oberbeck, Lars; Reusch, Thilo C. G.; Hallam, Toby; Simmons, Michelle Y.; Schofield, Steven R.; Curson, Neil J.

2014-01-01

We demonstrate the locating and imaging of single phosphorus atoms and phosphorus dopant nanostructures, buried beneath the Si(001) surface using scanning tunneling microscopy. The buried dopant nanostructures have been fabricated in a bottom-up approach using scanning tunneling microscope lithography on Si(001). We find that current imaging tunneling spectroscopy is suited to locate and image buried nanostructures at room temperature and with residual surface roughness present. From these studies, we can place an upper limit on the lateral diffusion during encapsulation with low-temperature Si molecular beam epitaxy.

Bearing and Range Estimation Algorithm for Buried Object in Underwater Acoustics

Directory of Open Access Journals (Sweden)

Dong Han

2009-01-01

(DOA of objects and objects-sensors distances, is used in MUSIC algorithm instead of classical model. The influence of the depth of buried objects is discussed. Finally, the numerical results are given in the case of buried cylindrical shells.

Compact Buried Ducts in a Hot-Humid Climate House

Energy Technology Data Exchange (ETDEWEB)

Mallay, D. [Home Innovation Research Labs, Upper Marlboro, MD (United States)

2016-01-01

A system of compact, buried ducts provides a high-performance and cost-effective solution for delivering conditioned air throughout the building. This report outlines research activities that are expected to facilitate adoption of compact buried duct systems by builders. The results of this research would be scalable to many new house designs in most climates and markets, leading to wider industry acceptance and building code and energy program approval.

Performance evaluation of buried pipe installation.

Science.gov (United States)

2010-05-01

The purpose of this study is to determine the effects of geometric and mechanical parameters characterizing the soil structure interaction developed in a buried pipe installation located under roads/highways. The drainage pipes or culverts installed ...

Detection and characterization of buried lunar craters with GRAIL data

Science.gov (United States)

Sood, Rohan; Chappaz, Loic; Melosh, Henry J.; Howell, Kathleen C.; Milbury, Colleen; Blair, David M.; Zuber, Maria T.

2017-06-01

We used gravity mapping observations from NASA's Gravity Recovery and Interior Laboratory (GRAIL) to detect, characterize and validate the presence of large impact craters buried beneath the lunar maria. In this paper we focus on two prominent anomalies detected in the GRAIL data using the gravity gradiometry technique. Our detection strategy is applied to both free-air and Bouguer gravity field observations to identify gravitational signatures that are similar to those observed over buried craters. The presence of buried craters is further supported by individual analysis of regional free-air gravity anomalies, Bouguer gravity anomaly maps, and forward modeling. Our best candidate, for which we propose the informal name of Earhart Crater, is approximately 200 km in diameter and forms part of the northwestern rim of Lacus Somniorum, The other candidate, for which we propose the informal name of Ashoka Anomaly, is approximately 160 km in diameter and lies completely buried beneath Mare Tranquillitatis. Other large, still unrecognized, craters undoubtedly underlie other portions of the Moon's vast mare lavas.

Risk and cost tradeoffs for remote retrieval of buried waste

Energy Technology Data Exchange (ETDEWEB)

Hyde, R.A.; Grienbenow, B.E.; Nickelson, D.F.

1994-12-31

The Buried Waste Integrated Demonstration is supporting the development, demonstration, testing, and evaluation of a suite of technologies that, when integrated with commercially available technologies, form a comprehensive system for the remediation of radioactive and hazardous buried waste. As a part of the program`s technology development, remote retrieval equipment is being developed and tested for the remediation of buried waste. During remedial planning, several factors are considered when choosing remote versus manual retrieval systems. Time that workers are exposed to radioactivity, chemicals, air particulate, and industrial hazards is one consideration. The generation of secondary waste is also a consideration because it amounts to more waste to treat and some wastes may require special handling or treatment. Cost is also a big factor in determining whether remote or manual operations will be used. Other considerations include implementability, effectiveness, and the number of required personnel. This paper investigates each of these areas to show the risk and cost benefits and limitations for remote versus manual retrieval of buried waste.

Preparation and infrared absorption properties of buried SiC layers

International Nuclear Information System (INIS)

Yan Hui; Chen Guanghua; Wong, S.P.; Kwok, R.W.M.

1997-01-01

Buried SiC layers were formed by using a metal vapor vacuum arc (MEVVA) ion source, with C + ions implanted into Si substrates under different doses. In the present study, the extracted voltage was 50 kV and the ion dose was varied from 3.0 x 10 17 to 1.6 x 10 18 cm -2 . According to infrared absorption measurements, it was fount that the structure of the buried SiC layers depended on the ion dose. Moreover, the results also demonstrated that the buried SiC layers including cubic crystalline SiC could be synthesized at an averaged substrate temperature of lower than 400 degree C with the MEVVA ion source

A fully coupled finite element model for stress distribution in buried gas pipeline

International Nuclear Information System (INIS)

Yahya Sukirman; Zainal Zakaria; Woong Soon Yue

2001-01-01

The study of stress-strain relationship is very important in many designs of buried structures over the years. The behavior and mechanism between the interaction of soil and buried structures such as a natural pipeline will mostly contributes to the integrity of the pipeline. This paper presents a fully coupled finite element of consolidation analysis model to study the stress-strain distribution along a buried pipeline before it excess its maximum deformation limit. The behavior of the soil-pipeline system can be modelled by a non-linear elasto-plastic based on Mohr-Coulomb and critical state yield surfaces. The deformation and deflection of the pipeline due to drained and external loading condition will be considered here. Finally the stress-strain distribution of the buried pipeline will be utilised to obtain the maximum deformation limit and the deflection of the buried pipeline. (Author)

Novel high-voltage power lateral MOSFET with adaptive buried electrodes

International Nuclear Information System (INIS)

Zhang Wen-Tong; Wu Li-Juan; Qiao Ming; Luo Xiao-Rong; Zhang Bo; Li Zhao-Ji

2012-01-01

A new high-voltage and low-specific on-resistance (R on,sp ) adaptive buried electrode (ABE) silicon-on-insulator (SOI) power lateral MOSFET and its analytical model of the electric fields are proposed. The MOSFET features are that the electrodes are in the buried oxide (BOX) layer, the negative drain voltage V d is divided into many partial voltages and the output to the electrodes is in the buried oxide layer and the potentials on the electrodes change linearly from the drain to the source. Because the interface silicon layer potentials are lower than the neighboring electrode potentials, the electronic potential wells are formed above the electrode regions, and the hole potential wells are formed in the spacing of two neighbouring electrode regions. The interface hole concentration is much higher than the electron concentration through designing the buried layer electrode potentials. Based on the interface charge enhanced dielectric layer field theory, the electric field strength in the buried layer is enhanced. The vertical electric field E I and the breakdown voltage (BV) of ABE SOI are 545 V/μm and −587 V in the 50 μm long drift region and the 1 μm thick dielectric layer, and a low R on,sp is obtained. Furthermore, the structure also alleviates the self-heating effect (SHE). The analytical model matches the simulation results. (condensed matter: electronic structure, electrical, magnetic, and optical properties)

Contemporary Management of Adult Acquired Buried Penis.

Science.gov (United States)

Jun, M S; Gallegos, M A; Santucci, R A

2018-04-06

In 2014, The World Health Organization reported that 1.9 billion adults, 39% of the population, were overweight or obese [1]. Unlike most complications of obesity, adult acquired buried penis is an uncomfortable topic which may be overlooked. Patients are often encouraged to lose weight, but this is futile. Simple weight loss will not cure buried penis, as it is a multifactorial condition caused by a combination of: a) overhanging escutcheon from overweight, b) lichen sclerosus, which often contracts and destroys the penile shaft skin, and c) loss of normal penile shaft attachments to the penile skin. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

Kelvin probe characterization of buried graphitic microchannels in single-crystal diamond

International Nuclear Information System (INIS)

Bernardi, E.; Battiato, A.; Olivero, P.; Vittone, E.; Picollo, F.

2015-01-01

In this work, we present an investigation by Kelvin Probe Microscopy (KPM) of buried graphitic microchannels fabricated in single-crystal diamond by direct MeV ion microbeam writing. Metal deposition of variable-thickness masks was adopted to implant channels with emerging endpoints and high temperature annealing was performed in order to induce the graphitization of the highly-damaged buried region. When an electrical current was flowing through the biased buried channel, the structure was clearly evidenced by KPM maps of the electrical potential of the surface region overlying the channel at increasing distances from the grounded electrode. The KPM profiling shows regions of opposite contrast located at different distances from the endpoints of the channel. This effect is attributed to the different electrical conduction properties of the surface and of the buried graphitic layer. The model adopted to interpret these KPM maps and profiles proved to be suitable for the electronic characterization of buried conductive channels, providing a non-invasive method to measure the local resistivity with a micrometer resolution. The results demonstrate the potential of the technique as a powerful diagnostic tool to monitor the functionality of all-carbon graphite/diamond devices to be fabricated by MeV ion beam lithography

The Buried Town of Beaver.

Science.gov (United States)

Jostad, Karen

Local history as source material for environmental education is uniquely portrayed in this resource kit. Utilizing a Winona County Historical Society publication, "The Beaver Story" and accompanied by a teacher's guide, "The Buried Town of Beaver," and other teaching aids, a case study of the area can be developed. Based on the reminiscences of…

Tabernaemontana divaricata leaves extract exacerbate burying behavior in mice

Directory of Open Access Journals (Sweden)

Raj Chanchal

2015-06-01

Full Text Available Objective: Tabernaemontana divaricata (TD from Apocynaceae family offers the traditional folklore medicinal benefits such as an anti-epileptic, anti-mania, brain tonic, and anti-oxidant. The aim of the present study was to evaluate the effect of ethanolic extract of TD leaves on burying behavior in mice. Materials and Methods:Mice were treated with oral administration (p.o. of ethanolic extract of TD (100, 200, and 300 mg/kg. Fluoxetine (FLX, a selective serotonin reuptake inhibitor was used as a reference drug. Obsessive-compulsive behavior was evaluated using marble-burying apparatus. Results:TD at doses of 100, 200, and 300 mg/kg dose-dependently inhibited the obsessive and compulsive behavior. The similar results were obtained from 5, 10, and 20 mg/kg of FLX. TD and FLX did not affect motor activity. Conclusion: The results indicated that TD and FLX produced similar inhibitory effects on marble-burying behavior.

Development of a teleoperated backhoe for buried waste excavation

International Nuclear Information System (INIS)

Burks, B.L.; Killough, S.M.; Thompson, D.H.

1992-01-01

For nearly five decades the United States (US) Department of Energy (DOE) and its predecessor agencies have engaged in broad-based research and development activities as well as nuclear weapons component production. As a by-product of these activities, large quantities of waste materials have been granted. One of the most common approaches used for solid waste storage was to bury waste containers in pits and trenches. With the current emphasis on environmental restoration, DOE now plans to either retrieve much of the legacy of buried waste or stabilize the waste in place via in situ vitrification or other means. Because of the variety of materials that have been buried over the years, the hazards of retrieval are significant if performed using conventional manned operations. The potential hazards, in addition to radiation exposure, include pyrophorics, toxic chemicals, and explosives. Although manifests exist for much of the buried waste, these records are often incomplete compared to today's requirements. Because of the potential hazards and uncertainty about waste contents and container integrity, it is highly desirable to excavate these wastes using remotely operated equipment. In this paper the authors describe the development of a teleoperated military tractor called the Small Emplacement Excavator (SEE). Development of the SEE is being funded jointly by both DOE and the US Army. The DOE sponsor is the Office of Technology Development (OTD) Robotics Program. The US Army sponsor is the Program Manager for Ammunition Logistics, Picatinny Arsenal. The primary interest for DOE is in the application to remote excavation of buried waste, while the primary emphasis for the US Army is in the remote retrieval of unexploded ordnance. Technical requirements for these two tasks are very similar and, therefore, justify a joint development project. 1 ref

Preliminary Systems Design Study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Quapp, W.J.; Feizollahi, F.; Del Signore, J.C.

1991-07-01

The System Design Study (SDS), part of the Waste Technology Development Department at Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic (TRU) waste stored at the Radioactive Waste Management Complex's (RWMC's) Subsurface Disposal Area (SDA) at INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. SDS resulted in the development of technology requirements including demonstration, testing and evaluation activities needed for implementing each concept. The SDS results are published in eight volumes. Volume 1 contains an executive summary. The SDS summary and analysis of results are presented in volume 2. Volumes 3 through 7 contain detailed descriptions of twelve system and four subsystem concepts. Volume 8 contains the appendices. 3 figs., 3 tabs

A summary of the environmental restoration program retrieval demonstration project at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

McQuary, J.

1991-02-01

This report provides a summary of the Environmental Restoration Program's Retrieval Demonstration Project at the Idaho National Engineering Laboratory. This project developed concepts for demonstrating facilities and equipment for the retrieval of buried transuranic mixed waste at the INEL. Included is a brief assessment of the viability, cost effectiveness, and safety of retrieval based on the developed concept. Changes made in Revision 1 reflect editorial changes only. 31 refs., 1 fig

Locating a buried magnetic dipole

Energy Technology Data Exchange (ETDEWEB)

Caffey, T.W.H.

1977-01-01

The theoretical basis and required computations for locating a buried magnetic dipole are outlined. The results are compared with measurements made with a tiltable coil lowered to a depth of 20 m in a vertical borehole within a three-layered earth. this work has application to the rescue of trapped miners. 3 figures, 1 table. (RWR)

Technical Review on Fitness-for-Service for Buried Pipe by ASME Code Case N-806

International Nuclear Information System (INIS)

Park, Sang Kyu; Lee, Yo Seop; So, Il Su; Lim, Bu Taek

2012-01-01

Fitness-for-Service is a useful technology to determine replacement timing, next inspection timing or in-service when nuclear power plant's buried pipes are damaged. If is possible for buried pipes to be aged by material loss, cracks and occlusion as operating time goes by. Therefore Fitness-for-Service technology for buried pipe is useful for plant industry to perform replacement and repair. Fitness-for-Service for buried pipe is studied in terms of existing code and standard for Fitness-for-Service and a current developing code case. Fitness-for-Service for buried pipe was performed according to Code Case N-806 developed by ASME (American Society of Mechanical Engineers)

Exposed versus buried intramedullary implants for pediatric forearm fractures: a comparison of complications.

Science.gov (United States)

Kelly, Brian A; Miller, Patricia; Shore, Benjamin J; Waters, Peter M; Bae, Donald S

2014-12-01

The purpose of this study was to compare the rate of complications between buried and exposed intramedullary implants after fixation of pediatric forearm fractures. A retrospective comparative cohort study of 339 children treated with intramedullary fixation for displaced forearm fractures between 2004 and 2009 was performed. Implants were left exposed in 128 patients (37.8%) and buried beneath the skin in 208 patients (61.4%); 3 patients had buried and exposed hardware (0.9%). Data on demographics, injury, surgical technique, and complications were analyzed. The buried implant group was older (mean 10.3 vs. 8.5 y; P exposed implant group. The buried group had their implants removed later than the exposed group (median 3.5 vs. 1.2 mo; P exposed implants were successfully removed in the office. Complications were seen in 56 patients (16.5%). There were 16 patients (4.7%) with refracture and 12 patients (3.5%) with infection. The buried and exposed implant groups did not differ significantly with respect to refracture (3.1% vs. 7.0%; P = 0.20), infection (3.5% vs. 2.3%; P = 0.66), or overall complications (14.5% vs. 17.2%; P = 0.87). There was also no difference between groups with respect to loss of reduction, nondelayed or delayed union, loss of motion, hypertrophic granuloma, or tendon rupture. Buried implants were also associated with penetration through the skin (3.9%). Injury to the dominant arm and need for open reduction were significant predictors of complication (OR = 1.01; 95% CI, 1.001-1.012; P = 0.02 and OR = 0.51; 95% CI, 0.264-0.974; P = 0.04, respectively). There were no significant differences seen in number of infections, refractures, or overall complications based on whether implants were left exposed or buried beneath the skin after surgery. Level III, therapeutic.

Pannus Is the New Prepuce? Penile Cancer in a Buried Phallus

Directory of Open Access Journals (Sweden)

Jared Manwaring

2015-01-01

Full Text Available Two males presented to our urology department with complaints of bleeding and malodor from buried phallus within a suprapubic fat pad. Although both men had neonatal circumcisions, advanced penile carcinoma was found in both men. Formal penectomies showed high grade, poorly differentiated squamous cell carcinoma invading the corporal bodies and urethra. Buried penis represents a difficulty in early detection of suspicious lesions but may also provide an environment susceptible to poor hygiene and subsequent chronic inflammation. Patients with buried penis may be at a higher risk for development of invasive penile cancer and may benefit from regular and thorough genital exams.

Detection of a buried wire with two resistively loaded wire antennas

NARCIS (Netherlands)

Vossen, S.H.J.A.; Tijhuis, A.G.; Lepelaars, E.S.A.M.; Zwamborn, A.P.M.

2002-01-01

The use of two identical straight thin-wire antennas for the detection of a buried wire is analyzed with the aid of numerical calculations. The buried wire is located below an interface between two homogeneous half-spaces. The detection setup, which is formed by a transmitting and a receiving wire,

Displaced humeral lateral condyle fractures in children: should we bury the pins?

Science.gov (United States)

Das De, Soumen; Bae, Donald S; Waters, Peter M

2012-09-01

The purpose of this investigation was to determine if leaving Kirschner wires exposed is more cost-effective than burying them subcutaneously after open reduction and internal fixation (ORIF) of humeral lateral condyle fractures. A retrospective cohort study of all lateral condyle fractures treated over a 10-year period at a single institution was performed. Data on surgical technique, fracture healing, and complications were analyzed, as well as treatment costs. A decision analysis model was then constructed to compare the strategies of leaving the pins exposed versus buried. Finally, sensitivity analyses were performed, assessing cost-effectiveness when infection rates and costs of treating deep infections were varied. A total of 235 children with displaced fractures were treated with ORIF using Kirschner wires. Pins were left exposed in 41 cases (17.4%) and buried in 194 cases (82.6%); the age, sex, injury mechanisms, and fracture patterns were similar in both the groups. The median time to removal of implants was shorter with exposed versus buried pins (4 vs. 6 wk, Pfracture union or loss of reduction rates. The rate of superficial infection was higher with exposed pins (9.8% vs. 3.1%), but this was not statistically significant (P=0.076). There were no deep infections with exposed pins, whereas the rate of deep infection was 0.5% with buried pins (P=1.00). Buried pins were associated with additional complications, including symptomatic implants (7.2%); pins protruding through the skin (16%); internal pin migration necessitating additional surgery (1%); and skin necrosis (1%). The decision analysis revealed that leaving pins exposed resulted in an average cost savings of $3442 per patient. This strategy remained cost-effective even when infection rates with exposed pins approached 40%. Leaving the pins exposed after ORIF of lateral condyle fractures is safe and more cost-effective than burying the pins subcutaneously. Retrospective cohort study (level III).

Role and development of soil parameters for seismic responses of buried lifelines

Energy Technology Data Exchange (ETDEWEB)

Wang, L.R.L.

1983-01-01

Buried lifelines, e.g. oil, gas, water and sewer pipelines have been damaged heavily in recent earthquakes such as 1971 San Fernando Earthquake, in U.S.A., 1976 Tangshan Earthquake, in China, and 1978 MiyagiKen-Oki Earthquake, in Japan, among others. Researchers on the seismic performance of these buried lifelines have been initiated in the United States and many other countries. Various analytical models have been proposed. However, only limited experimental investigations are available. The sources of earthquake damage to buried lifelines include landslide, tectonic uplift-subsidence, soil liquefaction, fault displacement and ground shaking (effects of wave propagation). This paper is concerned with the behavior of buried lifeline systems subjected to surface faulting and ground shaking. The role and development of soil parameters that significantly influence the seismic responses are discussed. The scope of this paper is to examine analytically the influence of various soil and soilstructure interaction parameters to the seismic responses of buried pipelines, to report the currently available physical data of these and related parameters for immediate applications, and to describe the experiments to obtain additional information on soil resistant characteristics to longitudinal pipe motions.

Ultrasmooth metallic films with buried nanostructures for backside reflection-mode plasmonic biosensing

Energy Technology Data Exchange (ETDEWEB)

Lindquist, N.C.; Johnson, T.W.; Jose, J.; Otto, L.M. [Laboratory of Nanostructures and Biosensing, Department of Electrical and Computer Engineering, University of Minnesota, Minneapolis, MN 55455 (United States); Oh, S.H. [Laboratory of Nanostructures and Biosensing, Department of Electrical and Computer Engineering, University of Minnesota, Minneapolis, MN 55455 (United States); Department of Biophysics and Chemical Biology, Seoul National University, Seoul, 151-747 (Korea, Republic of)

2012-11-15

A new plasmonic device architecture based on ultrasmooth metallic surfaces with buried plasmonic nanostructures is presented. Using template-stripping techniques, ultrathin gold films with less than 5 Aa surface roughness are optically coupled to an arbitrary arrangement of buried metallic gratings, rings, and nanodots. As a prototypical example, linear plasmonic gratings buried under an ultrasmooth 20 nm thick gold surface for biosensing are presented. The optical illumination and collection are completely decoupled from the microfluidic delivery of liquid samples due to the backside, reflection-mode geometry. This allows for sensing with opaque or highly scattering liquids. With the buried nanostructure design, high sensitivity and decoupled backside (reflective) optical access are maintained, as with traditional prism-based surface plasmon resonance (SPR) sensors. In addition, the benefits offered by nanoplasmonic sensors such as spectral tunability and high-resolution, wide-field SPR imaging with normal-incidence epi-illumination that is simple to construct and align are gained as well. Beyond sensing, the buried plasmonic nanostructures with ultrasmooth metallic surfaces can benefit nanophotonic waveguides, surface-enhanced spectroscopy, nanolithography, and optical trapping. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Thermal tests of a transport / Storage cask in buried conditions

International Nuclear Information System (INIS)

Yamakawa, H.; Gomi, Y.; Saegusa, T.; Ito, C.

1998-01-01

Thermal tests for a hypothetical accident which simulated accidents caused by building collapse in case of an earthquake were conducted using a full-scale dry type transport and storage cask (total heat load: 23 kW). The objectives of these tests were to clarify the heat transfer features of the buried cask under such accidents and the time limit for maintaining the thermal integrity of the cask. Moreover, thermal analyses of the test cask under the buried conditions were carried out on basis of experimental results to establish methodology for the thermal analysis. The characteristics of the test cask are described as well as the test method used. The heat transfer features of the buried cask under such accidents and a time for maintaining the thermal integrity of the cask have been obtained. (O.M.)

GWSCREEN: A semi-analytical model for assessment of the groundwater pathway from surface or buried contamination. Theory and user`s manual, Version 2.0: Revision 2

Energy Technology Data Exchange (ETDEWEB)

Rood, A.S.

1994-06-01

Multimedia exposure assessment of hazardous chemicals and radionuclides requires that all pathways of exposure be investigated. The GWSCREEN model was designed to perform initial screening calculations for groundwater pathway impacts resulting from the leaching of surficial and buried contamination at CERCLA sites identified as low probability hazard at the INEL. In Version 2.0, an additional model was added to calculate impacts to groundwater from the operation of a percolation pond. The model was designed to make best use of the data that would potentially be available. These data include the area and depth of contamination, sorptive properties and solubility limit of the contaminant, depth to aquifer, and the physical properties of the aquifer (porosity, velocity, and dispersivity). For the pond model, data on effluent flow rates and operation time are required. Model output includes the limiting soil concentration such that, after leaching and transport to the aquifer, regulatory contaminant levels in groundwater are not exceeded. Also, groundwater concentration as a function of time may be calculated. The model considers only drinking water consumption and does not include the transfer of contamination to food products due to irrigation with contaminated water. Radiological dose, carcinogenic risk, and the hazard quotient are calculated for the peak time using the user-defined input mass (or activity). Appendices contain sample problems and the source code listing.

The acute and long-term neurotoxic effects of MDMA on marble burying behaviour in mice.

Science.gov (United States)

Saadat, Kathryn S; Elliott, J Martin; Colado, M Isabel; Green, A Richard

2006-03-01

When mice are exposed to harmless objects such as marbles in their cage they bury them, a behaviour sometimes known as defensive burying. We investigated the effect of an acute dose of MDMA (èecstasy') and other psychoactive drugs on marble burying and also examined the effect of a prior neurotoxic dose of MDMA or p-chloroamphetamine (PCA) on burying. Acute administration of MDMA produced dose-dependent inhibition of marble burying (EC50: 7.6 micro mol/kg). Other drugs that enhance monoamine function also produced dose-dependent inhibition: methamphetamine PCA paroxetine MDMA GBR 12909 methylphenidate. None of these drugs altered locomotor activity at a dose that inhibited burying. A prior neurotoxic dose of MDMA, which decreased striatal dopamine content by 60%, but left striatal 5-HT content unaltered, did not alter spontaneous marble burying 18 or 40 days later. However, a neurotoxic dose of PCA which decreased striatal dopamine by 60% and striatal 5-HT by 70% attenuated marble burying 28 days later. Overall, these data suggest that MDMA, primarily by acutely increasing 5-HT function, acts like several anxiolytic drugs in this behavioural model. Long-term loss of cerebral 5-HT content also produced a similar effect. Since this change was observed only after 28 days, it is probably due to an adaptive response in the brain.

Analysis of buried pipelines at Kozloduy

International Nuclear Information System (INIS)

Asfura, A.

1999-01-01

This paper describes the analysis of the buried pipelines at Kozloduy NPP. It involves the description of the studied pipelines, their properties, a detailed description of the methodology applied, and the evaluation of the soil strain field as well as the graphical representation of the results obtained

Identification of buried victims in natural disaster with GPR method

Science.gov (United States)

Dewi, Rianty Kusuma; Kurniawan, Adityo; Taqwantara, Reyhan Fariz; Iskandar, Farras M.; Naufal, Taufiq Ziyan; Widodo

2017-07-01

Indonesian is one of the most seismically active regions in the world and has very complicated plate convergence because there is meeting point of several tectonic plates. The complexity of tectonic features causes a lot of natural disasters such as landslides, tsunamis, earth quakes, volcanoes eruption, etc. Sometimes, the disasters occurs in high populated area and causing thousands to millions of victim been buried under the rumble. Unfortunately, the evacuation still uses the conventional method such using rescue dogs whereas the sensitivity of smell is decrease when the victims buried under the level of the ground. The purpose of this study is to detect buried bodies using GPR method, so it can enhance the effectiveness and the efficiency in looking for the disaster victims. GPR method is used because it can investigate things under the ground. A detailed GPR research has been done in Cikutra Graveyard, Bandung, with corpse buried two week until two years before the research. The radar profiles from this research showed amplitude contras anomaly between the new corpse and the old ones. We obtained the amplitude contras at 1.2-1.4 meters under the surface. This method proved to be effective but still need more attention on undulated surface and non-soil areas.

The initiation and linkage of surface fractures above a buried strike ...

Indian Academy of Sciences (India)

a buried strike-slip fault: An experimental approach. N Ghosh and A ... conditions viz., (i) heterogeneous simple shear of the cover rocks above a buried strike slip fault. (wrench .... (iii) study of fracture types in the damage zones from Gozo .... was dominant, the results may vary from a true ... For example, as shown in figure 5 ...

Quality Assurance Project Plan for the Gas Generation Testing Program at the INEL

International Nuclear Information System (INIS)

1994-10-01

The data quality objectives (DQOs) for the Program are to evaluate compliance with the limits on total gas generation rates, establish the concentrations of hydrogen and methane in the total gas flow, determine the headspace concentration of VOCs in each drum prior to the start of the test, and obtain estimates of the concentrations of several compounds for mass balance purposes. Criteria for the selection of waste containers at the INEL and the parameters that must be characterized prior to and during the tests are described. Collection of gaseous samples from 55-gallon drums of contact-handled transuranic waste for the gas generation testing is discussed. Analytical methods and calibrations are summarized. Administrative quality control measures described in this QAPjP include the generation, review, and approval of project documentation; control and retention of records; measures to ensure that personnel, subcontractors or vendors, and equipment meet the specifications necessary to achieve the required data quality for the project

Permanent burying method for product

International Nuclear Information System (INIS)

Sakai, Goro; Sakata, Noboru; Hironaka, Yoshikazu; Shigematsu, Kazuo; Yurugi, Masahiro; Minami, Masayoshi; Yoshisaki, Masato.

1995-01-01

In a method of permanently burying an object by filling and solidifying a cement mortar in gaps between each of objects to be buried underground, cement mortar is filled into gaps, which comprises water at a unit amount determined as from 200 to 250kg/m 3 , a cement at low water/cement ratio (%) of from 70 to 400%, and contains fine powder having an average grain size of not greater than 100μm (not containing cement) of 50 to 800kg/m 3 , fine aggregates of 800 to 1200kg/m 3 , UERAN gum (a bio-gum powder produced by aerobic fermentation of alcaligenes-bacteria) of 20g/m 3 to 1.3kg/m 3 , a dispersing agent of 0 to 40kg/m 3 , a swelling agent of 0 to 40kg/m 3 . Then if the mortar blended with the UERAN gum is injected, any gaps can be filled tightly, no breeding is caused and since the amount of cement is small, it does not suffer from temperature cracking. Therefore, the state of filling is kept permanently, and environmental pollution caused by radioactive wastes can be prevented. (N.H.)

Inspection device for buried equipment

International Nuclear Information System (INIS)

Hanawa, Jun.

1994-01-01

In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

Efficient calculation of broadband acoustic scattering from a partially, obliquely buried cylinder

NARCIS (Netherlands)

Nijhof, M.J.J.; Espana, A.; Williams, K.

2013-01-01

An efficient model for the Target In Environment Response (TIER) of buried/half buried, mine-like objects and UXOs is essential for the development and training of automatic target detection and classification methods and for use in sonar performance prediction models. For instance, to investigate

High-performance a-IGZO thin-film transistor with conductive indium-tin-oxide buried layer

Science.gov (United States)

Ahn, Min-Ju; Cho, Won-Ju

2017-10-01

In this study, we fabricated top-contact top-gate (TCTG) structure of amorphous indium-gallium-zinc oxide (a-IGZO) thin-film transistors (TFTs) with a thin buried conductive indium-tin oxide (ITO) layer. The electrical performance of a-IGZO TFTs was improved by inserting an ITO buried layer under the IGZO channel. Also, the effect of the buried layer's length on the electrical characteristics of a-IGZO TFTs was investigated. The electrical performance of the transistors improved with increasing the buried layer's length: a large on/off current ratio of 1.1×107, a high field-effect mobility of 35.6 cm2/Vs, a small subthreshold slope of 116.1 mV/dec, and a low interface trap density of 4.2×1011 cm-2eV-1 were obtained. The buried layer a-IGZO TFTs exhibited enhanced transistor performance and excellent stability against the gate bias stress.

Oxygen dynamics around buried lesser sandeels Ammodytes tobianus (Linnaeus 1785): mode of ventilation and oxygen requirements

DEFF Research Database (Denmark)

Behrens, Jane W; Stahl, Henrik J; Steffensen, John F

2007-01-01

The oxygen environment around buried sandeels (Ammodytes tobianus) was monitored by planar optodes. The oxygen penetration depth at the sediment interface was only a few mm. Thus fish, typically buried at 1-4 cm depth, were generally in anoxic sediment. However, they induced an advective transport...... down along the body, referred to as ;plume ventilation'. Yet, within approximately 30 min the oxic plume was replenished by oxygen-depleted water from the gills. The potential for cutaneous respiration by the buried fish was thus of no quantitative importance. Calculations derived by three independent...... methods (each with N=3) revealed that the oxygen uptake of sandeel buried for 6-7 h was 40-50% of previous estimates on resting respirometry of non-buried fish, indicating lower O(2) requirements during burial on a diurnal timescale. Buried fish exposed to decreasing oxygen tensions gradually approached...

Risk-based decision-making: A reality at the INEL

International Nuclear Information System (INIS)

Halford, V.E.; Nitschke, R.L.; Hula, G.A.

1994-01-01

Risk Analysis and Risk Management are major components of the Idaho National Engineering Laboratory's (INEL's) environmental restoration and waste management program. These tools help define responsible and cost-effective approaches to address potential human health and environmental risks from past operational practices. These techniques along with stake holder involvement, play a key role in the decision-making process which involves the US Department of Energy Idaho Operations Office (DOE), the US Environmental Protection Agency Region 10 (EPA), and the State of Idaho Department of Health and Welfare (IDHW), hereafter referred to as the agencies. An example of how this process works is Pad A, an above-ground mixed waste disposal site composed mainly of transuranic-contaminated evaporation pond salts. The site was constructed in 1972 for the disposal of solid radioactive wastes. A Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) baseline risk assessment was conducted to determine the incremental cancer risk and potential for adverse health effects to the public and the impacts to the environment if no action was performed. The risk characterization indicated that the carcinogenic risk for current and future hypothetical scenarios was below or within the NCP acceptable risk range. There was a potential 10 year window for an adverse health effect to an infant from nitrate contamination of the groundwater in about 250 years. Based on these results, a responsible and sound decision was reached to maintain and recontour the existing soil cover and to perform monitoring to confirm modeling assumptions

[Congenital buried penis in the child: about a case].

Science.gov (United States)

Rami, Mohamed; Bakkaly, Achraf El; Bouljrouf, Jaouad; Lafia, Toualouth; Bouhafs, Mohammed Amine; Belkacem, Rachid

2017-01-01

Congenital buried penis in the child is a congenital malformation where the penis appears small in size while all the parts of the organ are normal (the urethra, the erectile tissue and the glans penis). Our study aimed to describe our experience in the surgical treatment of this abnormality. We report the case of a 18-months old infant with bilateral hydrocele initially admitted to the Emergency Department and then referred to our Department. Clinical examination showed buried penis with tight foreskin and a dilation of the preputial reservoir due to urine. Surgical procedure included several steps: Z-shaped incision, pulling back of the foreskin of the penis, release of the adhesions surrounding the corpus cavernosum and ventral penile skin coverage using bladder catheter kept for a week to protect the wound healing. Aesthetic and functional result was satisfactory after 1-year follow-up. Congenital buried penis is a very debated subject in the literature. Our technique was simple and easily reproducible. Voiding difficulties and urinary infection are the main indications of this surgical procedure.

Quantification of Methamphetamine in Mouse Thighbones Buried in Soil.

Science.gov (United States)

Nakao, Ken-Ichiro; Tatara, Yuki; Kibayashi, Kazuhiko

2017-11-01

Bone samples are used for analysis of drugs in decomposed or skeletonized bodies. Toxicological analyses of buried bones are important for determining the causes and circumstances of death. In this study, methamphetamine and amphetamine concentrations in heart blood, thigh muscles, and thighbones were analyzed using solid-phase extraction with liquid chromatography-tandem mass spectrometry. Methamphetamine concentrations in heart blood, thigh muscle, and thighbone ranged from 0.041 to 0.873 μg/mL, 0.649 to 2.623 μg/g, and 56.543 to 643.371 μg/g, respectively. Thighbone concentrations were significantly higher than those in heart blood or thigh muscles were. Methamphetamine concentrations in buried thighbone (4.010-45.785 μg/g) were significantly lower than those of unburied thighbones were (56.543-643.371 μg/g). Methamphetamine and amphetamine were detected in thighbones buried for 7-180 days. These findings indicate that the methamphetamine concentrations in bone are higher and decrease after burial in soil. © 2017 American Academy of Forensic Sciences.

Image restoration techniques using Compton backscatter imaging for the detection of buried land mines

Science.gov (United States)

Wehlburg, Joseph C.; Keshavmurthy, Shyam P.; Watanabe, Yoichi; Dugan, Edward T.; Jacobs, Alan M.

1995-06-01

Earlier landmine imaging systems used two collimated detectors to image objects. These systems had difficulty in distinguishing between surface features and buried features. Using a combination of collimated and uncollimated detectors in a Compton backscatter imaging (CBI) system, allows the identification of surface and buried features. Images created from the collimated detectors contain information about the surface and the buried features, while the uncollimated detectors respond (approximately 80%) to features on the surface. The analysis of surface features are performed first, then these features can be removed and the buried features can be identified. Separation of the surface and buried features permits the use of a globbing algorithm to define regions of interest that can then be quantified [area, Y dimension, X dimension, and center location (xo, yo)]. Mine composition analysis is also possible because of the properties of the four detector system. Distinguishing between a pothole and a mine, that was previously very difficult, can now be easily accomplished.

Method of forming buried oxide layers in silicon

Science.gov (United States)

Sadana, Devendra Kumar; Holland, Orin Wayne

2000-01-01

A process for forming Silicon-On-Insulator is described incorporating the steps of ion implantation of oxygen into a silicon substrate at elevated temperature, ion implanting oxygen at a temperature below 200.degree. C. at a lower dose to form an amorphous silicon layer, and annealing steps to form a mixture of defective single crystal silicon and polycrystalline silicon or polycrystalline silicon alone and then silicon oxide from the amorphous silicon layer to form a continuous silicon oxide layer below the surface of the silicon substrate to provide an isolated superficial layer of silicon. The invention overcomes the problem of buried isolated islands of silicon oxide forming a discontinuous buried oxide layer.

Radiotoxic hazard measure for buried solid radioactive waste

International Nuclear Information System (INIS)

Hamstra, J.

1975-01-01

The radiotoxic hazards resulting from the disposal of highlevel reprocessing wastes into a deep geological formation are reviewed. The term radiotoxic hazard measure (RHM), used to measure the hazard from buried radioactive wastes, is based on the maximum radionuclide concentration permissible in water. Calculations are made of the RHM levels for the high-level reprocessing wastes of both light-water-reactor and fast breeder reactor fuels. In comparing these RHM levels with that for the natural activity of an equivalent amount of uranium ore and its mill tailings, it is concluded that an actual additional radiotoxic hazard for buried high-level reprocessing waste only exists for the first 300 to 500 years after burial. (U.S.)

Distribution of ancient carbon in buried soils in an eroding loess landscape

Science.gov (United States)

Szymanski, L. M.; Mason, J. A.; De Graaff, M. A.; Berhe, A. A.; Marin-Spiotta, E.

2017-12-01

Understanding the processes that contribute to the accumulation and loss of carbon in soils and the implications for land management is vital for mitigating climate change. Buried soils or paleosols that represent former surface horizons can store more organic carbon than mineral horizons at equivalent depths due to burial restricting microbial decomposition. The presence of buried soils defies modeled expectations of exponential declines in carbon concentrations with depth, especially in locations where successive depositional events lead to multiple buried soil layers. Buried soils are found in a diversity of depositional environments across latitudes and without accounting for their presence can lead to underestimates of regional carbon reservoirs. Here we present data on the spatial distribution of carbon in a paleosol loess sequence in Nebraska, focusing on one prominent paleosol, the Brady soil. The Brady soil has been identified throughout the Central Great Plains and began developing at the end of the Pleistocene and was subsequently buried by loess in the early Holocene (Mason et al. 2003). Preliminary analyses of the Brady soil at its deepest, 6-m below the surface, reveal large differences in the composition and degree of decomposition of organic matter from the modern soil. We sampled along burial and erosional transects to characterize spatial variability in the depth of Brady soil from the modern landscape surface and to determine how these differences may alter the amount and composition of organic carbon. A more accurate determination of the spatial extent and heterogeneity of buried soil carbon will improve regional estimates of carbon reservoirs. This assessment of its variability across the landscape will inform future planned work on the vulnerability of ancient carbon to disturbance.

A Novel Method for Remote Depth Estimation of Buried Radioactive Contamination.

Science.gov (United States)

Ukaegbu, Ikechukwu Kevin; Gamage, Kelum A A

2018-02-08

Existing remote radioactive contamination depth estimation methods for buried radioactive wastes are either limited to less than 2 cm or are based on empirical models that require foreknowledge of the maximum penetrable depth of the contamination. These severely limits their usefulness in some real life subsurface contamination scenarios. Therefore, this work presents a novel remote depth estimation method that is based on an approximate three-dimensional linear attenuation model that exploits the benefits of using multiple measurements obtained from the surface of the material in which the contamination is buried using a radiation detector. Simulation results showed that the proposed method is able to detect the depth of caesium-137 and cobalt-60 contamination buried up to 40 cm in both sand and concrete. Furthermore, results from experiments show that the method is able to detect the depth of caesium-137 contamination buried up to 12 cm in sand. The lower maximum depth recorded in the experiment is due to limitations in the detector and the low activity of the caesium-137 source used. Nevertheless, both results demonstrate the superior capability of the proposed method compared to existing methods.

Preliminary Systems Design Study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Quapp, W.J.; Feizollahi, F.; Del Signore, J.C.

1991-07-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept. The SDS results are published in eight volumes. Volume 1 contains an executive summary. The SDS summary and analysis of results are presented in Volume 2. Volumes 3 through 7 contain detailed descriptions of twelve system and four subsystem concepts. Volume 8 contains the appendixes. 23 refs., 23 figs., 16 tabs

Seismic induced earth pressures in buried vaults

International Nuclear Information System (INIS)

Miller, C.A.; Costantino, C.J.

1994-01-01

The magnitude and distribution of earth pressures acting on buried structures and induced by a seismic event are considered in this paper. A soil-structure-interaction analysis is performed for typical Department of Energy high level waste storage tanks using a lumped parameter model. The resulting soil pressure distributions are determined and compared with the static soil pressure to assess the design significance of the seismic induced soil pressures. It is found that seismic pressures do not control design unless the peak ground acceleration exceeds about 0.3 G. The effect of soil non linearities (resulting from local soil failure) are also found to have little effect on the predictions of the seismic response of the buried structure. The seismic induced pressures are found to be very similar to those predicted using the elastic model in ASCE 4-86

7 CFR 1755.505 - Buried services.

Science.gov (United States)

2010-01-01

... using the recommendations in RUS Bulletin 1751F-640, “Design of Buried Plant—Physical Considerations... water, oil, sewer) and structures 4 2 [50.8] Wires or cables of another communications system 2 [50.8] 1... wire or cable size and type of surface shall be in accordance with the manufacturer's recommendation...

Mutation choice to eliminate buried free cysteines in protein therapeutics.

Science.gov (United States)

Xia, Xue; Longo, Liam M; Blaber, Michael

2015-02-01

Buried free-cysteine (Cys) residues can contribute to an irreversible unfolding pathway that promotes protein aggregation, increases immunogenic potential, and significantly reduces protein functional half-life. Consequently, mutation of buried free-Cys residues can result in significant improvement in the storage, reconstitution, and pharmacokinetic properties of protein-based therapeutics. Mutational design to eliminate buried free-Cys residues typically follows one of two common heuristics: either substitution by Ser (polar and isosteric), or substitution by Ala or Val (hydrophobic); however, a detailed structural and thermodynamic understanding of Cys mutations is lacking. We report a comprehensive structure and stability study of Ala, Ser, Thr, and Val mutations at each of the three buried free-Cys positions (Cys16, Cys83, and Cys117) in fibroblast growth factor-1. Mutation was almost universally destabilizing, indicating a general optimization for the wild-type Cys, including van der Waals and H-bond interactions. Structural response to Cys mutation characteristically involved changes to maintain, or effectively substitute, local H-bond interactions-by either structural collapse to accommodate the smaller oxygen radius of Ser/Thr, or conversely, expansion to enable inclusion of novel H-bonding solvent. Despite the diverse structural effects, the least destabilizing average substitution at each position was Ala, and not isosteric Ser. © 2014 Wiley Periodicals, Inc. and the American Pharmacists Association.

Protection of Buried Pipe under Repeated Loading by Geocell Reinforcement

Science.gov (United States)

Khalaj, Omid; Joz Darabi, N.; Moghaddas Tafreshi, S. N.; Mašek, Bohuslav

2017-12-01

With increase in cities’ population and development of urbane life, passing buried pipelines near ground’s surface is inevitable in urban areas, roads, subways and highways. This paper presents the results of three-dimensional full scale model tests on high-density polyethylene (HDPE) pipe with diameter of 250 mm in geocell reinforced soil, subjected to repeated loading to simulate the vehicle loads. The effect of geocell’s pocket size (55*55 mm and 110*110 mm) and embedment depth of buried pipe (1.5 and 2 times pipe diameter) in improving the behaviour of buried pipes was investigated. The geocell’s height of 100 mm was used in all tests. The repeated load of 800 kPa was applied on circular loading plate with diameter of 250 mm. The results show that the pipe displacement, soil surface settlement and transferred pressure on the pipe’s crown has been influenced significantly upon the use of geocells. For example, the vertical diametric strain (VDS) and soil surface settlement (SSS), in a way that using a geocell with pocket size of 110*110 mm reduces by 27% and 43%, respectively, compared with the unreinforced one. Meanwhile, by increasing buried depth of pipe from 1.5D to 2D, the use of geocell of 110*110 mm delivers about 50% reduction in SSS and VDS, compared with the unreinforced soil.

Thin films and buried interfaces characterization with X-ray standing waves

Energy Technology Data Exchange (ETDEWEB)

Lagomarsino, S [CNR, Rome (Italy). Istituto Elettronica Stato Solido

1996-09-01

The X-ray standing wave techniques is a powerful, non destructive method to study interfaces at the atomic level. Its basic features are described here together with the peculiarities of its applications to epitaxial films and buried interfaces. As examples of applications, experiments carried out on Si/silicide interfaces, on GaAs/InAs/GaAs buried interfaces and on Si/Ge superlattices are shown.

Buried and Surface Polymetallic Nodule Distribution in the Eastern CLARION-CLIPPERTON Zone: Main Distinctions and Similarities

Science.gov (United States)

Kotlinski, R.; Stoyanova, V.

The distribution pattern, abundance variations, morphology, chemical and mineralogical composition of buried polymetallic nodules in the eastern Clarion-Clipperton Zone (CCZ) are presented. Our observations are based on data collected from 59 boxcore stations, which comprise about 22.6% of all sampled stations in the Interoceanmetal exploration area site B2 in the eastern CCZ, with recorded buried and surface polymetallic nodules. The majority of stations with buried nodules (>90%) is below 4300 m water depth and is associated mainly with seafloor hills and slopes of ridges and depressions. Buried nodules lie completely beneath the active sediment-water boundary layer (with thickness range from 0 to 15 cm), and they are vertically recorded down to the 45 cm in sediment cores. Abundance of buried nodules varies from 0.2 to 22.1 kg/m2, averaging 3.2 kg/m2. By comparison, surface nodules are more abundant, varying from 0 to 20.2 kg/m2, averaging 10.3 kg/m2. As a general rule the size of buried nodules is larger than surface nodules, and >27% of recovered buried nodules exceed 10 cm in diameter. It is assumed that more than 90% of analyzed buried nodules have a diagenetic origin; however, the identification of factors and conditions responsible for their formation still remains unknown.

Development of New Technology for Leak Detection of a Buried Pipe

Energy Technology Data Exchange (ETDEWEB)

Yoon, D. B.; Park, J. H.; Moon, S. S.; Han, S. W.; Kang, T.; Kim, H. J.

2014-01-15

The importance of the leak detection of a buried pipe in a power plant of Korea is being emphasized as the buried pipes of a power plant are more than 20 years old. The first objective of this work is to develop new technologies for leak detection of a buried pipe. The second objective is to design and fabricate a trial product of leakage detection system for buried pipe. To achieve these purposes, as a first step, literature survey of the leak detection methods and techniques has been performed. As an algorithm for enhancing the leak detection capability of newly developed leakage detection system, an algorithm for removing mechanical noise and reflected wave within the pipe has been developed, and its feasibility was verified by performing numerical simulations and experiments. The hardware for leakage detection system is designed as a portable type by considering the test environment of a power plant, where speedy leakage inspection and rapid movement/reinstallation of the inspection equipment is necessary. The software is designed to provide a user-friendly GUI(Graphic User Interface) environment, making the system setup and data display quick and easy. It is also designed to allow for a real time visualization of analysis results on a monitoring screen for an estimation of the leakage location. The feature of the developed leak detection system is that it equipped with noise rejection algorithms that can effectively enhance the leak detection capability in a noisy environment. Then, a trial product of the leakage detection system has been fabricated, and its functionality and capability were verified by field experiments. The experimental results demonstrated that even in a noisy environment, the developed system can provide more reliable means for estimating the leak location of the buried pipe. It is expected that the reliability of leakage point estimation can be enhanced when the developed leak detection system is applied to a leakage estimation problem

Development of New Technology for Leak Detection of a Buried Pipe

International Nuclear Information System (INIS)

Yoon, D. B.; Park, J. H.; Moon, S. S.; Han, S. W.; Kang, T.; Kim, H. J.

2014-01-01

The importance of the leak detection of a buried pipe in a power plant of Korea is being emphasized as the buried pipes of a power plant are more than 20 years old. The first objective of this work is to develop new technologies for leak detection of a buried pipe. The second objective is to design and fabricate a trial product of leakage detection system for buried pipe. To achieve these purposes, as a first step, literature survey of the leak detection methods and techniques has been performed. As an algorithm for enhancing the leak detection capability of newly developed leakage detection system, an algorithm for removing mechanical noise and reflected wave within the pipe has been developed, and its feasibility was verified by performing numerical simulations and experiments. The hardware for leakage detection system is designed as a portable type by considering the test environment of a power plant, where speedy leakage inspection and rapid movement/reinstallation of the inspection equipment is necessary. The software is designed to provide a user-friendly GUI(Graphic User Interface) environment, making the system setup and data display quick and easy. It is also designed to allow for a real time visualization of analysis results on a monitoring screen for an estimation of the leakage location. The feature of the developed leak detection system is that it equipped with noise rejection algorithms that can effectively enhance the leak detection capability in a noisy environment. Then, a trial product of the leakage detection system has been fabricated, and its functionality and capability were verified by field experiments. The experimental results demonstrated that even in a noisy environment, the developed system can provide more reliable means for estimating the leak location of the buried pipe. It is expected that the reliability of leakage point estimation can be enhanced when the developed leak detection system is applied to a leakage estimation problem

Partitioning of a scaled shallow-buried near-field blast load

CSIR Research Space (South Africa)

Reinecke, J David

2015-07-01

Full Text Available and target force response to a shallow and deep buried blast loads and the initial loading phase contribution to the blast load were quantified. There is no separate precursor air shock for shallow buried blast load and the initial loading phase impulse... stream_source_info Reinecke_2015.pdf.txt stream_content_type text/plain stream_size 24459 Content-Encoding UTF-8 stream_name Reinecke_2015.pdf.txt Content-Type text/plain; charset=UTF-8 Partitioning of a Scaled Shallow...

Buried Man-made Structure Imaging using 2-D Resistivity Inversion

Science.gov (United States)

Anderson Bery, Andy; Nordiana, M. M.; El Hidayah Ismail, Noer; Jinmin, M.; Nur Amalina, M. K. A.

2018-04-01

This study is carried out with the objective to determine the suitable resistivity inversion method for buried man-made structure (bunker). This study was carried out with two stages. The first stage is suitable array determination using 2-D computerized modeling method. One suitable array is used for the infield resistivity survey to determine the dimension and location of the target. The 2-D resistivity inversion results showed that robust inversion method is suitable to resolve the top and bottom part of the buried bunker as target. In addition, the dimension of the buried bunker is successfully determined with height of 7 m and length of 20 m. The location of this target is located at -10 m until 10 m of the infield resistivity survey line. The 2-D resistivity inversion results obtained in this study showed that the parameters selection is important in order to give the optimum results. These parameters are array type, survey geometry and inversion method used in data processing.

Post-liquefaction soil-structure interaction for buried structures: Sensitivity analysis studies

International Nuclear Information System (INIS)

Pires, J.A.; Ang, H.S.; Katayama, I.; Satoh, M.

1993-01-01

The post liquefaction behavior of buried conduits is analyzed and sensitivity analysis is conducted to investigate the damage potential of the forces induced in the buried lifelines following seismically induced liquefaction of the surrounding soil. Various lifeline configurations and loading conditions are considered. The loading conditions considered are: buoyancy forces and permanent ground displacements parallel to the lifeline axis. Pertinent parameters for the soil-lifeline interaction following liquefaction are identified. (author)

Laboratory scale vitrification of low-level radioactive nitrate salts and soils from the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Shaw, P.; Anderson, B.

1993-07-01

INEL has radiologically contaminated nitrate salt and soil waste stored above and below ground in Pad A and the Acid Pit at the Radioactive Waste Management Complex. Pad A contain uranium and transuranic contaminated potassium and sodium nitrate salts generated from dewatered waste solutions at the Rocky Flats Plant. The Acid Pit was used to dispose of liquids containing waste mineral acids, uranium, nitrate, chlorinated solvents, and some mercury. Ex situ vitrification is a high temperature destruction of nitrates and organics and immobilizes hazardous and radioactive metals. Laboratory scale melting of actual radionuclides containing INEL Pad A nitrate salts and Acid Pit soils was performed. The salt/soil/additive ratios were varied to determine the range of glass compositions (resulted from melting different wastes); maximize mass and volume reduction, durability, and immobilization of hazardous and radioactive metals; and minimize viscosity and offgas generation for wastes prevalent at INEL and other DOE sites. Some mixtures were spiked with additional hazardous and radioactive metals. Representative glasses were leach tested and showed none. Samples spiked with transuranic showed low nuclide leaching. Wasteforms were two to three times bulk densities of the salt and soil. Thermally co-processing soils and salts is an effective remediation method for destroying nitrate salts while stabilizing the radiological and hazardous metals they contain. The measured durability of these low-level waste glasses approached those of high-level waste glasses. Lab scale vitrification of actual INEL contaminated salts and soils was performed at General Atomics Laboratory as part of the INEL Waste Technology Development and Environmental Restoration within the Buried Waste Integrated Demonstration Program

Modelling the buried human body environment in upland climes using three contrasting field sites.

Science.gov (United States)

Wilson, Andrew S; Janaway, Robert C; Holland, Andrew D; Dodson, Hilary I; Baran, Eve; Pollard, A Mark; Tobin, Desmond J

2007-06-14

Despite an increasing literature on the decomposition of human remains, whether buried or exposed, it is important to recognise the role of specific microenvironments which can either trigger or delay the rate of decomposition. Recent casework in Northern England involving buried and partially buried human remains has demonstrated a need for a more detailed understanding of the effect of contrasting site conditions on cadaver decomposition and on the microenvironment created within the grave itself. Pigs (Sus scrofa) were used as body analogues in three inter-related taphonomy experiments to examine differential decomposition of buried human remains. They were buried at three contrasting field sites (pasture, moorland, and deciduous woodland) within a 15 km radius of the University of Bradford, West Yorkshire, UK. Changes to the buried body and the effect of these changes on hair and associated death-scene textile materials were monitored as was the microenvironment of the grave. At recovery, 6, 12 and 24 months post-burial, the extent of soft tissue decomposition was recorded and samples of fat and soil were collected for gas chromatography mass spectrometry (GCMS) analysis. The results of these studies demonstrated that (1) soil conditions at these three burial sites has a marked effect on the condition of the buried body but even within a single site variation can occur; (2) the process of soft tissue decomposition modifies the localised burial microenvironment in terms of microbiological load, pH, moisture and changes in redox status. These observations have widespread application for the investigation of clandestine burial and time since deposition, and in understanding changes within the burial microenvironment that may impact on biomaterials such as hair and other associated death scene materials.

Analyses of SRS waste glass buried in granite in Sweden and salt in the United States

International Nuclear Information System (INIS)

Williams, J.P.; Wicks, G.G.; Clark, D.E.; Lodding, A.R.

1991-01-01

Simulated Savannah River Site (SRS) waste glass forms have been buried in the granite geology of the Stirpa mine in Sweden for two years. Analyses of glass surfaces provided a measure of the performance of the waste glasses as a function of time. Similar SRS waste glass compositions have also been buried in salt at the WIPP facility in Carlsbad, New Mexico for a similar time period. Analyses of the SRS waste glasses buried in-situ in granite will be presented and compared to the performance of these same compositions buried in salt at WIPP

Idaho National Engineering Laboratory High-Level Waste Roadmap

International Nuclear Information System (INIS)

1993-08-01

The Idaho National Engineering Laboratory (INEL) High-Level Waste (HLW) Roadmap takes a strategic look at the entire HLW life-cycle starting with generation, through interim storage, treatment and processing, transportation, and on to final disposal. The roadmap is an issue-based planning approach that compares ''where we are now'' to ''where we want and need to be.'' The INEL has been effectively managing HLW for the last 30 years. Calcining operations are continuing to turn liquid HLW into a more manageable form. Although this document recognizes problems concerning HLW at the INEL, there is no imminent risk to the public or environment. By analyzing the INEL current business operations, pertinent laws and regulations, and committed milestones, the INEL HLW Roadmap has identified eight key issues existing at the INEL that must be resolved in order to reach long-term objectives. These issues are as follows: A. The US Department of Energy (DOE) needs a consistent policy for HLW generation, handling, treatment, storage, and disposal. B. The capability for final disposal of HLW does not exist. C. Adequate processes have not been developed or implemented for immobilization and disposal of INEL HLW. D. HLW storage at the INEL is not adequate in terms of capacity and regulatory requirements. E. Waste streams are generated with limited consideration for waste minimization. F. HLW is not adequately characterized for disposal nor, in some cases, for storage. G. Research and development of all process options for INEL HLW treatment and disposal are not being adequately pursued due to resource limitations. H. HLW transportation methods are not selected or implemented. A root-cause analysis uncovered the underlying causes of each of these issues

Idaho National Engineering Laboratory High-Level Waste Roadmap. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Idaho National Engineering Laboratory (INEL) High-Level Waste (HLW) Roadmap takes a strategic look at the entire HLW life-cycle starting with generation, through interim storage, treatment and processing, transportation, and on to final disposal. The roadmap is an issue-based planning approach that compares ``where we are now`` to ``where we want and need to be.`` The INEL has been effectively managing HLW for the last 30 years. Calcining operations are continuing to turn liquid HLW into a more manageable form. Although this document recognizes problems concerning HLW at the INEL, there is no imminent risk to the public or environment. By analyzing the INEL current business operations, pertinent laws and regulations, and committed milestones, the INEL HLW Roadmap has identified eight key issues existing at the INEL that must be resolved in order to reach long-term objectives. These issues are as follows: A. The US Department of Energy (DOE) needs a consistent policy for HLW generation, handling, treatment, storage, and disposal. B. The capability for final disposal of HLW does not exist. C. Adequate processes have not been developed or implemented for immobilization and disposal of INEL HLW. D. HLW storage at the INEL is not adequate in terms of capacity and regulatory requirements. E. Waste streams are generated with limited consideration for waste minimization. F. HLW is not adequately characterized for disposal nor, in some cases, for storage. G. Research and development of all process options for INEL HLW treatment and disposal are not being adequately pursued due to resource limitations. H. HLW transportation methods are not selected or implemented. A root-cause analysis uncovered the underlying causes of each of these issues.

Mechanical Energy Propagation and Backscattering in Nominally Dry Soil: Imaging Buried Land Mines

Science.gov (United States)

Sen, Surajit

2003-04-01

The imaging of shallow buried objects in a complex medium, e.g., nominally dry sand, is an outstanding challenge. Such imaging is of relevance in connection with the detection and subsequent imaging of buried non-metallic anti-personnel land mines and in other applications. It has been shown that gentle mechanical impulses and low frequency sound waves with frequencies roughly between 150-350 Hz or so can penetrate distances of up to a foot in sand. Hence, such signals can potentially be useful in the detection and perhaps in the imaging of shallow buried objects. It is presently unclear whether high frequency signals can be effectively used to image shallow buried objects. Impulses can typically penetrate larger distances into sand and soil. Both impulses and continuous sound waves can be used for imaging shallow buried objects. The talk shall briefly review the state-of-the-art in low frequency sound propagation in soil and shall discuss the current understanding of impulse propagation and backscattering in nominally dry sand beds. It will be argued that impulse based imaging may have the potential to be a simple and fast way to detect and image small non-metallic mines. Research supported by the National Science Foundation Grant No. NSF-CMS 0070055.

Detection of Buried Mines and Unexploded Ordnance (UXO)

National Research Council Canada - National Science Library

Heberlein, David; Balko, Bohdan; Chappell, Isaac; Biddle, John

2007-01-01

... [and/or their explosive-related compounds (ERCs)] concentrated in the top soil, and radiation techniques, which uses radiation to probe beneath the earth's surface to provide bulk detection of buried explosive devices...

Classification System for Individualized Treatment of Adult Buried Penis Syndrome.

Science.gov (United States)

Tausch, Timothy J; Tachibana, Isamu; Siegel, Jordan A; Hoxworth, Ronald; Scott, Jeremy M; Morey, Allen F

2016-09-01

The authors present their experience with reconstructive strategies for men with various manifestations of adult buried penis syndrome, and propose a comprehensive anatomical classification system and treatment algorithm based on pathologic changes in the penile skin and involvement of neighboring abdominal and/or scrotal components. The authors reviewed all patients who underwent reconstruction of adult buried penis syndrome at their referral center between 2007 and 2015. Patients were stratified by location and severity of involved anatomical components. Procedures performed, demographics, comorbidities, and clinical outcomes were reviewed. Fifty-six patients underwent reconstruction of buried penis at the authors' center from 2007 to 2015. All procedures began with a ventral penile release. If the uncovered penile skin was determined to be viable, a phalloplasty was performed by anchoring penoscrotal skin to the proximal shaft, and the ventral shaft skin defect was closed with scrotal flaps. In more complex patients with circumferential nonviable penile skin, the penile skin was completely excised and replaced with a split-thickness skin graft. Complex patients with severe abdominal lipodystrophy required adjacent tissue transfer. For cases of genital lymphedema, the procedure involved complete excision of the lymphedematous tissue, and primary closure with or without a split-thickness skin graft, also often involving the scrotum. The authors' overall success rate was 88 percent (49 of 56), defined as resolution of symptoms without the need for additional procedures. Successful correction of adult buried penis often necessitates an interdisciplinary, multimodal approach. Therapeutic, IV.

Buried waste integrated demonstration fiscal year 1992 close-out report

International Nuclear Information System (INIS)

Cannon, P.G.; Kostelnik, K.M.; Owens, K.J.

1993-02-01

The mission of the Buried Waste Integrated Demonstration Program (BWID) is to support the development and demonstration of a suite of technologies that when integrated with commercially-available baseline technologies form a comprehensive remediation system for the effective and efficient remediation of buried waste disposed of throughout the US Department of Energy complex. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Office of Technology Development initiated the BWID at the Idaho National Engineering Laboratory in fiscal year (FY)-91. This report summarizes the activities of the BWID Program during FY-92

Note: Laser ablation technique for electrically contacting a buried implant layer in single crystal diamond

International Nuclear Information System (INIS)

Ray, M. P.; Baldwin, J. W.; Butler, J. E.; Pate, B. B.; Feygelson, T. I.

2011-01-01

The creation of thin, buried, and electrically conducting layers within an otherwise insulating diamond by annealed ion implantation damage is well known. Establishing facile electrical contact to the shallow buried layer has been an unmet challenge. We demonstrate a new method, based on laser micro-machining (laser ablation), to make reliable electrical contact to a buried implant layer in diamond. Comparison is made to focused ion beam milling.

Imaging of Au nanoparticles deeply buried in polymer matrix by various atomic force microscopy techniques

International Nuclear Information System (INIS)

Kimura, Kuniko; Kobayashi, Kei; Matsushige, Kazumi; Yamada, Hirofumi

2013-01-01

Recently, some papers reported successful imaging of subsurface features using atomic force microscopy (AFM). Some theoretical studies have also been presented, however the imaging mechanisms are not fully understood yet. In the preceeding papers, imaging of deeply buried nanometer-scale features has been successful only if they were buried in a soft matrix. In this paper, subsurface features (Au nanoparticles) buried in a soft polymer matrix were visualized. To elucidate the imaging mechanisms, various AFM techniques; heterodyne force microscopy, ultrasonic atomic force microscopy (UAFM), 2nd-harmonic UAFM and force modulation microscopy (FMM) were employed. The particles buried under 960 nm from the surface were successfully visualized which has never been achieved. The results elucidated that it is important for subsurface imaging to choose a cantilever with a suitable stiffness range for a matrix. In case of using the most suitable cantilever, the nanoparticles were visualized using every technique shown above except for FMM. The experimental results suggest that the subsurface features buried in a soft matrix with a depth of at least 1 µm can affect the local viscoelasticity (mainly viscosity) detected as the variation of the amplitude and phase of the tip oscillation on the surface. This phenomenon presumably makes it possible to visualize such deeply buried nanometer-scale features in a soft matrix. - Highlights: • We visualized subsurface features buried in soft matrix, and investigated its imaging mechanism. • AFM techniques; UAFM, FMM, HFM and 2nd-harmonic UAFM were applied to elucidate the mechanism. • Au nanoparticles buried under 960 nm from surface were visualized, which has never been achieved. • Imaging at contact resonance using a cantilever of suitable stiffness is important. • Subsurface features in a soft matrix affect surface viscoelasticity, which are detected by AFM

Management of national nuclear power programs for assured safety. Report of visit by international participants to INEL on August 24, 1985

International Nuclear Information System (INIS)

Rouhani, S.Z.

1985-10-01

Through a special arrangement with the US State Department and support from the Department of Energy a group of high ranking officials from six different countries visited the Idaho National Engineering Laboratory on August 24, 1985. They were briefed on the highlights of the US-NRC's nuclear safety research programs at the INEL. The purpose of this project was to broadcast the advancements of the US nuclear safety technology to other nations that are at the start of major programs for peaceful use of nuclear energy in their countries

Detection of Buried Objects : The MUD Project

NARCIS (Netherlands)

Quesson, B.A.J.; Vossen, R. van; Zampolli, M.; Beckers, A.L.D.

2011-01-01

The aim of the Mine Underwater Detection (MUD) project at TNO is to experimentally investigate the acoustic and magnetic detection of explosives underwater, buried in a soft sediment layer. This problem is relevant for the protection of harbors and littoral assets against terrorist attacks and for

Micromachining of buried micro channels in silicon

NARCIS (Netherlands)

de Boer, Meint J.; Tjerkstra, R.W.; Berenschot, Johan W.; Jansen, Henricus V.; Burger, G.J.; Burger, G.J.; Gardeniers, Johannes G.E.; Elwenspoek, Michael Curt; van den Berg, Albert

A new method for the fabrication of micro structures for fluidic applications, such as channels, cavities, and connector holes in the bulk of silicon wafers, called buried channel technology (BCT), is presented in this paper. The micro structures are constructed by trench etching, coating of the

Contribution of buried aspartic acid to the stability of the PDZ2 protein

International Nuclear Information System (INIS)

Jayasimha, Pruthvi; Shanmuganathan, Aranganathan; Suladze, Saba; Makhatadze, George I.

2012-01-01

Highlights: ► Buried Asp residues on average form 2.5 to 3 hydrogen bonds and/or 0.8 salt bridges. ► Contribution of buried Asp to stability was estimated using model protein PDZ2. ► The energetic contribution of Asp56 to PDZ2 stability estimated to be 18 kJ · mol −1 . ► Findings are discussed in terms of contribution of Asp residues to protein stability. - Abstract: Statistical analysis of protein structures shows that buried aspartic acid residues on average form 2.5 to 3 hydrogen bonds and/or 0.8 potential ionic interactions with other protein groups. To estimate the energetic contribution of such buried groups to the Gibbs free energy of proteins, we measured the effects of amino acid substitutions of D56 in a model protein PDZ2 on its stability. We used temperature-induced unfolding monitored by DSC and denaturant-induced unfolding monitored by the changes in fluorescence intensity. We find that all substitutions of D56 lead to protein unfolding, thus suggesting that this buried hydrogen bonded aspartic acid has a significant contribution to the stability. To quantify the changes in the Gibbs free energy, one of the variants, D56N was stabilized by addition of the protective osmolyte TMAO. Comparison of the stability of the D56N variant with the wild-type PDZ2 in the presence and absence of TMAO allowed us to estimate the contribution of D56 to the protein stability to be 18 kJ · mol −1 . These findings are discussed in terms of contribution of buried ionizable groups to protein stability.

LMFBR safety: Interim test report for the characterization of released particle tests conducted at INEL during FY 1979

International Nuclear Information System (INIS)

Johnson, R.P.; Nelson, C.T.

1979-01-01

Two additional atmospheric sodium release tests were jointly conducted by ESG and ARL at INEL. These tests were conducted under very stable (Pasquill E and G) meteorological conditions where the natural humidity content was high (47 and 96% RH). Sufficient experimental data was obtained on Test 7 to quantitatively qualify the formation of Na 2 CO 3 in the open atmosphere from primary sodium combustion products. These data show that a maximum concentration of approx. 60% Na 2 CO 3 is reached with the plume 100 meters from the release point. This concentration increases slightly as the plume is dispersed beyond 2400 meters. The available particle fallout data is consistent with predictions

Computer simulation of explosion crater in dams with different buried depths of explosive

Science.gov (United States)

Zhang, Zhichao; Ye, Longzhen

2018-04-01

Based on multi-material ALE method, this paper conducted a computer simulation on the explosion crater in dams with different buried depths of explosive using LS-DYNA program. The results turn out that the crater size increases with the increase of buried depth of explosive at first, but closed explosion cavity rather than a visible crater is formed when the buried depth of explosive increases to some extent. The soil in the explosion cavity is taken away by the explosion products and the soil under the explosion cavity is compressed with its density increased. The research can provide some reference for the anti-explosion design of dams in the future.

Study on dinamic behavior and least burying depth of underground protective pipe

Energy Technology Data Exchange (ETDEWEB)

Kataoka, Tetsuyuki; Kokusyo, Goji; Tanaka, Yukihisa; Kobayashi, Seiichi

1988-03-30

Effect of unit load per travel wheel on the protective pipe was studied when electricity cable distribution lines were buried in the depth less than the present standard for electric equipment, and logical burying depth was investigated. Test items were material test of the protective pipe, indoor load test, and field test at loamy ground. Impact resistance hard PVC pipe was used as the protective pipe, and its strength and elastic modulus were measured. Along with these tests, it was confirmed that there was no problem of cracking by repeated flattening or breakage by fatigue. By indoor test, it was observed that, in case of shallow burying, creap deformation was small, stress concentrate occured at the middle of axial direction, and that flattening ratio was seriously affected by the method of backfilling. Field test was conducted by applying the static load of a 20 ton dump truck, and the deformation, stress, and subsidence of the protective pipe, were measured. As the conclusion of those experiments, it was found that burying of protective pipe in the depth of not less than 30 cm is allowable, as long as sufficient bakfilling is made. (14 figs, 3 tabs, 3 refs)

Direct Measurement of the Band Structure of a Buried Two-Dimensional Electron Gas

DEFF Research Database (Denmark)

Miwa, Jill; Hofmann, Philip; Simmons, Michelle Y.

2013-01-01

We directly measure the band structure of a buried two dimensional electron gas (2DEG) using angle resolved photoemission spectroscopy. The buried 2DEG forms 2 nm beneath the surface of p-type silicon, because of a dense delta-type layer of phosphorus n-type dopants which have been placed there...

Lab-scale tests on ISV vapor transport phenomena

International Nuclear Information System (INIS)

Farnsworth, R.K.; Gardner, B.M.

1996-01-01

In situ vitrification (ISV) is a promising technology for remediating buried waste sites and contaminated soil sites. However, concerns exist that low soil permeabilities may limit vapor transport away from the advancing melt front and cause a melt expulsion that breaches ISV containment. As a result, two ISV lab tests were conducted at the Idaho National Engineering Laboratory (INEL) using INEL soil (permeability: 10 -6 cm/s) and a low permeability (10 -10 cm/s) clay material. The clay test also had a ceramic tube inserted vertically through the center of the area being melted to provide one-dimensional data on vapor transport. Results confirm that low soil permeabilities can limit vapor transport away from the advancing ISV melt front. In addition, peak pressures inside the ceramic tube were significantly greater than those outside the tube, indicating the importance of horizontal vapor transport around the advancing ISV melt front

Buried Porous Silicon-Germanium Layers in Monocrystalline Silicon Lattices

Science.gov (United States)

Fathauer, Robert W. (Inventor); George, Thomas (Inventor); Jones, Eric W. (Inventor)

1998-01-01

Monocrystalline semiconductor lattices with a buried porous semiconductor layer having different chemical composition is discussed and monocrystalline semiconductor superlattices with a buried porous semiconductor layers having different chemical composition than that of its monocrystalline semiconductor superlattice are discussed. Lattices of alternating layers of monocrystalline silicon and porous silicon-germanium have been produced. These single crystal lattices have been fabricated by epitaxial growth of Si and Si-Ge layers followed by patterning into mesa structures. The mesa structures are strain etched resulting in porosification of the Si-Ge layers with a minor amount of porosification of the monocrystalline Si layers. Thicker Si-Ge layers produced in a similar manner emitted visible light at room temperature.

Investigation of guided waves propagation in pipe buried in sand

International Nuclear Information System (INIS)

Leinov, Eli; Cawley, Peter; Lowe, Michael J.S.

2014-01-01

The inspection of pipelines by guided wave testing is a well-established method for the detection of corrosion defects in pipelines, and is currently used routinely in a variety of industries, e.g. petrochemical and energy. When the method is applied to pipes buried in soil, test ranges tend to be significantly compromised because of attenuation of the waves caused by energy radiating into the soil. Moreover, the variability of soil conditions dictates different attenuation characteristics, which in-turn results in different, unpredictable, test ranges. We investigate experimentally the propagation and attenuation characteristics of guided waves in pipes buried in fine sand using a well characterized full scale experimental apparatus. The apparatus consists of an 8 inch-diameter, 5.6-meters long steel pipe embedded over 3 meters of its length in a rectangular container filled with fine sand, and an air-bladder for the application of overburden pressure. Longitudinal and torsional guided waves are excited in the pipe and recorded using a transducer ring (Guided Ultrasonics Ltd). Acoustic properties of the sand are measured independently in-situ and used to make model predictions of wave behavior in the buried pipe. We present the methodology and the systematic measurements of the guided waves under a range of conditions, including loose and compacted sand. It is found that the application of overburden pressure modifies the compaction of the sand and increases the attenuation, and that the measurement of the acoustic properties of sand allows model prediction of the attenuation of guided waves in buried pipes with a high level of confidence

BATATA: a buried muon hodoscope

International Nuclear Information System (INIS)

Sanchez, F.; Supanitsky, A. D.; Medina-Tanco, G.; Paic, G.; Salazar, M. E. Patino; D'Olivo, J. C.; Molina, R. Alfaro

2009-01-01

Muon hodoscopes have several applications, ranging from astrophysics to fundamental particle physics. In this work, we present a detector dedicated to the study, at ground level, of the main signals of cosmic-ray induced showers above 6 PeV. The whole detector is composed by a set of three parallel dual-layer scintillator planes buried at fix depths ranging from 120 g/cm 2 to 600 g/cm 2 and by a triangular array of water cerenkov detectors located nearby on ground.

Magnetometry of buried layers—Linear magnetic dichroism and spin detection in angular resolved hard X-ray photoelectron spectroscopy

International Nuclear Information System (INIS)

Gloskovskii, Andrei; Stryganyuk, Gregory; Fecher, Gerhard H.; Felser, Claudia; Thiess, Sebastian; Schulz-Ritter, Heiko; Drube, Wolfgang; Berner, Götz; Sing, Michael; Claessen, Ralph; Yamamoto, Masafumi

2012-01-01

Highlights: ► Newly commissioned HAXPES instrument at P09 beamline of the PETRA III ring at DESY. ► We report HAXPES studies on buried magnetic nanolayers in a multi-layer sample. ► Linear magnetic dichroism of photoelectrons from buried CoFe–Ir 78 Mn 22 layers. ► Spin-resolved HAXPES measurements on buried magnetic multilayers using Mott detector. - Abstract: The electronic properties of buried magnetic nano-layers were studied using the linear magnetic dichroism in the angular distribution of photoemitted Fe, Co, and Mn 2p electrons from a CoFe–Ir 78 Mn 22 multi-layered sample. The buried layers were probed using hard X-ray photoelectron spectroscopy, HAXPES, at the undulator beamline P09 of the 3rd generation storage ring PETRA III. The results demonstrate that this magnetometry technique can be used as a sensitive element specific probe for magnetic properties suitable for application to buried ferromagnetic and antiferromagnetic magnetic materials and multilayered spintronics devices. Using the same instrument, spin-resolved Fe 2p HAXPES spectra were obtained from the buried layer with good signal quality.

Atomic friction at exposed and buried graphite step edges: Experiments and simulations

Energy Technology Data Exchange (ETDEWEB)

Ye, Zhijiang; Martini, Ashlie, E-mail: amartini@ucmerced.edu [School of Engineering, University of California Merced, 5200 N. Lake Road, Merced, California 95343 (United States)

2015-06-08

The surfaces of layered materials such as graphite exhibit step edges that affect friction. Step edges can be exposed, where the step occurs at the outmost layer, or buried, where the step is underneath another layer of material. Here, we study friction at exposed and buried step edges on graphite using an atomic force microscope (AFM) and complementary molecular dynamics simulations of the AFM tip apex. Exposed and buried steps exhibit distinct friction behavior, and the friction on either step is affected by the direction of sliding, i.e., moving up or down the step, and the bluntness of the tip. These trends are analyzing in terms of the trajectory of the AFM tip as it moves over the step, which is a convolution of the topography of the surface and the tip shape.

Atomic friction at exposed and buried graphite step edges: Experiments and simulations

International Nuclear Information System (INIS)

Ye, Zhijiang; Martini, Ashlie

2015-01-01

The surfaces of layered materials such as graphite exhibit step edges that affect friction. Step edges can be exposed, where the step occurs at the outmost layer, or buried, where the step is underneath another layer of material. Here, we study friction at exposed and buried step edges on graphite using an atomic force microscope (AFM) and complementary molecular dynamics simulations of the AFM tip apex. Exposed and buried steps exhibit distinct friction behavior, and the friction on either step is affected by the direction of sliding, i.e., moving up or down the step, and the bluntness of the tip. These trends are analyzing in terms of the trajectory of the AFM tip as it moves over the step, which is a convolution of the topography of the surface and the tip shape

Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik [School of Materials Science and Engineering, Andong National University, Andong (Korea, Republic of); Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae [Power Engineering Research Institute, KEPCO Engineering and Construction Company, Seongnam (Korea, Republic of)

2015-02-15

Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

International Nuclear Information System (INIS)

Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik; Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae

2015-01-01

Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

Gamma-ray and surface organic results of the robotic survey of Pit 9 at INEL

International Nuclear Information System (INIS)

Clegg, B.; Rowland, M.; Pence, J.

1991-09-01

The Buried Waste Robotics Program demonstrated and evaluated robotic techniques to non-invasively characterize a representative radiological burial area at the Idaho National Engineering Laboratory (ML). Lawrence Livermore National Laboratory (LLNL) contributed a large, NaI gamma-ray detector system and a photo-ionization organics detector to this program. This Program mounted multiple geophysics, nucleonic, and chemical sensor systems on the Solder Robot Interface Program (SRIP) remotely operated vehicle. These sensors simultaneously collected radiological waste-site, surface characterization data on Pit 9 radiological burial area, and the Cold Test Pit (CTP), off-site control area. LLNL sensors found no radiological waste at the CTP control area, however, we easily detected the natural thorium series, the potassium radionuclides and trace worldwide fallout cesium. Earlier manual measurements indicated no significant data error invoked by the vehicle on our gamma-ray and organic sensor systems. Thick soil overburden at the Subsurface Disposal Area (SDA), Pit 9, permitted radiological, but no isotopic determinations. A flood of scattered photons from the buried waste allows a surface, spatial radiological dose assessment. We found no evidence of surface-evolving organics, sensitive to photo-ionization detection. The observed signals can safely guide a remediation excavation. The vehicle-supported multiple measurements enhanced the data collection efficiency. Data provided site-surface characterization, quickly and safely in potentially hazardous areas. However, a large, buried-waste site will require subsurface access for detailed characterization

FY-94 buried waste integrated demonstration program report

International Nuclear Information System (INIS)

1994-01-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the U.S. Department of Energy (DOE), Environmental Restoration and Waste Management (ER/WM) needs and objectives. This document summarizes previous demonstrations and describes the FY-94 BWID technology development and demonstration activities. Sponsored by the DOE Office of Technology Development (OTD), BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process

Comprehensive Review and Case Study on the Management of Buried Penis Syndrome and Related Panniculectomy

Science.gov (United States)

Burns, Hadley; Chowdhry, Saeed; Lee, Thomas; Schulz, Steven; Wilhelmi, Bradon J.

2018-01-01

Objective: This paper discusses the various surgical techniques and outcomes associated with management of buried penis syndrome. Methods: Presented is the case of a 49-year-old man with morbid obesity, leading to massive panniculus and buried penis. We review our technique for reconstruction of the buried penis and treatment of the overlying large panniculus. Literature search was conducted to review current techniques in correcting buried penis syndrome. Results: The patient underwent a successful panniculectomy with removal of all excess skin and tissue. Thoughtful planning and coordination between plastic surgery and urology were paramount to externalize the penis for an excellent functional and cosmetic result. Conclusions: Management of a buried, hidden penis is complex and difficult. Patients are often obese and have poor hygiene due to the inability to cleanse areas that are entrapped by excessive fat. Following removal of the overhanging panniculus, satisfactory reconstruction of a hidden penis is possible when proper care is taken to adhere the base of the penis to the pubis. Split-thickness skin grafts are often necessary but depend on the viability of the penile skin and whether it is restricting penile length. Complications with wound dehiscence and infection are not uncommon; however, patients generally recover well, are satisfied with results, and are reported to have fully regained urinary and sexual functions following surgical correction of the buried penis. PMID:29467914

Environmental considerations associated with siting, constructing, and operating a special isotope separation plant at INEL: Volume 1, Proceedings: Report of public hearings

International Nuclear Information System (INIS)

1987-03-01

This report documents the two public hearings conducted for the purpose of determining the scope of issues to be addressed in relation to the siting, constructing, and operating of a special isotope separation plant at INEL. The report includes transcripts of the public hearings held in Idaho Falls, Idaho, February 24, 1987, and in Boise, Idaho, February 26, 1987, and includes the exhibits of records relating to those hearings. The review and hearing process meets pertinent National Environmental Policy Act (NEPA) requirements, Council on Environmental Quality (CEQ) regulations, and DOE guidelines

Environmental considerations associated with siting, constructing, and operating a special isotope separation plant at INEL: Volume 2, Proceedings: Report of public hearings

International Nuclear Information System (INIS)

1987-03-01

This report documents the two public hearings conducted for the purpose of determining the scope of issues to be addressed in relation to the siting, constructing, and operating of a special isotope separation plant at INEL. The report includes transcripts of the public hearings held in Idaho Falls, Idaho, February 24, 1987, and in Boise, Idaho, February 26, 1987, and includes the exhibits of record relating to those hearings. The review and hearing process meets pertinent National Environmental Policy Act (NEPA) requirements, Council on Environmental Quality (CEQ) regulations, and DOE guidelines

Detecting buried radium contamination using soil-gas and surface-flux radon meaurements

International Nuclear Information System (INIS)

Karp, K.E.

1988-06-01

The Technical Measurements Center (TMC) has investigated the effectiveness of using radon soil-gas under surface-flux measurments to locate radium contamination that is buried sufficiently deep to be undetectable by surface gamma methods. At the first test site studied, an indication of a buried source was revealed by mapping anomalous surface-flux and soil-gas concentrations in the near surface overburden. The mapped radon anomalies were found to correspond in rough outline to the shape of the areal extent of the deposit as determined by borehole gamma-ray logs. The 5.9pCi/g radium deposit, buried 2 feet below the surface, went undetected by conventional surface gamma measurements. Similar results were obtained at the second test site where radon and conventional surface gamma measurements were taken in an area having radium concentrations ranging from 13.3 to 341.0 pCi/g at a depth of 4 feet below the surface. The radon methods were found to have a detection limit for buried radium lower than that of the surface gamma methods, as evidenced by the discovery of the 13.3 pCi/g deposit which went undetected by the surface gamma methods. 15 refs., 33 figs., 8 tabs

A comparison between decomposition rates of buried and surface remains in a temperate region of South Africa.

Science.gov (United States)

Marais-Werner, Anátulie; Myburgh, J; Becker, P J; Steyn, M

2018-01-01

Several studies have been conducted on decomposition patterns and rates of surface remains; however, much less are known about this process for buried remains. Understanding the process of decomposition in buried remains is extremely important and aids in criminal investigations, especially when attempting to estimate the post mortem interval (PMI). The aim of this study was to compare the rates of decomposition between buried and surface remains. For this purpose, 25 pigs (Sus scrofa; 45-80 kg) were buried and excavated at different post mortem intervals (7, 14, 33, 92, and 183 days). The observed total body scores were then compared to those of surface remains decomposing at the same location. Stages of decomposition were scored according to separate categories for different anatomical regions based on standardised methods. Variation in the degree of decomposition was considerable especially with the buried 7-day interval pigs that displayed different degrees of discolouration in the lower abdomen and trunk. At 14 and 33 days, buried pigs displayed features commonly associated with the early stages of decomposition, but with less variation. A state of advanced decomposition was reached where little change was observed in the next ±90-183 days after interment. Although the patterns of decomposition for buried and surface remains were very similar, the rates differed considerably. Based on the observations made in this study, guidelines for the estimation of PMI are proposed. This pertains to buried remains found at a depth of approximately 0.75 m in the Central Highveld of South Africa.

Direct measurements of the velocity and thickness of ''explosively'' propagating buried molten layers in amorphous silicon

International Nuclear Information System (INIS)

Lowndes, D.H.; Jellison, G.E. Jr.; Pennycook, S.J.; Withrow, S.P.; Mashburn, D.N.

1986-01-01

Simultaneous infrared (1152 nm) and visible (633 nm) reflectivity measurements with nanosecond resolution were used to study the initial formation and subsequent motion of pulsed KrF laser-induced ''explosively'' propagating buried molten layers in ion implantation-amorphized silicon. The buried layer velocity decreases with depth below the surface, but increases with KrF laser energy density; a maximum velocity of about 14 m/s was observed, implying an undercooling-velocity relationship of approx. 14 K/(m/s). Z-contrast scanning transmission electron microscopy was used to form a direct chemical image of implanted Cu ions transported by the buried layer and showed that the final buried layer thickness was <15 nm

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

International Nuclear Information System (INIS)

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

1986-01-01

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

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

International Nuclear Information System (INIS)

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

1986-03-01

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

New Technique for the Treatment of Buried Penis in Children.

Science.gov (United States)

Liu, Feng; Lin, Tao; He, Dawei; Wei, Guanghui; Liu, Junhong; Liu, Xing; Hua, Yi; Zhang, Deying; Lu, Peng; Wu, Shengde; Li, Xuliang

2016-02-01

To present our treatment experience of buried penis, which has no consensus therapeutic technique for all cases of buried penis, by using a new technique for the repair of this condition, in which the approach is through the ventral penile root. We performed a retrospective review of 153 patients (median age: 6.5 years) who underwent repair of a buried penis between March 2005 and March 2013. The technique involves the creation of a wedge-shaped cut of the ventral penile skin, followed by fixation of the subcutaneous penile skin at the base of the degloved penis to the Buck fascia at the 2- and 10-o'clock positions. The ventral outer preputial skin is split down the midline, and the dorsal inner preputial skin is cut with oblique incision. All patients were followed for an average of 12 months after repair. Other than 2 cases (1.3%) of trapped penis with a ring of scar tissue, which required subsequent excision, there were no complications and the cosmetic appearance was satisfactory. The described ventral penile approach is a simple and effective procedure with good cosmetic outcomes and few complications. Copyright © 2016 Elsevier Inc. All rights reserved.

FY-95 technology catalog. Technology development for buried waste remediation

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

FY-95 technology catalog. Technology development for buried waste remediation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

Retrieval of buried waste using conventional equipment

International Nuclear Information System (INIS)

Valentich, D.J.

1994-01-01

A field test was conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive test pit 841 m 3 in volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, vessels, vaults, pipes, and beams were also placed in the pit. These materials were intended to simulate the type of waste found in existing TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were also observed

Buried penis: classification surgical approach.

Science.gov (United States)

Hadidi, Ahmed T

2014-02-01

The purpose of this study was to describe morphological classification of congenital buried penis (BP) and present a versatile surgical approach for correction. Sixty-one patients referred with BP were classified into 3 grades according to morphological findings: Grade 1-29 patients with Longer Inner Prepuce (LIP) only, Grade II-20 patients who presented with LIP associated with indrawn penis that required division of the fundiform and suspensory ligaments, and Grade III-12 patients who had in addition to the above, excess supra-pubic fat. A ventral midline penile incision extending from the tip of prepuce down to the penoscrotal junction was used in all patients. The operation was tailored according to the BP Grade. All patients underwent circumcision. Mean follow up was 3 years (range 1 to 10). All 61 patients had an abnormally long inner prepuce (LIP). Forty-seven patients had a short penile shaft. Early improvement was noted in all cases. Satisfactory results were achieved in all 29 patients in grade I and in 27 patients in grades II and III. Five children (Grades II and III) required further surgery (9%). Congenital buried penis is a spectrum characterized by LIP and may include in addition; short penile shaft, abnormal attachment of fundiform, and suspensory ligaments and excess supra-pubic fat. Congenital Mega Prepuce (CMP) is a variant of Grade I BP, with LIP characterized by intermittent ballooning of the genital area. Copyright © 2014 Elsevier Inc. All rights reserved.

A metallic buried interconnect process for through-wafer interconnection

International Nuclear Information System (INIS)

Ji, Chang-Hyeon; Herrault, Florian; Allen, Mark G

2008-01-01

In this paper, we present the design, fabrication process and experimental results of electroplated metal interconnects buried at the bottom of deep silicon trenches with vertical sidewalls. A manual spray-coating process along with a unique trench-formation process has been developed for the electroplating of a metal interconnection structure at the bottom surface of the deep trenches. The silicon etch process combines the isotropic dry etch process and conventional Bosch process to fabricate a deep trench with angled top-side edges and vertical sidewalls. The resulting trench structure, in contrast to the trenches fabricated by wet anisotropic etching, enables spray-coated photoresist patterning with good sidewall and top-side edge coverage while maintaining the ability to form a high-density array of deep trenches without excessive widening of the trench opening. A photoresist spray-coating process was developed and optimized for the formation of electroplating mold at the bottom of 300 µm deep trenches having vertical sidewalls. A diluted positive tone photoresist with relatively high solid content and multiple coating with baking between coating steps has been experimentally proven to provide high quality sidewall and edge coverage. To validate the buried interconnect approach, a three-dimensional daisy chain structure having a buried interconnect as the bottom connector and traces on the wafer surface as the top conductor has been designed and fabricated

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Krisman, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-07-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the acid pit and transuranic pits and trenches (TRU-PTs) at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues lated with ISV application at the SDA. The activities of the ISV Steering Committee are summarized in a three-volume report. Volume I identifies the systematic approach used to identify and prioritize the ISV technical issues and briefly discusses the methodology that will be employed to resolve these issues. Volumes 2 and 3 discuss each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTS, respectively. The three-volume report is a working document that will be updated as necessary to reflect current evaluation strategy for the ISV technology. This is Volume 3

Detection of buried pipes by polarimetric borehole radar; Polarimetric borehole radar ni yoru maisetsukan no kenshutsu jikken

Energy Technology Data Exchange (ETDEWEB)

Sato, M.; Niitsuma, H. [Tohoku University, Sendai (Japan); Nakauchi, T. [Osaka Gas Co. Ltd., Osaka (Japan)

1997-05-27

If the borehole radar is utilized for detection of buried pipes, the underground radar measurement becomes possible even in the situation where the mesurement on the earth surface is difficult, for example, such a place as under the road where there is much traffic. However, since buried pipes are horizontally installed and the existing borehole radar can send/receive only vertical polarization, the measurement conducted comes to be poor in efficiency from a viewpoint of the polarization utilization. Therefore, by introducing the polarimetric borehole radar to the detection of buried pipes, a basic experiment was conducted for the effective detection of horizontal buried pipes. Proposing the use of a slot antenna which can send/receive horizontal polarization in borehole in addition to a dipole antenna which sends/receives vertical polarization, developed was a step frequency type continuous wave radar of a network analyzer basis. As a result of the experiment, it was confirmed that reflection from buried pipes is largely dependent on polarization. Especially, it was found that in the slot dipole cross polarization mesurement, reflection from buried pipes can be emphasized. 4 refs., 5 figs.

The Thermal Regime Around Buried Submarine High-Voltage Cables

Science.gov (United States)

Emeana, C. J.; Dix, J.; Henstock, T.; Gernon, T.; Thompson, C.; Pilgrim, J.

2015-12-01

The expansion of offshore renewable energy infrastructure and the desire for "trans-continental shelf" power transmission, all require the use of submarine High Voltage (HV) cables. These cables have maximum operating surface temperatures of up to 70oC and are typically buried at depths of 1-2 m beneath the seabed, within the wide range of substrates found on the continental shelf. However, the thermal properties of near surface shelf sediments are poorly understood and this increases the uncertainty in determining the required cable current ratings, cable reliability and the potential effects on the sedimentary environments. We present temperature measurements from a 2D laboratory experiment, designed to represent a buried, submarine HV cable. We used a large (2.5 m-high) tank, filled with water-saturated ballotini and instrumented with 120 thermocouples, which measured the time-dependent 2D temperature distributions around the heat source. The experiments use a buried heat source to represent a series of realistic cable surface temperatures with the aim for identifying the thermal regimes generated within typical non-cohesive shelf sediments: coarse silt, fine sand and very coarse sand. The steady state heat flow regimes, and normalised and radial temperature distributions were assessed. Our results show that at temperatures up to 60°C above ambient, the thermal regimes are conductive for the coarse silt sediments and convective for the very coarse sand sediments even at 7°C above ambient. However, the heat flow pattern through the fine sand sediment shows a transition from conductive to convective heat flow at a temperature of approximately 20°C above ambient. These findings offer an important new understanding of the thermal regimes associated with submarine HV cables buried in different substrates and has huge impacts on cable ratings as the IEC 60287 standard only considers conductive heat flow as well as other potential near surface impacts.

Electrochemical deposition of buried contacts in high-efficiency crystalline silicon photovoltaic cells

DEFF Research Database (Denmark)

Jensen, Jens Arne Dahl; Møller, Per; Bruton, Tim

2003-01-01

This article reports on a newly developed method for electrochemical deposition of buried Cu contacts in Si-based photovoltaic ~PV! cells. Contact grooves, 20 mm wide by 40 mm deep, were laser-cut into Si PV cells, hereafter applied with a thin electroless NiP base and subsequently filled with Cu...... by electrochemical deposition at a rate of up to 10 mm per min. With the newly developed process, void-free, superconformal Cu-filling of the laser-cut grooves was observed by scanning electron microscopy and focused ion beam techniques. The Cu microstructure in grooves showed both bottom and sidewall texture......, with a grain-size decreasing from the center to the edges of the buried Cu contacts and a pronounced lateral growth outside the laser-cut grooves. The measured specific contact resistances of the buried contacts was better than the production standard. Overall performance of the new PV cells was equal...

Buried bumber syndrome (internal button buried of the gastrostomy): Unearthing the solution

International Nuclear Information System (INIS)

Moreno, Nelson; Otero, William; Gomez, Martin; Bula, Rodrigo; Otero, Elder

2006-01-01

The Buried bumper syndrome is a major complication of percutaneous endoscopic gastrostomy and the literature of in of having described of rarely. The physiopathology is the gastric isquemy of the mucous one for an excessive pressure for the ends that fix the gastrostomy. Their clinical manifestations that depend on the depth of migration of the end go from the absence of symptoms, spill of the nutrition enteral being the most frequent, until peritonitis. The diverse described treatment modalities are based on the depth of migration of the end valued endoscopically. The successful use of the ecoendosonography is described for the estimate of the depth of the migration, when you cannot visualize the end internal endoscopically and we propose a handling .algorithm based on this technique

User's and reference guide to the INEL RML/analytical radiochemistry sample tracking database version 1.00

International Nuclear Information System (INIS)

Femec, D.A.

1995-09-01

This report discusses the sample tracking database in use at the Idaho National Engineering Laboratory (INEL) by the Radiation Measurements Laboratory (RML) and Analytical Radiochemistry. The database was designed in-house to meet the specific needs of the RML and Analytical Radiochemistry. The report consists of two parts, a user's guide and a reference guide. The user's guide presents some of the fundamentals needed by anyone who will be using the database via its user interface. The reference guide describes the design of both the database and the user interface. Briefly mentioned in the reference guide are the code-generating tools, CREATE-SCHEMA and BUILD-SCREEN, written to automatically generate code for the database and its user interface. The appendices contain the input files used by the these tools to create code for the sample tracking database. The output files generated by these tools are also included in the appendices

Detection of buried land mines using back scattered neutron induced γ-ray analysis

International Nuclear Information System (INIS)

Aziz, M.; Megahd, R.

2003-01-01

The application of nuclear technique to detection buried land mine is examined. MCNP code was used to design a computer model that calculate the back scattered neutron induced γ rays from buried simulate explosive materials. The characteristic γ rays for each isotopes were used to distinguish materials. The advantage of the nuclear technique was discussed. The results were compared with experimental measurements which show good agreement

Ground Penetrating Radar Imaging of Buried Metallic Objects

DEFF Research Database (Denmark)

Polat, A. Burak; Meincke, Peter

2001-01-01

During the past decade there has been considerable research on ground penetrating radar (GPR) tomography for detecting objects such as pipes, cables, mines and barrels buried under the surface of the Earth. While the earlier researches were all based on the assumption of a homogeneous background...

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rechard, R.P.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency's Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

Rechard, R.P. [ed.

1993-12-01

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Building America Case Study: Compact Buried Ducts in a Hot-Humid Climate House, Lady's Island, South Carolina

Energy Technology Data Exchange (ETDEWEB)

2016-02-01

A system of compact, buried ducts provides a high-performance and cost-effective solution for delivering conditioned air throughout the building. This report outlines research activities that are expected to facilitate adoption of compact buried duct systems by builders. The results of this research would be scalable to many new house designs in most climates and markets, leading to wider industry acceptance and building code and energy program approval. The primary research question with buried ducts is potential condensation at the outer jacket of the duct insulation in humid climates during the cooling season. Current best practices for buried ducts rely on encapsulating the insulated ducts with closed-cell spray polyurethane foam insulation to control condensation and improve air sealing. The encapsulated buried duct concept has been analyzed and shown to be effective in hot-humid climates. The purpose of this project is to develop an alternative buried duct system that performs effectively as ducts in conditioned space - durable, energy efficient, and cost-effective - in a hot-humid climate (IECC warm-humid climate zone 3A) with three goals that distinguish this project: 1) Evaluation of design criteria for buried ducts that use common materials and do not rely on encapsulation using spray foam or disrupt traditional work sequences, 2) Establishing design criteria for compact ducts and incorporate those with the buried duct criteria to further reduce energy losses and control installed costs, and 3) Developing HVAC design guidance for performing accurate heating and cooling load calculations for compact buried ducts.

History of the incipient Icelandic plume: Observations from ancient buried landscapes

Science.gov (United States)

Stucky de Quay, Gaia; Roberts, Gareth G.; Watson, Jonathan S.; Jackson, Christopher A.-L.

2017-04-01

Ancient buried terrestrial landscapes contain records of vertical motions which can be used to probe histories of geodynamical processes. In the North Atlantic Ocean, sedimentary basins contain excellent evidence that the continental shelf experienced staged subaerial exposure. For example, now buried landscapes were uplifted, rapidly eroded, and drowned close to the Paleocene-Eocene boundary. We use commercial wells and three-dimensional seismic data to reconstruct a 57-55 Ma landscape now buried 1.5 km beneath the seabed in the Bressay area of the northern North Sea. Geochemical analyses of organic matter from core samples intersecting the erosional landscape indicate the presence of angiosperm (flowering plant) debris. Combined with the presence of coarse clastic material, mapped beach ridges, and dendritic drainage patterns, these observations indicate that this landscape was of terrestrial origin. Longitudinal profiles of ancient rivers were extracted and inverted for an uplift rate history. The best-fitting uplift rate history has three phases and total cumulative uplift of 350 m. Biostratigraphic data from surrounding marine stratigraphy indicate that this landscape formed within 1-1.5 Ma. This uplift history is similar to that of a slightly older buried landscape in the Faeroe-Shetland basin 400 km to the west. These records of vertical motion can explained by pulses of anomalously hot asthenosphere spreading out from the incipient Icelandic plume. Using simple isostatic calculations we estimate that the maximum thermal anomaly beneath Bressay was 50˚. Our observations suggest that a thermal anomaly departed the Icelandic plume as early as 58.5 Ma and had highest average temperatures at 55.6 Ma.

Seed longevity of Eragrostis plana Nees buried in natural grassland soil

Directory of Open Access Journals (Sweden)

Renato Borges de Medeiros

2014-11-01

Full Text Available The objective of this research was to evaluate the seed longevity of Eragrostis plana Nees buried at different soil depths, in a natural-grassland area in the Pampa biome (46 m altitude, 30º05´S and 51º40´W of Rio Grande do Sul State, Brazil. The experimental design was a split-plot type in complete blocks with two factors: seeds buried at five different depth levels (soil surface and 2.5, 5, 10 and 20 cm and seven exhumation dates. The blocks were allocated in natural grassland grazed by cattle, allocated in a 12-m-long transection. Fifty-four permeable nylon bags filled with 100 seeds in each division, with five vertical divisions, were buried in each row. Seven exhumation dates were used: the first on October 14, 2003 and the last on January 14, 2006. The percentage of viable seeds of E. plana, collected at seven exhumation times and set at different depths in the soil horizon, were described by simple negative exponential equations. Based on the model, the percentage of viable seeds collected at the five depths, (soil surface and 2.5, 5, 10, and 20 cm, after 2.5 years of burial, were 0.1, 0.5, 1.0, 7.4 and 22.1%, respectively. Increase in depth is directly associated with physical and physiological seed integrity of E. plana. Negative simple exponential equations can be used to predict seed longevity of E. plana buried in nylon bags. This invader species accumulates soil seed-bank of high longevity.

Characteristic electron energy loss spectra in SiC buried layers formed by C+ implantation into crystalline silicon

International Nuclear Information System (INIS)

Yan Hui; Chen Guanghua; Kwok, R.W.M.

1998-01-01

SiC buried layers were synthesized by a metal vapor vacuum arc ion source, with C + ions implanted into crystalline Si substrates. According to X-ray photoelectron spectroscopy, the characteristic electron energy loss spectra of the SiC buried layers were studied. It was found that the characteristic electron energy loss spectra depend on the profiles of the carbon content, and correlate well with the order of the buried layers

Site Assessment of Multiple-Sensor Approaches for Buried Utility Detection

Directory of Open Access Journals (Sweden)

Alexander C. D. Royal

2011-01-01

Full Text Available The successful operation of buried infrastructure within urban environments is fundamental to the conservation of modern living standards. Open-cut methods are predominantly used, in preference to trenchless technology, to effect a repair, replace or install a new section of the network. This is, in part, due to the inability to determine the position of all utilities below the carriageway, making open-cut methods desirable in terms of dealing with uncertainty since the buried infrastructure is progressively exposed during excavation. However, open-cut methods damage the carriageway and disrupt society's functions. This paper describes the progress of a research project that aims to develop a multi-sensor geophysical platform that can improve the probability of complete detection of the infrastructure buried beneath the carriageway. The multi-sensor platform is being developed in conjunction with a knowledge-based system that aims to provide information on how the properties of the ground might affect the sensing technologies being deployed. The fusion of data sources (sensor data and utilities record data is also being researched to maximize the probability of location. This paper describes the outcome of the initial phase of testing along with the development of the knowledge-based system and the fusing of data to produce utility maps.

Burying behaviour of two sympatric crab species: Cancer magister and Cancer productus

Directory of Open Access Journals (Sweden)

Iain J. McGaw

2005-09-01

Full Text Available The mechanics and emergence patterns associated with burying behaviour were investigated in the Dungeness crab, Cancer magister, and the red rock crab, Cancer productus. Cancer magister used both the legs and chelae to excavate the sand, whereas Cancer productus used the legs to pull and push itself down into the sediment only using the chelae in a final push beneath the sediment. Several individuals of each species remained buried for over 50 h, which was accomplished by alterations in ventilatory physiology. More commonly, both species exhibited an endogenous rhythm of circadian periodicity, with peak periods of emergence from the sand occurring during nocturnal high tides. Although burial may act as a means of predator evasion and to ambush prey, it appears the primary reason may be to conserve energy. These two species of crabs often occur sympatrically; the difference in behaviours is closely related to previously reported differences in physiological mechanisms between the two species when buried.

Theoretical investigation of metal magnetic memory testing technique for detection of magnetic flux leakage signals from buried defect

Science.gov (United States)

Xu, Kunshan; Qiu, Xingqi; Tian, Xiaoshuai

2018-01-01

The metal magnetic memory testing (MMMT) technique has been extensively applied in various fields because of its unique advantages of easy operation, low cost and high efficiency. However, very limited theoretical research has been conducted on application of MMMT to buried defects. To promote study in this area, the equivalent magnetic charge method is employed to establish a self-magnetic flux leakage (SMFL) model of a buried defect. Theoretical results based on the established model successfully capture basic characteristics of the SMFL signals of buried defects, as confirmed via experiment. In particular, the newly developed model can calculate the buried depth of a defect based on the SMFL signals obtained via testing. The results show that the new model can successfully assess the characteristics of buried defects, which is valuable in the application of MMMT in non-destructive testing.

Strategies for managing rival bacterial communities: Lessons from burying beetles.

Science.gov (United States)

Duarte, Ana; Welch, Martin; Swannack, Chris; Wagner, Josef; Kilner, Rebecca M

2018-03-01

The role of bacteria in animal development, ecology and evolution is increasingly well understood, yet little is known of how animal behaviour affects bacterial communities. Animals that benefit from defending a key resource from microbial competitors are likely to evolve behaviours to control or manipulate the animal's associated external microbiota. We describe four possible mechanisms by which animals could gain a competitive edge by disrupting a rival bacterial community: "weeding," "seeding," "replanting" and "preserving." By combining detailed behavioural observations with molecular and bioinformatic analyses, we then test which of these mechanisms best explains how burying beetles, Nicrophorus vespilloides, manipulate the bacterial communities on their carcass breeding resource. Burying beetles are a suitable species to study how animals manage external microbiota because reproduction revolves around a small vertebrate carcass. Parents shave a carcass and apply antimicrobial exudates on its surface, shaping it into an edible nest for their offspring. We compared bacterial communities in mice carcasses that were either fresh, prepared by beetles or unprepared but buried underground for the same length of time. We also analysed bacterial communities in the burying beetle's gut, during and after breeding, to understand whether beetles could be "seeding" the carcass with particular microbes. We show that burying beetles do not "preserve" the carcass by reducing bacterial load, as is commonly supposed. Instead, our results suggest they "seed" the carcass with bacterial groups which are part of the Nicrophorus core microbiome. They may also "replant" other bacteria from the carcass gut onto the surface of their carrion nest. Both these processes may lead to the observed increase in bacterial load on the carcass surface in the presence of beetles. Beetles may also "weed" the bacterial community by eliminating some groups of bacteria on the carcass, perhaps through

Buried Waste Integrated Demonstration lessons learned: 1993 technology demonstrations

International Nuclear Information System (INIS)

Kostelnik, K.M.; Owens, K.J.

1994-01-01

An integrated technology demonstration was conducted by the Buried Waste Integrated Demonstration (BWID) at the Idaho National Engineering Laboratory Cold Test Pit in the summer of 1993. This program and demonstration was sponsored by the US Department of Energy Office of Technology Development. The demonstration included six technologies representing a synergistic system for the characterization and retrieval of a buried hazardous waste site. The integrated technology demonstration proved very successful and a summary of the technical accomplishments is presented. Upon completion of the integrated technology demonstration, cognizant program personnel participated in a lessons learned exercise. This exercise was conducted at the Simplot Decision Support Center at Idaho State University and lessons learned activity captured additional information relative to the integration of technologies for demonstration purposes. This information will be used by BWID to enhance program planning and strengthen future technology demonstrations

Regulatory issues and assumptions associated with barriers in the vadose zone surrounding buried waste

International Nuclear Information System (INIS)

Siskind, B.; Heiser, J.

1993-02-01

One of the options for control of contaminant migration from buried waste sites is the construction of a subsurface barrier that consists of a wall of low permeability material. The barrier material should be compatible with soil and waste conditions specific to the site and have as low an effective diffusivity as is reasonably achievable to minimize or inhibit transport of moisture and contaminants. This report addresses the regulatory issues associated with the use of non-traditional organic polymer barriers as well as the use of soil-bentonite or cement-bentonite mixtures for such barriers, considering barriers constructed from these latter materials to be a regulatory baseline. The regulatory issues fall into two categories. The first category consists of issues associated with the acceptability of such barriers to the EPA as a method for achieving site or performanceimprovement. The second category encompasses those regulatory issues concerning health, safety and the environment which must be addressed regarding barrier installation and performance, especially if non-traditional materials are to be used

Evaluation of overweight load routing on buried utility facilities

Science.gov (United States)

2011-02-01

Overweight traffic movements can negatively affect pavement integrity and quality. However, it is less : known to what degree buried utility plant along and across the right of way is affected by these overweight : loads, especially if the utility fa...

A Newton method for a simultaneous reconstruction of an interface and a buried obstacle from far-field data

International Nuclear Information System (INIS)

Zhang, Haiwen; Zhang, Bo

2013-01-01

This paper is concerned with the inverse problem of scattering of time-harmonic acoustic waves from a penetrable and a buried obstacle. By introducing a related transmission scattering problem, a Newton iteration method is proposed to simultaneously reconstruct both the penetrable interface and the buried obstacle inside from far-field data. The main feature of our method is that we do not need to know the type of boundary conditions on the buried obstacle. In particular, the boundary condition on the buried obstacle can also be determined simultaneously by the method. Finally, numerical examples using multi-frequency data are carried out to illustrate the effectiveness of our method. (paper)

A Title 40 Code of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site - 8210

International Nuclear Information System (INIS)

G J Shott; V Yucel; L Desotell

2008-01-01

In 1986, 21 m 3 of transuranic (TRU) waste was inadvertently buried in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site (NTS). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is considered five options for management of the buried TRU waste. One option is to leave the waste in-place if the disposal can meet the requirements of Title 40 Code of Federal Regulations (CFR) Part 191, 'Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes'. This paper describes analyses that assess the likelihood that TRU waste in shallow land burial can meet the 40 CFR 191 standards for a geologic repository. The simulated probability of the cumulative release exceeding 1 and 10 times the 40 CFR 191.13 containment requirements is estimated to be 0.009 and less than 0.0001, respectively. The cumulative release is most sensitive to the number of groundwater withdrawal wells drilled through the disposal trench. The mean total effective dose equivalent for a member of the public is estimated to reach a maximum of 0.014 milliSievert (mSv) at 10,000 years, or approximately 10 percent of the 0.15 mSv 40 CFR 191.15 individual protection requirement. The dose is predominantly from inhalation of short-lived Rn-222 progeny in air produced by low-level waste disposed in the same trench. The transuranic radionuclide released in greatest amounts, Pu-239, contributes only 0.4 percent of the dose. The member of public dose is most sensitive to the U-234 inventory and the radon emanation coefficient. Reasonable assurance of compliance with the Subpart C groundwater protection standard is provided by site characterization data and hydrologic processes modeling which support a conclusion of no groundwater pathway within 10,000 years. Limited quantities of transuranic waste in a shallow land burial trench at the NTS can meet

Reactions and Diffusion During Annealing-Induced H(+) Generation in SOI Buried Oxides

International Nuclear Information System (INIS)

Devine, R.A.B.; Fleetwood, D.M.; Vanheusden, K; Warren, W.L.

1999-01-01

We report experimental results suggesting that mobile protons are generated at strained Si-O-Si bonds near the Si/SiO 2 interface during annealing in forming gas. Our data further suggest that the presence of the top Si layer plays a crucial role in the mobile H + generation process. Finally, we show that the diffusion of the reactive species (presumably H 2 or H 0 ) towards the H + generation sites occurs laterally along the buried oxide layer, and can be impeded significantly due to the presence of trapping sites in the buried oxide

Method of retrieving an object buried in the bottom of a body of water

Energy Technology Data Exchange (ETDEWEB)

van Steveninck, J

1975-05-14

In this method of retrieving an object buried in the bottom of a body of water, the object to be retrieved has a number of openings or nozzles, with the aid of at least some of which the object has been buried by fluidization in the bottom of a body of water, for example a fluidization device for burying a pipeline or a fluidization anchor. The method consists of supplying a gas to the buried object, allowing the gas to pass to and through openings or nozzles on the object in such a manner that the gas will be introduced into, and will refluidize the bottom material above the object, and raising the object. Experiments have shown that in this manner fluidization can be reestablished immediately, due to the low density and the low viscosity of the gas, whereafter the object due to the low resistance of the refluidized bottom material is easy to raise to the surface, even after the fluidization has been interrupted for a long period of time. Preferably, the gas used is air, since air is readily available; however, other gases can be used, if desired. (7 claims)

The importance to reveal buried interfaces in the semiconductor heterostructure devices

International Nuclear Information System (INIS)

Takeda, Yoshikazu; Tabuchi, Masao

2007-01-01

Even though several in-situ monitoring techniques exist and are quite useful to understand the growth processes in MBE or MOVPE, we also need a technique to reveal the buried interfaces along which carriers are transported and recombine to emit light. The interface is modified during the capping (overgrowth) and also during the device fabrication processes after growth. We need to correlate the interface structures in the devices and the device performances. The only technique we have at present is the X-ray CTR scattering measurements. We discuss the limits of the in-situ monitoring and the necessity to reveal the buried interfaces non-destructively, either in-situ or ex-situ

Concerning enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material

International Nuclear Information System (INIS)

1988-01-01

The Atomic Safety Commission of Japan, after examining a report submitted by the Science and Technology Agency concerning the enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material, has approved the plan given in the report. Thus, laws and regulations concerning procedures for application for waste burying business, technical standards for implementation of waste burying operation, and measures to be taken for security should be established to ensure the following. Matters to be described in the application for the approval of such business and materials to be attached to the application should be stipulated. Technical standards concerning inspection of waste burying operation should be stipulated. Measures to be taken for the security of waste burying facilities and security concerning the transportation and disposal of nuclear fuel material should be stipulated. Matters to be specified in the security rules should be stipulated. Matters to be recorded by waste burying business operators, measures to be taken to overcome dangers and matters to be reported to the Science and Technology Agency should be stipulated. (Nogami, K.)

Burying Nutrition Myths and Activating Choices for our Children's ...

African Journals Online (AJOL)

Burying Nutrition Myths and Activating Choices for our Children's Development. Lawrence Haddad. Abstract. (Af. J. of Food, Agriculture, Nutrition and Development: 2003 3(1): 56-59). Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT.

Field test plan: Buried waste technologies, Fiscal Year 1995

International Nuclear Information System (INIS)

Heard, R.E.; Hyde, R.A.; Engleman, V.S.; Evans, J.D.; Jackson, T.W.

1995-06-01

The US Department of Energy, Office of Technology Development, supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that, when integrated with commercially available baseline technologies, form a comprehensive remediation system for the effective and efficient remediation of buried waste. The Fiscal Year 1995 effort is to deploy and test multiple technologies from four functional areas of buried waste remediation: site characterization, waste characterization, retrieval, and treatment. This document is the basic operational planning document for the deployment and testing of the technologies that support the field testing in Fiscal Year 1995. Discussed in this document are the scope of the tests; purpose and objective of the tests; organization and responsibilities; contingency plans; sequence of activities; sampling and data collection; document control; analytical methods; data reduction, validation, and verification; quality assurance; equipment and instruments; facilities and utilities; health and safety; residuals management; and regulatory management

Graphite electrode arc melter demonstration Phase 2 test results

International Nuclear Information System (INIS)

Soelberg, N.R.; Chambers, A.G.; Anderson, G.L.; O'Connor, W.K.; Oden, L.L.; Turner, P.C.

1996-06-01

Several U.S. Department of Energy organizations and the U.S. Bureau of Mines have been collaboratively conducting mixed waste treatment process demonstration testing on the near full-scale graphite electrode submerged arc melter system at the Bureau's Albany (Oregon) Research Center. An initial test series successfully demonstrated arc melter capability for treating surrogate incinerator ash of buried mixed wastes with soil. The conceptual treatment process for that test series assumed that buried waste would be retrieved and incinerated, and that the incinerator ash would be vitrified in an arc melter. This report presents results from a recently completed second series of tests, undertaken to determine the ability of the arc melter system to stably process a wide range of open-quotes as-receivedclose quotes heterogeneous solid mixed wastes containing high levels of organics, representative of the wastes buried and stored at the Idaho National Engineering Laboratory (INEL). The Phase 2 demonstration test results indicate that an arc melter system is capable of directly processing these wastes and could enable elimination of an up-front incineration step in the conceptual treatment process

Full-scale retrieval of simulated buried transuranic waste

International Nuclear Information System (INIS)

Valentich, D.J.

1993-09-01

This report describes the results of a field test conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive) test pit (1,100 yd 3 volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, tanks, vaults, pipes, and beams, were also placed in the pit. These materials were intended to simulate the type of wastes found in TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were observed. The feasibility of teleoperating reading equipment was also addressed

A comparison of buried oxide characteristics of single and multiple implant SIMOX and bond and etch back wafers

International Nuclear Information System (INIS)

Annamalai, N.K.; Bockman, J.F.; McGruer, N.E.; Chapski, J.

1990-01-01

The current through the buried oxides of single and multiple implant SIMOX and bond and etch back silicon-on-insulator (BESOI) wafers were measured as a function of radiation dose. From these measurements, conductivity and static capacitances were derived. High frequency capacitances were also measured. Leakage current through the buried oxide of multiple implant SIMOX is considerably less than that of single implant SIMOX (more than an order of magnitude). High frequency and static capacitances, as a function of total dose, were used to study the buried oxide---top silicon interface and the buried oxide---bottom silicon interface. Multiple implant had fewer interface traps than single implant at pre-rad and after irradiation

Distinguishing Buried Objects in Extremely Shallow Underground by Frequency Response Using Scanning Laser Doppler Vibrometer

Science.gov (United States)

Touma Abe,; Tsuneyoshi Sugimoto,

2010-07-01

A sound wave vibration using a scanning laser Doppler vibrometer are used as a method of exploring and imaging an extremely shallow underground. Flat speakers are used as a vibration source. We propose a method of distinguishing a buried object using a response range of a frequencies corresponding to a vibration velocities. Buried objects (plastic containers, a hollow steel can, an unglazed pot, and a stone) are distinguished using a response range of frequencies. Standardization and brightness imaging are used as methods of discrimination. As a result, it was found that the buried objects show different response ranges of frequencies. From the experimental results, we confirmed the effectiveness of our proposed method.

Instability of buried hydration sites increases protein subdomains fluctuations in the human prion protein by the pathogenic mutation T188R

Directory of Open Access Journals (Sweden)

Katsufumi Tomobe

2016-05-01

Full Text Available The conformational change from the cellular prion protein (PrPc to scrapie prion protein (PrPsc is a key process in prion diseases. The prion protein has buried water molecules which significantly contribute to the stability of the protein; however, there has been no report investigating the influence on the buried hydration sites by a pathogenic mutation not adjacent to the buried hydration sites. Here, we perform molecular dynamics simulations of wild type (WT PrPc and pathogenic point mutant T188R to investigate conformational changes and the buried hydration sites. In WT-PrPc, four buried hydration sites are identified by residence time and rotational relaxation analysis. However, there are no stable buried hydration sites in one of T188R simulations, which indicates that T188R sometimes makes the buried hydration sites fragile. We also find that fluctuations of subdomains S1-H1-S2 and H1-H2 increase in T188R when the buried hydration sites become unstable. Since the side chain of arginine which is replaced from threonine in T188R is larger than of threonine, the side chain cannot be embedded in the protein, which is one of the causes of the instability of subdomains. These results show correlations between the buried hydration sites and the mutation which is far from them, and provide a possible explanation for the instability by mutation.

Instability of buried hydration sites increases protein subdomains fluctuations in the human prion protein by the pathogenic mutation T188R

Science.gov (United States)

Tomobe, Katsufumi; Yamamoto, Eiji; Akimoto, Takuma; Yasui, Masato; Yasuoka, Kenji

2016-05-01

The conformational change from the cellular prion protein (PrPc) to scrapie prion protein (PrPsc) is a key process in prion diseases. The prion protein has buried water molecules which significantly contribute to the stability of the protein; however, there has been no report investigating the influence on the buried hydration sites by a pathogenic mutation not adjacent to the buried hydration sites. Here, we perform molecular dynamics simulations of wild type (WT) PrPc and pathogenic point mutant T188R to investigate conformational changes and the buried hydration sites. In WT-PrPc, four buried hydration sites are identified by residence time and rotational relaxation analysis. However, there are no stable buried hydration sites in one of T188R simulations, which indicates that T188R sometimes makes the buried hydration sites fragile. We also find that fluctuations of subdomains S1-H1-S2 and H1-H2 increase in T188R when the buried hydration sites become unstable. Since the side chain of arginine which is replaced from threonine in T188R is larger than of threonine, the side chain cannot be embedded in the protein, which is one of the causes of the instability of subdomains. These results show correlations between the buried hydration sites and the mutation which is far from them, and provide a possible explanation for the instability by mutation.

Seismic fragility analysis of buried steel piping at P, L, and K reactors

International Nuclear Information System (INIS)

Wingo, H.E.

1989-10-01

Analysis of seismic strength of buried cooling water piping in reactor areas is necessary to evaluate the risk of reactor operation because seismic events could damage these buried pipes and cause loss of coolant accidents. This report documents analysis of the ability of this piping to withstand the combined effects of the propagation of seismic waves, the possibility that the piping may not behave in a completely ductile fashion, and the distortions caused by relative displacements of structures connected to the piping

In situ grouting of buried transuranic waste

International Nuclear Information System (INIS)

Spalding, B.P.; Lee, S.Y.

1987-01-01

This task is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34,000 liters of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. The grout was also completely contained within the two trenches as no grout constituents were observed in the 12 perimeter ground water monitoring wells. Polyacrylamide grout was selected for field demonstration over polyacrylate grout because of its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty of controlling the set time of the acrylate polymerization process in the presence of potassium ferricyanide. Based on preliminary degradation monitoring, polyacrylamide was estimated to have a microbiological half-life of 115 years in the test soil. However, this calculated value is likely to be conservatively low because microbial degradation of the grout set accelerator or residual monomer may be contributing most to the measured microbial respiration. Addition work, using 14 C-labeled acrylate and acrylamide grouts, is being carried out to more accurately estimate the grouts' microbiological half-life

Support for the in situ vitrification treatability study at the Idaho National Engineering Laboratory: FY 1988 summary

International Nuclear Information System (INIS)

Oma, K.H.; Reimus, M.A.H.; Timmerman, C.L.

1989-02-01

The objective of this project is to determine if in situ vitrification (ISV) is a viable, long-term confinement technology for previously buried solid transuranic and mixed waste at the Radioactive Waste Management Complex (RWMC). The RWMC is located at the Idaho National Engineering Laboratory (INEL). In situ vitrification is a thermal treatment process that converts contaminated soils and wastes into a durable glass and crystalline form. During processing, heavy metals or other inorganic constituents are retained and immobilized in the glass structure, and organic constituents are typically destroyed or removed for capture by an off-gas treatment system. The primary FY 1988 activities included engineering-scale feasibility tests on INEL soils containing a high metals loading. Results of engineering-scale testing indicate that wastes with a high metals content can be successfully processed by ISV. The process successfully vitrified soils containing localized metal concentrations as high as 42 wt % without requiring special methods to prevent electrical shorting within the melt zone. Vitrification of this localized concentration resulted in a 15.9 wt % metals content in the entire ISV test block. This ISV metals limit is related to the quantity of metal that accumulates at the bottom of the molten glass zone. Intermediate pilot-scale testing is recommended to determine metals content scale-up parameters in order to project metals content limits for large-scale ISV operation at INEL

Detectability Measurement of GPR for Buried Target in Self-Designed Test Field

International Nuclear Information System (INIS)

Son, Soo Jung; Shin, Byoung Chul

2000-01-01

In this paper, we were investigated the detectability on various specimen in self-designed test field using the GPR system with three antenna elements. The GPR system was constantly radiated 730MHz frequency. To examine the detectability on various condition, the test were experimented using different materials, size and buried depth. As an adjusted wave-propagation velocity, the location of hyperbolic curve pattern were displayed B-scan CRT. And the pattern was exactly positioned when it was compared to the real buried-depth. Therefore, we can confirm similarity between the wave-propagation velocity and previous results

In situ chemical state analysis of buried polymer/metal adhesive interface by hard X-ray photoelectron spectroscopy

International Nuclear Information System (INIS)

Ozawa, Kenichi; Kakubo, Takashi; Shimizu, Katsunori; Amino, Naoya; Mase, Kazuhiko; Ikenaga, Eiji; Nakamura, Tetsuya; Kinoshita, Toyohiko; Oji, Hiroshi

2014-01-01

Highlights: • Chemical state analysis of the buried rubber/brass interface is conducted by HAXPES. • Ultrathin rubber films are prepared on the brass surface by two methods. • A high density of Cu 2 S is found on the rubber side of the buried adhesive layer. • The chemical states of the buried and exposed interfaces are compared. - Abstract: Chemical state analysis of adhesive interfaces is important to understand an adhesion mechanism between two different materials. Although photoelectron spectroscopy (PES) is an ideal tool for such an analysis, the adhesive interfaces must be exposed to the surface because PES is essentially a surface sensitive technique. However, an in situ observation is possible by hard X-ray PES (HAXPES) owing to its large probing depth. In the present study, HAXPES is applied to investigate the adhesive interface between rubber and brass without exposing the interface. It is demonstrated that copper sulfides formed at the buried rubber/brass interface are distinguished from S-containing species in the rubber overlayer. The chemical state of the buried interface is compared with that of the “exposed” interface prepared by so-called a filter-paper method

Super analog computer for evaluating the safety of buried radioactive waste

International Nuclear Information System (INIS)

Cohen, B.L.

1980-01-01

It is argued that the past use of digital computer programs for evaluating the safety of buried radioactive waste has been largely wasteful and dangerously delusive. It is suggested to use actual rocks as the analog of buried waste. The problem of comparable rates of leaching of radioactive waste and of natural rock is discussed. Two examples are given of the use of natural rock as an ''analog computer'': one for high-level radioactive waste, and one for low-level radioactive waste. Digital computers have not contributed anything to two crucial questions: Can shafts be securely sealed. Does the heat crack the rock or have important effects on its chemistry. 4 refs

Report for slot cutter proof-of-principle test, Buried Waste Containment System project. Revision 1

International Nuclear Information System (INIS)

1998-01-01

Several million cubic feet of hazardous and radioactive waste was buried in shallow pits and trenches within many US Department of Energy (US DOE) sites. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. Many of the hazardous materials in these waste sites are migrating into groundwater systems through plumes and leaching. On-site containment is one of the options being considered for prevention of waste migration. This report describes the results of a proof-of-principle test conducted to demonstrate technology for containing waste. This proof-of-principle test, conducted at the RAHCO International, Inc., facility in the summer of 1997, evaluated equipment techniques for cutting a horizontal slot beneath an existing waste site. The slot would theoretically be used by complementary equipment designed to place a cement barrier under the waste. The technology evaluated consisted of a slot cutting mechanism, muck handling system, thrust system, and instrumentation. Data were gathered and analyzed to evaluate the performance parameters

Report for slot cutter proof-of-principle test, Buried Waste Containment System project. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-21

Several million cubic feet of hazardous and radioactive waste was buried in shallow pits and trenches within many US Department of Energy (US DOE) sites. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. Many of the hazardous materials in these waste sites are migrating into groundwater systems through plumes and leaching. On-site containment is one of the options being considered for prevention of waste migration. This report describes the results of a proof-of-principle test conducted to demonstrate technology for containing waste. This proof-of-principle test, conducted at the RAHCO International, Inc., facility in the summer of 1997, evaluated equipment techniques for cutting a horizontal slot beneath an existing waste site. The slot would theoretically be used by complementary equipment designed to place a cement barrier under the waste. The technology evaluated consisted of a slot cutting mechanism, muck handling system, thrust system, and instrumentation. Data were gathered and analyzed to evaluate the performance parameters.

In situ grouting of buried transuranic waste with polyacrylamide

International Nuclear Information System (INIS)

Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

1987-01-01

This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs

In situ grouting of buried transuranic waste with polyacrylamide

Energy Technology Data Exchange (ETDEWEB)

Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

1987-01-01

This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs.

Ion beam synthesis of buried single crystal erbium silicide

International Nuclear Information System (INIS)

Golanski, A.; Feenstra, R.; Galloway, M.D.; Park, J.L.; Pennycook, S.J.; Harmon, H.E.; White, C.W.

1990-01-01

High doses (10 16 --10 17 /cm 2 ) of 170 keV Er + were implanted into single-crystal left-angle 111 right-angle Si at implantation temperatures between 350 degree C and 520 degree C. Annealing at 800 degree C in vacuum following the implant, the growth and coalescence of ErSi 2 precipitates leads to a buried single crystalline ErSi 2 layer. This has been studied using Rutherford backscattering/channeling, X-ray diffraction, cross-sectional TEM and resistance versus temperature measurements. Samples implanted at 520 degree C using an Er dose of 7 x 10 16 /cm 2 and thermally annealed were subsequently used as seeds for the mesoepitaxial growth of the buried layer during a second implantation and annealing process. Growth occurs meso-epitaxially along both interfaces through beam induced, defect mediated mobility of Er atoms. The crystalline quality of the ErSi 2 layer strongly depends on the temperature during the second implantation. 12 refs., 4 figs

Effect of embedment ratio on buried pipelines subject to combined loading

Energy Technology Data Exchange (ETDEWEB)

Mahdavi, H. [Memorial Univ. of Newfoundland, St. John' s, NL (Canada); Kenny, S. [Memorial Univ. of Newfoundland, St. John' s, NL (Canada). Faculty of Engineering and Applied Science; Phillips, R. [Memorial Univ. of Newfoundland, St. John' s, NL (Canada). C-Core; Radu Popecsu [Princeton Univ., Princeton, NJ (United States). URS Corp.

2009-07-01

Pipelines along certain route corridors may be subject to long term, large scale ground movement due to accumulated soil deformation such as subsidence, thaw settlement, frost heave, and slope movement. The pipeline may therefore deform, yield, and experience local buckling mechanisms. This study investigated the influence of geotechnical loads and restraint on the local buckling response of buried pipelines. Two soil types were studied, notably stiff clay and dense sand. Three-dimensional continuum modelling procedures were developed, using ABAQUS/Standard, and calibrated against limited physical data on the buckling response of an unpressurized buried pipeline. The influence of soil restraint and embedment ratio (H/D) on the pipeline peak moment capacity, critical strain and ovalization were investigated through a parametric analysis. The study showed that as the H/D ratio increases, the soil failure mechanism changes from passive wedge formation to soil local failure around a pipeline. The contact surface between the pipeline and surrounding soil is influenced by changes in soil failure mechanisms. Therefore, the magnitude and distribution of loads that can be transferred varies. Also the location of the critical section, the factor of ovalization, and the moment-strain relationship of a buried pipeline changes with increasing H/D ratio. 21 refs., 4 tabs.,10 figs.

InGaAsP/InP quantum well buried heterostructure waveguides produced by ion implantation

International Nuclear Information System (INIS)

Zucker, J.E.; Jones, K.L.; Tell, B.; Brown-Goebeler, K.; Joyner, C.H.; Miller, B.I.; Young, M.G.

1992-01-01

Formation of buried InGaAsP/InP quantum well wave-guides by means of phosphorus ion implantation and thermal annealing during regrowth is demonstrated. Absorption spectra of implanted and unimplanted regions are used to estimate the induced index difference, which is of the order of 1% at 1.55μm. Calculated mode intensities are in good agreement with the observed near field intensity patterns. With this etchless implant technique, we achieve a significant reduction in propagation loss for singlemode pin waveguides relative to etched semi-insulating planar buried heterostructure waveguides fabricated from the same quantum well structure. In addition to reduced scattering loss, buried quantum well waveguides produced by ion implantation are more manufacturable because fewer and less-critical processing steps are involved. (author)

Studies of phase formation in CoSi2 buried layers fabricated using ion implantation

International Nuclear Information System (INIS)

Galaev, A.A.; Parkhomenko, Yu.N.; Podgornyi, D.A.; Shcherbachev, K.D.

1998-01-01

The processes of the formation of cobalt disilicide buried layers in silicon are studied under different conditions of implantation with Co. In particular, the effects of the implantation dose and the postimplantation annealing temperature on the state of the Co-implanted layer are considered. Two types of heteroepitaxial Si/CoSi 2 /Si structures are obtained with the conducting layers of thicknesses 70 and 90 nm buried at the depths 80 and 10 nm, respectively

Examination of faults active motion on buried pipelines | Parish ...

African Journals Online (AJOL)

... lateral spreading, landslides and slope failures. Since the pipelines are widely spread, and in some areas necessarily cross through the areas with faults, therefore, improvement study of pipelines in areas with faults is very important. This article explores faults active motion on buried pipelines. Keywords: water utilities ...

DBAC: A simple prediction method for protein binding hot spots based on burial levels and deeply buried atomic contacts

Science.gov (United States)

2011-01-01

Background A protein binding hot spot is a cluster of residues in the interface that are energetically important for the binding of the protein with its interaction partner. Identifying protein binding hot spots can give useful information to protein engineering and drug design, and can also deepen our understanding of protein-protein interaction. These residues are usually buried inside the interface with very low solvent accessible surface area (SASA). Thus SASA is widely used as an outstanding feature in hot spot prediction by many computational methods. However, SASA is not capable of distinguishing slightly buried residues, of which most are non hot spots, and deeply buried ones that are usually inside a hot spot. Results We propose a new descriptor called “burial level” for characterizing residues, atoms and atomic contacts. Specifically, burial level captures the depth the residues are buried. We identify different kinds of deeply buried atomic contacts (DBAC) at different burial levels that are directly broken in alanine substitution. We use their numbers as input for SVM to classify between hot spot or non hot spot residues. We achieve F measure of 0.6237 under the leave-one-out cross-validation on a data set containing 258 mutations. This performance is better than other computational methods. Conclusions Our results show that hot spot residues tend to be deeply buried in the interface, not just having a low SASA value. This indicates that a high burial level is not only a necessary but also a more sufficient condition than a low SASA for a residue to be a hot spot residue. We find that those deeply buried atoms become increasingly more important when their burial levels rise up. This work also confirms the contribution of deeply buried interfacial atomic contacts to the energy of protein binding hot spot. PMID:21689480

Testing MODFLOW-LGR for simulating flow around Buried Quaternary valleys - synthetic test cases

DEFF Research Database (Denmark)

Vilhelmsen, Troels Norvin; Christensen, Steen

In Denmark the water supply is entirely based on ground water. In some parts of the country these resources are found in buried quaternary tunnel valleys. Intensive mapping has shown that the valleys typically have a complex internal hydrogeology with multiple cut and ­fill structures....... The administration of groundwater resources has been based on simulations using regional scale groundwater models. However, regional scale models have difficulties with accurately resolving the complex geology of the buried valleys, which bears the risk of poor model predictions of local scale effects of groundwater...

Geophysical research results of buried relief and distribution groundwater runoff of the Aragats massif

OpenAIRE

V.P. Vardanyan; A.H. Hovhannisyan

2017-01-01

Based on the synthesis and reinterpretation of long-term data of geophysical studies together with the hydrology - hydrological materials it has been received new data about the buried topography and spatial distribution of groundwater runoff of the Aragats massif. First of all, it requires to determine the structure of its buried relief, which is basically a regional relief aquitard. The underground water sources are considered to be precipitation on the massif (approximately 83% of the tota...

Implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bullock, M.G.; Rodriguez, R.R.

1987-05-01

This document presents the current implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory. Information contained in this report was also included in several Department of Energy (DOE) planning documents for the Defense Transuranic Waste Program. This information can be found in the following DOE documents: Comprehensive Implementation Plan for the DOE Defense Buried TRU Waste Program; Defense Waste Management Plan for Buried Transuranic-Contaminated Waste, Transuranic-Contaminated Waste, Transuranic-Contaminated Soil, and Difficult-to-Certify Transuranic Waste; and Defense Special-Case Transuranic Waste Implementation Plan. 11 refs

3D Imaging of Dielectric Objects Buried under a Rough Surface by Using CSI

Directory of Open Access Journals (Sweden)

Evrim Tetik

2015-01-01

Full Text Available A 3D scalar electromagnetic imaging of dielectric objects buried under a rough surface is presented. The problem has been treated as a 3D scalar problem for computational simplicity as a first step to the 3D vector problem. The complexity of the background in which the object is buried is simplified by obtaining Green’s function of its background, which consists of two homogeneous half-spaces, and a rough interface between them, by using Buried Object Approach (BOA. Green’s function of the two-part space with planar interface is obtained to be used in the process. Reconstruction of the location, shape, and constitutive parameters of the objects is achieved by Contrast Source Inversion (CSI method with conjugate gradient. The scattered field data that is used in the inverse problem is obtained via both Method of Moments (MoM and Comsol Multiphysics pressure acoustics model.

Generation and confinement of mobile charges in buried oxide of SOI substrates

International Nuclear Information System (INIS)

Gruber, O.; Krawiec, S.; Musseau, O.; Paillet, Ph.; Courtot-Descharles, A.

1999-01-01

We analyze the mechanisms of generation and confinement of mobile protons resulting from hydrogen annealing of SOI buried oxides. This study of the mechanisms of generation and confinement of mobile protons in the buried oxide of SOI wafers emphasizes the importance of H+ diffusion in the oxide in the formation of a mobile charge. Under specific electric field conditions the irradiation of these devices results in a pinning of this mobile charge at the bottom Si-SiO 2 interface. Ab initio calculations are in progress to investigate the possible precursor defects in the oxide and detail the mechanism for mobile proton generation and confinement. (authors)

77 FR 14446 - Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, “Buried and...

Science.gov (United States)

2012-03-09

...) Report Revision 2 AMP XI.M41, ``Buried and Underground Piping and Tanks'' AGENCY: Nuclear Regulatory...), LR- ISG-2011-03, ``Changes to GALL Report Revision 2 Aging Management Program (AMP) XI.M41, `Buried... Report Revision 2 AMP XI.M41 based on the staff's review of several license renewal applications' buried...

Exploring interface morphology of a deeply buried layer in periodic multilayer

Energy Technology Data Exchange (ETDEWEB)

Das, Gangadhar; Srivastava, A. K.; Tiwari, M. K., E-mail: mktiwari@rrcat.gov.in [Indus Synchrotrons Utilization Division, Raja Ramanna Centre for Advanced Technology, Indore-452013, Madhya Pradesh (India); Homi Bhabha National Institute, Anushaktinagar, Mumbai-400094, Maharashtra (India); Khooha, Ajay; Singh, A. K. [Indus Synchrotrons Utilization Division, Raja Ramanna Centre for Advanced Technology, Indore-452013, Madhya Pradesh (India)

2016-06-27

Long-term durability of a thin film device is strongly correlated with the nature of interface structure associated between different constituent layers. Synthetic periodic multilayer structures are primarily employed as artificial X-ray Bragg reflectors in many applications, and their reflection efficiency is predominantly dictated by the nature of the buried interfaces between the different layers. Herein, we demonstrate the applicability of the combined analysis approach of the X-ray reflectivity and grazing incidence X-ray fluorescence measurements for the reliable and precise determination of a buried interface structure inside periodic X-ray multilayer structures. X-ray standing wave field (XSW) generated under Bragg reflection condition is used to probe the different constituent layers of the W- B{sub 4}C multilayer structure at 10 keV and 12 keV incident X-ray energies. Our results show that the XSW assisted fluorescence measurements are markedly sensitive to the location and interface morphology of a buried layer structure inside a periodic multilayer structure. The cross sectional transmission electron microscopy results obtained on the W-B{sub 4}C multilayer structure provide a deeper look on the overall reliability and accuracy of the XSW method. The method described here would also be applicable for nondestructive characterization of a wide range of thin film based semiconductor and optical devices.

Modeling of Buried Wire Detection by Radio-Frequency Electromagnetic Waves

NARCIS (Netherlands)

Naus, H.W.L.

2013-01-01

The detection of buried insulated wires of finite length with a transmitter–receiver electromagnetic induction sensor is theoretically investigated. The transmitter is modeled as a magnetic dipole. Its electric field induces a current in the cable. Analytical results for its Fourier transform are

Analysis of buried interfaces in multilayer device structures with hard XPS (HAXPES) using a CrKα source

DEFF Research Database (Denmark)

Renault, O.; Martinez, E.; Zborowski, C.

2018-01-01

Applications of laboratory hard X-ray photoelectron spectroscopy on buried interfaces in devices are presented. We use a novel spectrometer fitted with a monochromated CrKα source (photon energy: 5414.9 eV) and a high-voltage analyzer. Elements buried at depths as deep as 25 nm underneath various...

Continuum soil modeling in the static analysis of buried structures

International Nuclear Information System (INIS)

Julyk, L.J.; Marlow, R.S.; Moore, C.J.; Day, J.P.; Dyrness, A.D.

1993-10-01

Soil loading traditionally has been modeled as a hydrostatic pressure, a practice acceptable for many design applications. In the analyses of buried structure with predictive goals, soil compliance and load redistribution in the presence of soil plasticity are important factors to consider in determining the appropriate response of the structure. In the analysis of existing buried waste-storage tanks at the US Department of Energy's Hanford Site, three soil-tank interaction modeling considerations are addressed. First, the soil interacts with the tank as the tank expands and contracts during thermal cycles associated with changes in the heat generated by the waste material as a result of additions and subtractions of the waste. Second, the soil transfers loads from the surface to the tank and provides support by resisting radial displacement of the tank haunch. Third, conventional finite-element mesh development causes artificial stress concentrations in the soil associated with differential settlement

Buried waste integrated demonstration Fiscal Year 1993 close-out report

International Nuclear Information System (INIS)

Owens, K.J.; Hyde, R.A.

1994-04-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the U.S. Department of Energy Environmental Restoration and Waste Management needs and objectives. BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Office of Technology Development initiated BWID at the Idaho National Engineering Laboratory. This report summarizes the activities of the BWID program during FY-93

In situ vitrification program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Loehr, C.A.; Merrill, S.K.

1991-01-01

A program to demonstrate the viability of in situ vitrification (ISV) technology in remediating a buried mixed transuranic (TRU) waste site is under way at the Idaho National Engineering Laboratory (INEL). The application of the technology to buried waste is being evaluated as part of a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) feasibility study. The ISV thermal treatment process converts contaminated soil into a chemically inert and stable glass and crystalline product. The process uses joule heating, accomplished by applying electric potential to electrodes that are placed in the soil to initiate and maintain soil melting. Organic contaminants in the soil are destroyed or removed while inorganic contaminants, including radionuclides, are incorporated into the stable, glass-like product or volatilized. Off-gases are collected in a confinement hood over the melt area and processed through an off-gas treatment system. The paper illustrates and describes the ISV process

Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1994-04-01

This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration's remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for 90 Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs

Soil Sampling Plan for the transuranic storage area soil overburden and final report: Soil overburden sampling at the RWMC transuranic storage area

International Nuclear Information System (INIS)

Stanisich, S.N.

1994-12-01

This Soil Sampling Plan (SSP) has been developed to provide detailed procedural guidance for field sampling and chemical and radionuclide analysis of selected areas of soil covering waste stored at the Transuranic Storage Area (TSA) at the Idaho National Engineering Laboratory's (INEL) Radioactive Waste Management Complex (RWMC). The format and content of this SSP represents a complimentary hybrid of INEL Waste Management--Environmental Restoration Program, and Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Remedial Investigation/Feasibility Study (RI/FS) sampling guidance documentation. This sampling plan also functions as a Quality Assurance Project Plan (QAPP). The QAPP as a controlling mechanism during sampling to ensure that all data collected are valid, reliabile, and defensible. This document outlines organization, objectives and quality assurance/quality control (QA/QC) activities to achieve the desired data quality goals. The QA/QC requirements for this project are outlined in the Data Collection Quality Assurance Plan (DCQAP) for the Buried Waste Program. The DCQAP is a program plan and does not outline the site specific requirements for the scope of work covered by this SSP

Preliminary Systems Design Study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1992-01-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept. This volume of the Systems Design Study contain four Appendixes that were part of the study. Appendix A is an EG ampersand G Idaho, Inc., report that represents a review and compilation of previous reports describing the wastes and quantities disposed in the Subsurface Disposal Area of the Idaho National Engineering Laboratory. Appendix B contains the process flowsheets considered in this study, but not selected for detailed analysis. Appendix C is a historical tabulation of radioactive waste incinerators. Appendix D lists Department of Energy facilities where cementation stabilization systems have been used

Preliminary Systems Design Study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1992-01-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques for the remediation of hazardous and transuranic waste stored at Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept. This volume contains introduction section containing a brief SDS background and lists the general assumptions and considerations used during the development of the system concepts. The introduction section is followed by sections describing two system concepts that produce a waste form in compliance with the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) and transportation package (TRAMPAC) requirements. This system concept category is referred to as Waste Form 4, ''WIPP and TRAMPAC Acceptable.'' The following two system concepts are under this category: Sort, Treat, and Repackage System (4-BE-2); Volume Reduction and Packaging System (4-BE-4)

Effect of Pseudomonas fluorescens on Buried Steel Pipeline Corrosion.

Science.gov (United States)

Spark, Amy J; Law, David W; Ward, Liam P; Cole, Ivan S; Best, Adam S

2017-08-01

Buried steel infrastructure can be a source of iron ions for bacterial species, leading to microbiologically influenced corrosion (MIC). Localized corrosion of pipelines due to MIC is one of the key failure mechanisms of buried steel pipelines. In order to better understand the mechanisms of localized corrosion in soil, semisolid agar has been developed as an analogue for soil. Here, Pseudomonas fluorescens has been introduced to the system to understand how bacteria interact with steel. Through electrochemical testing including open circuit potentials, potentiodynamic scans, anodic potential holds, and electrochemical impedance spectroscopy it has been shown that P. fluorescens increases the rate of corrosion. Time for oxide and biofilms to develop was shown to not impact on the rate of corrosion but did alter the consistency of biofilm present and the viability of P. fluorescens following electrochemical testing. The proposed mechanism for increased corrosion rates of carbon steel involves the interactions of pyoverdine with the steel, preventing the formation of a cohesive passive layer, after initial cell attachment, followed by the formation of a metal concentration gradient on the steel surface.

Coherent light scattering from a buried dipole in a high-aperture optical system

International Nuclear Information System (INIS)

Vamivakas, A N; Mueller, T; Atatuere, M; Yurt, A; Koeklue, F H; Uenlue, M S

2011-01-01

We develop a theoretical formulation to calculate the absolute and differential transmission of a focused laser beam through a high-aperture optical system. The focused field interacts with a point dipole that is buried in a high-index material, and is situated at the Gaussian focus of the focusing and collection two-lens system. The derived expressions account for the vectorial nature of the focused electromagnetic field and the inhomogeneous focal region environment. The results obtained are in agreement with recent resonant light-scattering experiments where the buried emitter is an indium arsenide semiconductor quantum dot in gallium arsenide.

Influence of oxygen on the ion-beam synthesis of silicon carbide buried layers in silicon

International Nuclear Information System (INIS)

Artamanov, V.V.; Valakh, M.Ya.; Klyui, N.I.; Mel'nik, V.P.; Romanyuk, A.B.; Romanyuk, B.N.; Yukhimchuk, V.A.

1998-01-01

The properties of silicon structures with silicon carbide (SiC) buried layers produced by high-dose carbon implantation followed by a high-temperature anneal are investigated by Raman and infrared spectroscopy. The influence of the coimplantation of oxygen on the features of SiC buried layer formation is also studied. It is shown that in identical implantation and post-implantation annealing regimes a SiC buried layer forms more efficiently in CZ Si wafers or in Si (CZ or FZ) subjected to the coimplantation of oxygen. Thus, oxygen promotes SiC layer formation as a result of the formation of SiO x precipitates and accommodation of the volume change in the region where the SiC phase forms. Carbon segregation and the formation of an amorphous carbon film on the SiC grain boundaries are also discovered

Lateral uniformity in chemical composition along a buried reaction front in polymers using off-specular reflectivity

International Nuclear Information System (INIS)

Lavery, Kristopher A; Prabhu, Vivek M; Wu Wenli; Satija, Sushil

2010-01-01

Off-specular neutron reflectometry was applied to characterize the form and amplitude of lateral compositional variations at a buried reaction-diffusion front. In this work, off-specular neutron measurements were first calibrated using off-specular x-ray reflectivity and atomic force microscopy via a roughened glass surface, both as a free surface and as a buried interface that was prepared by spin coating thin polymer films upon the glass surface. All three methods provided consistent roughness values despite the difference in their detection mechanism. Our neutron results demonstrated, for the first time, that the compositional heterogeneity at a buried reaction front can be measured; the model system used in this study mimics the deprotection reaction that occurs during the photolithographic process necessary for manufacturing integrated circuits.

Lateral uniformity in chemical composition along a buried reaction front in polymers using off-specular reflectivity.

Science.gov (United States)

Lavery, Kristopher A; Prabhu, Vivek M; Satija, Sushil; Wu, Wen-Li

2010-12-01

Off-specular neutron reflectometry was applied to characterize the form and amplitude of lateral compositional variations at a buried reaction-diffusion front. In this work, off-specular neutron measurements were first calibrated using off-specular x-ray reflectivity and atomic force microscopy via a roughened glass surface, both as a free surface and as a buried interface that was prepared by spin coating thin polymer films upon the glass surface. All three methods provided consistent roughness values despite the difference in their detection mechanism. Our neutron results demonstrated, for the first time, that the compositional heterogeneity at a buried reaction front can be measured; the model system used in this study mimics the deprotection reaction that occurs during the photolithographic process necessary for manufacturing integrated circuits.

a Uav Based 3-D Positioning Framework for Detecting Locations of Buried Persons in Collapsed Disaster Area

Science.gov (United States)

Moon, H.; Kim, C.; Lee, W.

2016-06-01

Regarding spatial location positioning, indoor location positioning theories based on wireless communication techniques such as Wi-Fi, beacon, UWB and Bluetooth has widely been developing across the world. These techniques are mainly focusing on spatial location detection of customers using fixed wireless APs and unique Tags in the indoor environment. Besides, since existing detection equipment and techniques using ultrasound or sound etc. to detect buried persons and identify survival status for them cause 2nd damages on the collapsed debris for rescuers. In addition, it might take time to check the buried persons. However, the collapsed disaster sites should consider both outdoor and indoor environments because empty spaces under collapsed debris exists. In order to detect buried persons from the empty spaces, we should collect wireless signals with Wi-Fi from their mobile phone. Basically, the Wi-Fi signal measure 2-D location. However, since the buried persons have Z value with burial depth, we also should collect barometer sensor data from their mobile phones in order to measure Z values according to weather conditions. Specially, for quick accessibility to the disaster area, a drone (UAV; Unmanned Arial Vehicle) system, which is equipped with a wireless detection module, was introduced. Using these framework, this study aims to provide the rescuers with effective rescue information by calculating 3-D location for buried persons based on the wireless and barometer sensor fusion.

Buried aquifers in the Brooten-Belgrade and Lake Emily areas, west-central Minnesota--Factors related to developing water for irrigation

Science.gov (United States)

Wolf, R.J.

1976-01-01

Irrigation has given a substantial boost to the economy in the Brooten-Belgrade and Lake Emily areas of Minnesota. The surficial outwash aquifer is capable of yielding sufficient quantities of water for irrigation over half of its area; the remaining part may be supplied by deep aquifers. Buried glacial outwash and Cretaceous sand aquifers, as thick as 50 feet occur to depths of 300 feet. In places, the buried aquifers are sufficiently thick and permeable to yield large quantities of water to wells. The buried aquifers are probably narrow, elongate, truncated bodies enclosed by clay till. The Precambrian surface, ranging from 190 to 350 feet below the land surface, is the lower limit of the buried aquifers.

Application of EM tomography to detect a buried pipe; EM tomography no maisetsukan tansa eno tekiyorei

Energy Technology Data Exchange (ETDEWEB)

Sakashita, S [OYO Corp., Tokyo (Japan)

1996-10-01

EM tomography was applied to detect buried pipes. Underground radar exploration method is limited to 10m in depth. Positive use of bored holes is desirable, and in such case, magnetic logging based on the magnetic susceptibility (MS) contrast between buried body and surrounding ground is effective. The primary magnetic field is generated by coil current, and the secondary one is generated by the primary one responding to foreign bodies in the ground. Since the measured primary magnetic field of low frequency within 10Hz can be treated as static magnetic field responding to MS in the ground, it is useful to determine MS distributions. Since the measured magnetic field of high frequency within 100kHz can be treated as induction field responding to conductivity in the ground, it is useful to determine resistivity distributions. The EM tomography which can image both above distributions by using electromagnetic wave in a wide frequency range, was applied to detect buried pipes. The EM tomography could detect an buried foreign body of 3m in diameter at 10m in distance between bored holes. The theoretical equation for analysis was also derived. 5 refs., 9 figs., 1 tab.

Optical evidence for a self-propagating molten buried layer in germanium films upon nanosecond laser irradiation

International Nuclear Information System (INIS)

Vega, F.; Chaoui, N.; Solis, J.; Armengol, J.; Afonso, C.N.

2005-01-01

This work describes the phase transitions occurring at the film-substrate interface of amorphous germanium films upon nanosecond laser-pulse-induced melting of the surface. Films with thickness ranging from 50 to 130 nm deposited on glass substrates were studied. Real-time reflectivity measurements with subnanosecond time resolution performed both at the air-film and film-substrate interfaces were used to obtain both surface and in-depth information of the process. In the thicker films (≥80 nm), the enthalpy released upon solidification of a shallow molten surface layer induces a thin buried liquid layer that self-propagates in-depth towards the film-substrate interface. This buried liquid layer propagates with a threshold velocity of 16±1 m/s and causes, eventually, melting at the film-substrate interface. In the thinnest film (50 nm) there is no evidence of the formation of the buried layer. The presence of the self-propagating buried layer for films thicker than 80 nm at low and intermediate laser fluences is discussed in terms of the thermal gradient in the primary melt front and the heat released upon solidification

Dynamic model of open shell structures buried in poroelastic soils

Science.gov (United States)

Bordón, J. D. R.; Aznárez, J. J.; Maeso, O.

2017-08-01

This paper is concerned with a three-dimensional time harmonic model of open shell structures buried in poroelastic soils. It combines the dual boundary element method (DBEM) for treating the soil and shell finite elements for modelling the structure, leading to a simple and efficient representation of buried open shell structures. A new fully regularised hypersingular boundary integral equation (HBIE) has been developed to this aim, which is then used to build the pair of dual BIEs necessary to formulate the DBEM for Biot poroelasticity. The new regularised HBIE is validated against a problem with analytical solution. The model is used in a wave diffraction problem in order to show its effectiveness. It offers excellent agreement for length to thickness ratios greater than 10, and relatively coarse meshes. The model is also applied to the calculation of impedances of bucket foundations. It is found that all impedances except the torsional one depend considerably on hydraulic conductivity within the typical frequency range of interest of offshore wind turbines.

Buried Waste Integrated Demonstration fiscal Year 1994 close-out report

International Nuclear Information System (INIS)

Owen, K.J.

1995-07-01

The Buried Waste integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a multitude of advanced technologies. These technologies are being integrated to form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy Environmental Restoration and Waste Management needs and objectives. BWID works with universities and private industry to develop these technologies, which are being transferred to the private sector for use nationally and internationally. A public participation policy has been established to provide stakeholders with timely and accurate information and meaningful opportunities for involvement in the technology development and demonstration process. To accomplish this mission of identifying technological solutions for remediation deficiencies, the Department of Energy Office of Technology Development initiated BMD at the Idaho National Engineering Laboratory. This report summarizes the activities of the BWID program during Fiscal Year 1994. In Fiscal Year 1995, these activities are transitioning into the Landfill Stabilization Focus Area

Thermal processing systems for TRU mixed waste

International Nuclear Information System (INIS)

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-01-01

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended

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

International Nuclear Information System (INIS)

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

1995-09-01

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

Facility status and progress of the INEL's WERF MLLW and LLW incinerator

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

Field investigation on structural performance of the buried UPVC pipes with and without geogrid reinforcement

Science.gov (United States)

Teja, Akkineni Surya; Rajkumar, R.; Gokula Krishnan, B.; Aravindh, R.

2018-02-01

Buried pipes are used mainly for water supply and drainage besides many other applications such as oil, liquefied natural gas, coal slurries and mine tailings. The pipes used may be rigid (reinforced concrete, vitrified clay and ductile iron) or flexible (Steel, UPVC, aluminium, Fiber glass and High-density polyethylene) although the distinction between them is blurring. Flexible pipe design is governed by deflection or buckling. UPVC pipes are preferred due to light weight, long term chemical stability and cost efficiency. This project aims to study the load deformation behaviour of the buried pipe and stress variation across the cross section of the pipe under static loading along with the influence of depth of embedment, density of backfill on the deformation and stresses in pipe and the deformation behaviour of buried pipe when soil is reinforced with geogrid reinforcement and evaluate the structural performance of the pipe.

Incidence of Treatment for Infection of Buried Versus Exposed Kirschner Wires in Phalangeal, Metacarpal, and Distal Radial Fractures.

Science.gov (United States)

Ridley, Taylor J; Freking, Will; Erickson, Lauren O; Ward, Christina Marie

2017-07-01

To determine whether there is a difference in the incidence of infection between exposed and buried K-wires when used to treat phalangeal, metacarpal, and distal radius fractures. We conducted a retrospective review identifying all patients aged greater than 16 years who underwent fixation of phalangeal, metacarpal, or distal radius fractures with K-wires between 2007 and 2015. We recorded patient demographic data, fracture location, number of K-wires used, whether K-wires were buried or left exposed, and duration of K-wire placement. A total of 695 patients met inclusion criteria. Surgeons buried K-wires in 207 patients and left K-wires exposed in 488. Infections occurred more frequently in exposed K-wire cases than in buried K-wire ones. Subgroup analysis based on fracture location revealed a significantly increased risk of being treated for infection when exposed K-wires were used for metacarpal fractures. Patients with exposed K-wires for fixation of phalangeal, metacarpal, or distal radius fractures were more likely to be treated for a pin-site infection than those with K-wires buried beneath the skin. Metacarpal fractures treated with exposed K-wires were 2 times more likely to be treated for a pin-site infection (17.6% of exposed K wire cases vs 8.7% of buried K wire cases). Therapeutic IV. Copyright © 2017 American Society for Surgery of the Hand. Published by Elsevier Inc. All rights reserved.

In situ vitrification application to buried waste: Final report of intermediate field tests at Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Callow, R.A.; Weidner, J.R.; Loehr, C.A.; Bates, S.O.; Thompson, L.E.; McGrail, B.P.

1991-08-01

This report describes two in situ vitrification field tests conducted on simulated buried waste pits during June and July 1990 at the Idaho National Engineering Laboratory. In situ vitrification, an emerging technology for in place conversion of contaminated soils into a durable glass and crystalline waste form, is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to access the general suitability of the process to remediate waste structures representative of buried waste found at Idaho National Engineering Laboratory. In particular, these tests, as part of a treatability study, were designed to provide essential information on the field performance of the process under conditions of significant combustible and metal wastes and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology successfully processed the high metal content waste. Test results indicate the process is a feasible technology for application to buried waste. 33 refs., 109 figs., 39 tabs

Experimental effects of immersion time and water temperature on body condition, burying depth and timing of spawning of the tellinid bivalve Macoma balthica

Science.gov (United States)

de Goeij, Petra; Honkoop, Pieter J.

2003-03-01

The burying depth of many bivalve molluscs on intertidal mudflats varies throughout the year and differs between places. Many factors are known to influence burying depth on a seasonal or spatial scale, with temperature and tidal regime probably being very important. Burying depth, body condition and gonadal development of Macoma balthica were followed throughout winter and spring in an experiment in which water temperature and immersion time were manipulated. Unexpectedly, relative water temperature, in contrast to the prediction, did not generally affect body condition or burying depth. This was probably a consequence of the exceptionally overall low water temperatures during the experimental winter. Differences in temperature did, however, result in different timing of spawning: M. balthica spawned earlier at higher spring temperatures. Longer immersion times led to higher body condition only late in spring, but led to deeper burying throughout almost the whole period. There was no effect of immersion time on the timing of spawning. We conclude that a longer immersion time leads to deeper burying, independent of body condition. We also conclude that burying behaviour of M. balthica is not determined by the moment of spawning.

Noise characteristics of resistors buried in low-temperature co-fired ceramics

International Nuclear Information System (INIS)

Kolek, A; Ptak, P; Dziedzic, A

2003-01-01

The comparison of noise properties of conventional thick film resistors prepared on alumina substrates and resistors embedded in low-temperature co-fired ceramics (LTCCs) is presented. Both types of resistors were prepared from commercially available resistive inks. Noise measurements of LTCC resistors below 1 kHz show Gaussian 1/f noise. This is concluded from the calculations of the second spectra as well as from studying the volume dependence of noise intensity. It has occurred that noise index of LTCC resistors on average is not worse than that of conventional resistors. A detailed study of co-fired surface resistors and co-fired buried resistors show that burying a resistor within LTCC substrate usually leads to (significant) enhancement of resistance but not of noise intensity. We interpret this behaviour as another argument in favour of tunnelling as the dominant conduction mechanism in LTCC resistors

Infectivity of Trichinella spiralis larvae in pork buried in the ground

Directory of Open Access Journals (Sweden)

Jovic S.

2001-06-01

Full Text Available Time of survival and infectivity of Trichinella spiralis larvae in pig muscle tissue, buried at various depths in the ground were assessed. In the pork pieces the number of infective larvae was 250 ML/g. Meat originated from pig halves was divided in 39 equal pieces, 0.7 kg each, disposed in three groups of 1 3, and buried in depths of 30, 50, and 100 centimeters respectively. The pork was dug up at 13 intervals, approximately every week, until 91st day of the experiment. After each time interval, infectivity of larvae was assessed by bioassay on rats. The artificially infected rats were sacrificed on 42nd day after the infection and meat was examined by the following methods - artificial digestion and trichinoscopy. It was found that the larvae during all 90 days preserved infectivity in each depth.

[The taphonomic aspects of cadaverous changes in corpses, buried in the plastic foils].

Science.gov (United States)

Stuller, F; Straka, L; Macko, V; Krivos, D; Krajcovic, J; Novomeský, F

2008-10-01

The forensic expertise of the 6 human bodies, being murdered in organised crime activities, had been realised by the authors. All the cadavers were packed in plastic bags or plastic foils, then buried to the illegal graves, being prepared in advance. The detail overlook and autopsy of the bodies had disclosed, that due of almost airtight sealing of the cadavers in plastic materials, the postmortal cadaverous changes went on much slower and were manifested under a different picture, as seen in the human cadavers being buried in the standard wooden coffins. The authors point out the peculiarities of such a postmortal changes, with particular focusing on the estimation of postmortal period.

A leak-detection instrument for long buried pipelines based on radioactive tracer measurements

International Nuclear Information System (INIS)

Lu Qingqian; Zhou Shuxuan; Tang Yonghua; Sun Xiaolei; Hu Xusheng; Li Deyi; Yin Liqiang

1987-01-01

The instrument introduced provides a means for leak detection of long buried pipelines based on the radioactive tracer technique. The principle, block diagram and performances for the instrument are described. The leak-detecting method and the determination of some related parameters are also presented. Leak-detection sensitivity of the instrument is 185 kBq (5 μCi). Accuracy for leak localization is within 2.5 m (per km). It is suitable for the buried light oil (gasoline, kerosene, diesel oil) and industrial water pipelines with a diameter of 15 or 20 cm. The detection length for a single operation reaches up to 50 km

Stabilization of ancient organic matter in deep buried paleosols

Science.gov (United States)

Marin-Spiotta, E.; Chaopricha, N. T.; Mueller, C.; Diefendorf, A. F.; Plante, A. F.; Grandy, S.; Mason, J. A.

2012-12-01

Buried soils representing ancient surface horizons can contain large organic carbon reservoirs that may interact with the atmosphere if exposed by erosion, road construction, or strip mining. Paleosols in long-term depositional sites provide a unique opportunity for studying the importance of different mechanisms on the persistence of organic matter (OM) over millennial time-scales. We report on the chemistry and bioavailability of OM stored in the Brady soil, a deeply buried (7 m) paleosol in loess deposits of southwestern Nebraska, USA. The Brady Soil developed 9,000-13,500 years ago during a time of warming and drying. The Brady soil represents a dark brown horizon enriched in C relative to loess immediately above and below. Spanning much of the central Great Plains, this buried soil contains large C stocks due to the thickness of its A horizon (0.5 to 1 m) and wide geographic extent. Our research provides a unique perspective on long-term OM stabilization in deep soils using multiple analytical approaches. Soils were collected from the Brady soil A horizon (at 7 m depth) and modern surface A horizons (0-15 cm) at two sites for comparison. Soils were separated by density fractionation using 1.85 g ml-1 sodium polytungstate into: free particulate organic matter (fPOM) and aggregate-occluded (oPOM) of two size classes (large: >20 μm, and small: separated into sand, silt, and clay size fractions. The distribution and age of C among density and particle-size fractions differed between surface and Brady soils. We isolated the source of the characteristic dark coloring of the Brady soil to the oPOM-small fraction, which also contained 20% of the total organic C pool in the Brady soil. The oPOM-small fraction and the bulk soil in the middle of the Brady A horizon had 14C ages of 10,500-12,400 cal yr BP, within the time that the soil was actively forming at the land surface. Surface soils showed modern ages. Lipid analyses of the Brady soil indicate a predominance of

Exhumation of radioactive solid wastes buried for fourteen years

International Nuclear Information System (INIS)

Horton, J.H.

1977-03-01

Twenty-five linear feet of a low-level beta-gamma waste trench was excavated fourteen years after the waste was buried. The waste included wood, steel, plastics, cotton cloth, rubber, and paper. Cardboard boxes not enclosed in plastic were the only materials to deteriorate visibly. Apparently, decades would be required for all cellulose materials to decompose, and plastics and metals would survive indefinitely

Scattering from a Buried Circular Cylinder Illuminated by a Three-Dimensional Source

DEFF Research Database (Denmark)

Hansen, T.B.; Meincke, Peter

2002-01-01

We employ plane and cylindrical wave expansions with the fast Fourier transform to solve scattering problems involving a circular cylinder buried in soil. The illumination is provided by a three-dimensional source located in air above ground. Plane wave expansions describe transmitted and reflect...... commonly used transmitter-receiver configuration for ground-penetrating radar (GPR). Numerical simulations involving time domain fields and fixed-offset configurations determine the radar responses of various types of pipes and conductive soils encountered in GPR.......We employ plane and cylindrical wave expansions with the fast Fourier transform to solve scattering problems involving a circular cylinder buried in soil. The illumination is provided by a three-dimensional source located in air above ground. Plane wave expansions describe transmitted and reflected...

Graphite electrode arc melter demonstration Phase 2 test results

Energy Technology Data Exchange (ETDEWEB)

Soelberg, N.R.; Chambers, A.G.; Anderson, G.L.; O`Connor, W.K.; Oden, L.L.; Turner, P.C.

1996-06-01

Several U.S. Department of Energy organizations and the U.S. Bureau of Mines have been collaboratively conducting mixed waste treatment process demonstration testing on the near full-scale graphite electrode submerged arc melter system at the Bureau`s Albany (Oregon) Research Center. An initial test series successfully demonstrated arc melter capability for treating surrogate incinerator ash of buried mixed wastes with soil. The conceptual treatment process for that test series assumed that buried waste would be retrieved and incinerated, and that the incinerator ash would be vitrified in an arc melter. This report presents results from a recently completed second series of tests, undertaken to determine the ability of the arc melter system to stably process a wide range of {open_quotes}as-received{close_quotes} heterogeneous solid mixed wastes containing high levels of organics, representative of the wastes buried and stored at the Idaho National Engineering Laboratory (INEL). The Phase 2 demonstration test results indicate that an arc melter system is capable of directly processing these wastes and could enable elimination of an up-front incineration step in the conceptual treatment process.

A UAV BASED 3-D POSITIONING FRAMEWORK FOR DETECTING LOCATIONS OF BURIED PERSONS IN COLLAPSED DISASTER AREA

Directory of Open Access Journals (Sweden)

H. Moon

2016-06-01

Full Text Available Regarding spatial location positioning, indoor location positioning theories based on wireless communication techniques such as Wi-Fi, beacon, UWB and Bluetooth has widely been developing across the world. These techniques are mainly focusing on spatial location detection of customers using fixed wireless APs and unique Tags in the indoor environment. Besides, since existing detection equipment and techniques using ultrasound or sound etc. to detect buried persons and identify survival status for them cause 2nd damages on the collapsed debris for rescuers. In addition, it might take time to check the buried persons. However, the collapsed disaster sites should consider both outdoor and indoor environments because empty spaces under collapsed debris exists. In order to detect buried persons from the empty spaces, we should collect wireless signals with Wi-Fi from their mobile phone. Basically, the Wi-Fi signal measure 2-D location. However, since the buried persons have Z value with burial depth, we also should collect barometer sensor data from their mobile phones in order to measure Z values according to weather conditions. Specially, for quick accessibility to the disaster area, a drone (UAV; Unmanned Arial Vehicle system, which is equipped with a wireless detection module, was introduced. Using these framework, this study aims to provide the rescuers with effective rescue information by calculating 3-D location for buried persons based on the wireless and barometer sensor fusion.

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Sections 1 through 8, Tables 2-1 through 6-1, Figures 1 and 2

International Nuclear Information System (INIS)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE's mixed waste

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Tables 8.1 and 8.2, Appendices A, B, C

International Nuclear Information System (INIS)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE's mixed waste

Idaho National Engineering Laboratory Conceptual Site Treatment Plan. Tables 8.1 and 8.2, Appendices A, B, C

Energy Technology Data Exchange (ETDEWEB)

Eaton, D.

1993-10-01

The US Department of Energy (DOE) is required by Section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (FFCAct), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The FFCAct requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the host state or the US Environmental Protection Agency (EPA) for either approval, approval with modification, or disapproval. The Idaho National Engineering Laboratory (INEL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the FFCAct and is being provided to the State of Idaho, the EPA, and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix A of this document. In addition to aiding the INEL in formulating its Final Proposed STP, this CSTP will also provide information to other DOE sites for use in identifying common technology needs and potential options for treating their wastes. The INEL CSTP is also intended to be used in conjunction with CSTPs from other sites as a basis for nationwide discussions among state regulators, the EPA, and other interested parties on treatment strategies and options, and on technical and equity issues associated with DOE`s mixed waste.

Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

International Nuclear Information System (INIS)

Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

1993-08-01

Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

CMOS-compatible method for doping of buried vertical polysilicon structures by solid phase diffusion

Energy Technology Data Exchange (ETDEWEB)

Turkulets, Yury [Micron Semiconductor Israel Ltd., Qiryat Gat 82109 (Israel); Department of Electrical and Computer Engineering, Ben Gurion University of the Negev, Beer-Sheva 8410501 (Israel); Silber, Amir; Ripp, Alexander; Sokolovsky, Mark [Micron Semiconductor Israel Ltd., Qiryat Gat 82109 (Israel); Shalish, Ilan, E-mail: shalish@bgu.ac.il [Department of Electrical and Computer Engineering, Ben Gurion University of the Negev, Beer-Sheva 8410501 (Israel)

2016-03-28

Polysilicon receives attention nowadays as a means to incorporate 3D-structured photonic devices into silicon processes. However, doping of buried layers of a typical 3D structure has been a challenge. We present a method for doping of buried polysilicon layers by solid phase diffusion. Using an underlying silicon oxide layer as a dopant source facilitates diffusion of dopants into the bottom side of the polysilicon layer. The polysilicon is grown on top of the oxide layer, after the latter has been doped by ion implantation. Post-growth heat treatment drives in the dopant from the oxide into the polysilicon. To model the process, we studied the diffusion of the two most common silicon dopants, boron (B) and phosphorus (P), using secondary ion mass spectroscopy profiles. Our results show that shallow concentration profiles can be achieved in a buried polysilicon layer using the proposed technique. We present a quantitative 3D model for the diffusion of B and P in polysilicon, which turns the proposed method into an engineerable technique.

Searching for Buried Treasure: Uncovering Discovery in Discovery-Based Learning

Science.gov (United States)

Chase, Kiera; Abrahamson, Dor

2018-01-01

Forty 4th and 9th grade students participated individually in tutorial interviews centered on a problem-solving activity designed for learning basic algebra mechanics through diagrammatic modeling of an engaging narrative about a buccaneering giant burying and unearthing her treasure on a desert island. Participants were randomly assigned to…

Evaluating the movement of active faults on buried pipelines | Parish ...

African Journals Online (AJOL)

During the earthquake, a buried pipeline may be experienced extreme loading that is the result of the relatively large displacement of the Earth along the pipe. Large movements of ground could occur by faulting, liquefaction, lateral spreading, landslides, and slope failures. Since the pipelines are widely spread, and in ...

Method of making a self-aligned schottky metal semi-conductor field effect transistor with buried source and drain

International Nuclear Information System (INIS)

Bol, I.

1984-01-01

A semi-conductor structure and particularly a high speed VLSI Self-Aligned Schottky Metal Semi-Conductor Field Effect Transistor with buried source and drain, fabricated by the ion implantation of source and drain areas at a predetermined range of depths followed by very localized laser annealing to electrically reactivate the amorphous buried source and drain areas thereby providing effective vertical separation of the channel from the buried source and drain respectively. Accordingly, spatial separations between the self-aligned gate-to-drain, and gate-to-source can be relatively very closely controlled by varying the doping intensity and duration of the implantation thereby reducing the series resistance and increasing the operating speed

Impact and structural analysis of the INEL 55 gallon recycled shielded storage container

International Nuclear Information System (INIS)

Richins, W.D.

1996-07-01

The INEL Recycled Shielded Storage Containers (RSSC) are designed primarily for the transportation and storage of mixed RH-TRU solid waste using recycled, potentially contaminated lead and stainless steel construction materials. Two versions of the RSSC have been developed accommodating either 30 or 55 gallon drums. This report addresses the structural qualification of the 55 gallon version of the RSSC to DOT 7A Type A requirements. The controlling qualification test is a 4 ft drop onto a rigid surface. During and after this test, the container contents must remain within the container and shielding must not be reduced. The container is also designed to withstand stacking, internal pressure, lifting loads, tiedown failure, penetration, and a range of temperatures. Nonlinear dynamic finite element analyses were performed using a range of material properties. Loads in the major connections and strains in the stainless steel and lead were monitored as a function of time during impact analyses for three simulated drop orientations. Initial results were used to develop the final design. For the final design, the stainless steel and lead have maximum strains well below ultimate levels except at an impact corner where additional deformation is acceptable. The predicted loads in the connections indicate that some yielding will occur but the containment and shielding will remain intact. The results presented here provide assurance that the container will pass the DOT 7A Type A drop tests as well as the other structural requirements

Tests of a system to exclude roots from buried radioactive waste in a warm, humid climate

International Nuclear Information System (INIS)

Murphy, C.E. Jr.; Corey, J.C.; Adriano, D.C.; Decker, O.D.; Griggs, R.D.

1989-01-01

Vegetation is commonly used to stabilize the ground covering buried waste sites. However, constituents of buried waste can be brought to the surface if the waste is penetrated by plant roots. An ideal waste burial system would allow the use of vegetation to stabilize the soil above the buried waste but would exclude roots from the waste. One system that shows considerable promise is a slow release encapsulation of a root growth inhibitor (Trifluralin). Projected lifetimes of the capsule are in the order of 100 years. The capsule is bonded to a geotextile, which provides an easy means of distributing the capsule evenly over the area to be protected. Vegetation grown in the soil above the barrier has provided good ground cover, although some decrease in growth has been found in some species. Of the species tested the sensitivity to the biobarrier, as measured by the distance root growth stops near the barrier, is bamboo> bahia grass> bermuda grass> soybean. Potential uses for the biobarrier at the Savannah River Site (SRS) include the protection of clay caps over buried, low-level saltstone and protection of gravel drains and clay caps over decommissioned seepage basins. Trails of the biobarrier as part of waste site caps are scheduled to begin during the next 12 months

High dose implantations of antimony for buried layer applications

International Nuclear Information System (INIS)

Gailliard, J.P.; Dupuy, M.; Garcia, M.; Roussin, J.C.

1978-01-01

Electrical and physical properties of high dose implantations of antimony in silicon have been studied for use in buried layer applications. The results have been obtained both on and oriented silicon wafers. Following implantations which lead to amorphization we perform an annealing at 600 0 C for 10 mn in order to recrystallize the layer. The observed electrical properties (μ, R) show that the concentration of electrically active antimony ions is greater than that predicted from the solubility of antimony in silicon. Further annealing (in the range 1050 0 - 1200 0 ) induces: firstly a precipitation of the Sb and secondly a diffusion and dissolution of the precipitates. There is a different evolution of the defects in the and silicon slices. T.E.M. reveals no defects in the wafers after one hour annealing at 1200 0 C, whereas defects and twins remain in wafers. Having obtained the evolution of R with time and temperature it is then determined the implantation and annealing conditions which lead to the low resistivity (R = 10) needed for buried layer applications. Results with very many industrially made devices are discussed

Ground Shock Resistant of Buried Nuclear Power Plant Facility

International Nuclear Information System (INIS)

Ornai, D.; Adar, A.; Gal, E.

2014-01-01

Nuclear Power Plant (NPP) might be subjected to hostile attacks such as Earth Penetrating Weapons (EPW) that carry explosive charges. Explosions of these weapons near buried NPP facility might cause collapse, breaching, spalling, deflection, shear, rigid body motion (depending upon the foundations), and in-structure shock. The occupants and the equipment in the buried facilities are exposed to the in-structure motions, and if they are greater than their fragility values than occupants might be wounded or killed and the equipment might be damaged, unless protective measures will be applied. NPP critical equipment such as pumps are vital for the normal safe operation since it requires constant water circulation between the nuclear reactor and the cooling system, including in case of an immediate shut down. This paper presents analytical- semi empirical formulation and analysis of the explosion of a penetrating weapon with a warhead of 100kgs TNT (Trinitrotoluene) that creates ground shock effect on underground NPP structure containing equipment, such as a typical pump. If the in-structure spectral shock is greater than the pump fragility values than protective measures are required, otherwise a real danger to the NPP safety might occur

Gamma ray energy spectrum of a buried radioactive source

Energy Technology Data Exchange (ETDEWEB)

Massey, N B

1957-07-01

Because of current attempts to utilize airborne gamma-ray scintillation spectrometers as a means of detecting and identifying buried radioactive mineral deposits, it has become important to study the effects of multiple scattering on the gamma-ray energy spectrum of a source buried in a semi-infinite medium. A series of ten experiments was made. First a scintillation detector was located in air at a fixed distance above a 250 microcurie cobalt-60 source suspended in a large tank. The level of water was raised from 25 cm below the source to 50 cm above, and the gamma-ray energy spectrum was observed. It was found that the high energy portion of the cobalt-60 spectrum remained identifiable even when the source was submerged more than five half-lengths. Further, the ratio of the counting rate of the total incident gamma radiation to the counting rate of the primary 1.33 MeV radiation was found to be very nearly linearly proportional to the depth of water cover. This leads to an empirical method for determining the depth of burial of a cobalt-60 point source. (author)

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

International Nuclear Information System (INIS)

1994-01-01

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

PREFACE: Buried Interface Sciences with X-rays and Neutrons 2010

Science.gov (United States)

Sakurai, Kenji

2011-09-01

The 2010 summer workshop on buried interface science with x-rays and neutrons was held at Nagoya University, Japan, on 25-27 July 2010. The workshop was organized by the Japan Applied Physics Society, which established a group to develop the research field of studying buried function interfaces with x-rays and neutrons. The workshop was the latest in a series held since 2001; Tsukuba (December 2001), Niigata (September 2002), Nagoya (July 2003), Tsukuba (July 2004), Saitama (March 2005), Yokohama (July 2006), Kusatsu (August 2006), Tokyo (December 2006), Sendai (July 2007), Sapporo (September 2007), Tokyo (December 2007), Tokyo-Akihabara (July 2009) and Hiratsuka (March 2010). The 2010 summer workshop had 64 participants and 34 presentations. Interfaces mark the boundaries of different material systems at which many interesting phenomena take place, thus making it extremely important to design, fabricate and analyse the structures of interfaces at both the atomic and macroscopic scale. For many applications, devices are prepared in the form of multi-layered thin films, with the result that interfaces are not exposed but buried under multiple layers. Because of such buried conditions, it is generally not easy to analyse such interfaces. In certain cases, for example, when the thin surface layer is not a solid but a liquid such as water, scientists can observe the atomic arrangement of the liquid-solid interface directly by using a scanning probe microscope, of which the tip is soaked in water. However, it has become clear that the use of a stylus tip positioned extremely close to the interface might change the structure of the water molecules. Therefore it is absolutely crucial to develop non-contact, non-destructive probes for buried interfaces. It is known that analysis using x-rays and neutrons is one of the most powerful tools for exploring near-surface structures including interfaces buried under several layers. In particular, x-ray analysis using 3rd

A servo controlled gradient loading triaxial model test system for deep-buried cavern

Energy Technology Data Exchange (ETDEWEB)

Chen, Xu-guang [College of Engineering, Ocean University of China, Qingdao 266100 (China); Shandong Provincial Key Laboratory of Ocean Engineering, Qingdao 266100 (China); Research Center of Geotechnical and Structural Engineering, Shandong University, Jinan 250061 (China); Zhang, Qiang-yong; Li, Shu-cai [Research Center of Geotechnical and Structural Engineering, Shandong University, Jinan 250061 (China)

2015-10-15

A servo controlled gradient loading model test system is developed to simulate the gradient geostress in deep-buried cavern. This system consists of the gradient loading apparatus, the digital servo control device, and the measurement system. Among them, the gradient loading apparatus is the main component which is used for exerting load onto the model. This loading apparatus is placed inside the counterforce wall/beam and is divided to several different loading zones, with each loading zone independently controlled. This design enables the gradient loading. Hence, the “real” geostress field surrounding the deep-buried cavern can be simulated. The loading or unloading process can be controlled by the human-computer interaction machines, i.e., the digital servo control system. It realizes the automation and visualization of model loading/unloading. In addition, this digital servo could control and regulate hydraulic loading instantaneously, which stabilizes the geostress onto the model over a long term. During the loading procedure, the collision between two adjacent loading platens is also eliminated by developing a guide frame. This collision phenomenon is induced by the volume shrinkage of the model when compressed in true 3D state. In addition, several accurate measurements, including the optical and grating-based method, are adopted to monitor the small deformation of the model. Hence, the distortion of the model could be accurately measured. In order to validate the performance of this innovative model test system, a 3D geomechanical test was conducted on a simulated deep-buried underground reservoir. The result shows that the radial convergence increases rapidly with the release of the stress in the reservoir. Moreover, the deformation increases with the increase of the gas production rate. This observation is consistence with field observation in petroleum engineering. The system is therefore capable of testing deep-buried engineering structures.

A servo controlled gradient loading triaxial model test system for deep-buried cavern.

Science.gov (United States)

Chen, Xu-guang; Zhang, Qiang-yong; Li, Shu-cai

2015-10-01

A servo controlled gradient loading model test system is developed to simulate the gradient geostress in deep-buried cavern. This system consists of the gradient loading apparatus, the digital servo control device, and the measurement system. Among them, the gradient loading apparatus is the main component which is used for exerting load onto the model. This loading apparatus is placed inside the counterforce wall/beam and is divided to several different loading zones, with each loading zone independently controlled. This design enables the gradient loading. Hence, the "real" geostress field surrounding the deep-buried cavern can be simulated. The loading or unloading process can be controlled by the human-computer interaction machines, i.e., the digital servo control system. It realizes the automation and visualization of model loading/unloading. In addition, this digital servo could control and regulate hydraulic loading instantaneously, which stabilizes the geostress onto the model over a long term. During the loading procedure, the collision between two adjacent loading platens is also eliminated by developing a guide frame. This collision phenomenon is induced by the volume shrinkage of the model when compressed in true 3D state. In addition, several accurate measurements, including the optical and grating-based method, are adopted to monitor the small deformation of the model. Hence, the distortion of the model could be accurately measured. In order to validate the performance of this innovative model test system, a 3D geomechanical test was conducted on a simulated deep-buried underground reservoir. The result shows that the radial convergence increases rapidly with the release of the stress in the reservoir. Moreover, the deformation increases with the increase of the gas production rate. This observation is consistence with field observation in petroleum engineering. The system is therefore capable of testing deep-buried engineering structures.

A servo controlled gradient loading triaxial model test system for deep-buried cavern

International Nuclear Information System (INIS)

Chen, Xu-guang; Zhang, Qiang-yong; Li, Shu-cai

2015-01-01

A servo controlled gradient loading model test system is developed to simulate the gradient geostress in deep-buried cavern. This system consists of the gradient loading apparatus, the digital servo control device, and the measurement system. Among them, the gradient loading apparatus is the main component which is used for exerting load onto the model. This loading apparatus is placed inside the counterforce wall/beam and is divided to several different loading zones, with each loading zone independently controlled. This design enables the gradient loading. Hence, the “real” geostress field surrounding the deep-buried cavern can be simulated. The loading or unloading process can be controlled by the human-computer interaction machines, i.e., the digital servo control system. It realizes the automation and visualization of model loading/unloading. In addition, this digital servo could control and regulate hydraulic loading instantaneously, which stabilizes the geostress onto the model over a long term. During the loading procedure, the collision between two adjacent loading platens is also eliminated by developing a guide frame. This collision phenomenon is induced by the volume shrinkage of the model when compressed in true 3D state. In addition, several accurate measurements, including the optical and grating-based method, are adopted to monitor the small deformation of the model. Hence, the distortion of the model could be accurately measured. In order to validate the performance of this innovative model test system, a 3D geomechanical test was conducted on a simulated deep-buried underground reservoir. The result shows that the radial convergence increases rapidly with the release of the stress in the reservoir. Moreover, the deformation increases with the increase of the gas production rate. This observation is consistence with field observation in petroleum engineering. The system is therefore capable of testing deep-buried engineering structures

Y chromosomal and sex effects on the behavioral stress response in the defensive burying test in wild house mice

NARCIS (Netherlands)

Sluyter, F; Korte, SM; Van Baal, GCM; De Ruiter, AJH; Van Oortmerssen, GA

1999-01-01

Genetically selected short attack latency (SAL) and long attack latency (LAL) male wild house mice behave differently in the defensive burying test. When challenged, SAL males respond actively with more time spent on defensive burying, whereas LAL males are more passive with more time remaining

Energy options

International Nuclear Information System (INIS)

Hampton, Michael

1999-01-01

This chapter focuses on energy options as a means of managing exposure to energy prices. An intuitive approach to energy options is presented, and traditional definitions of call and put options are given. The relationship between options and swaps, option value and option exercises, commodity options, and option pricing are described. An end-user's guide to energy option strategy is outlined, and straight options, collars, participating swaps and collars, bull and bear spreads, and swaption are examined. Panels explaining the defining of basis risk, and discussing option pricing and the Greeks, delta hedging, managing oil options using the Black-Scholes model, caps, floors and collars, and guidelines on hedging versus speculation with options are included in the paper

The kinetics of solid phase epitaxy in As-doped buried amorphous silicon layers

International Nuclear Information System (INIS)

McCallum, J.C.

1998-01-01

The kinetics of dopant-enhanced solid phase epitaxy (SPE) have been measured in buried a-Si layers doped with arsenic. SPE rates were measured over the temperature range 480 - 660 deg C for buried a-Si layers containing ten different As concentrations. In the absence of H-retardation effects, the dopant-enhanced SPE rate is observed to depend linearly on the As concentration over the entire range of concentrations, 1-16 x 10 19 cm -3 covered in the study. The Fermi level energy was calculated as a function of doping and find an equation that can provide good fits to the data. The implications of these results for models of the SPE process is discussed

Measurement of buried undercut structures in microfluidic devices by laser fluorescent confocal microscopy

International Nuclear Information System (INIS)

Li Shiguang; Liu Jing; Nguyen, Nam-Trung; Fang Zhongping; Yoon, Soon Fatt

2009-01-01

Measuring buried, undercut microstructures is a challenging task in metrology. These structures are usually characterized by measuring their cross sections after physically cutting the samples. This method is destructive and the obtained information is incomplete. The distortion due to cutting also affects the measurement accuracy. In this paper, we first apply the laser fluorescent confocal microscopy and intensity differentiation algorithm to obtain the complete three-dimensional profile of the buried, undercut structures in microfluidic devices, which are made by the soft lithography technique and bonded by the oxygen plasma method. The impact of material wettability and the refractive index (n) mismatch among the liquid, samples, cover layer, and objective on the measurement accuracy are experimentally investigated.

Local Backbone Flexibility as a Determinant of the Apparent pKa Values of Buried Ionizable Groups in Proteins.

Science.gov (United States)

Peck, Meredith T; Ortega, Gabriel; De Luca-Johnson, Javier N; Schlessman, Jamie L; Robinson, Aaron C; García-Moreno E, Bertrand

2017-10-10

Ionizable groups buried in the hydrophobic interior of proteins are essential for energy transduction. These groups can have highly anomalous pK a values that reflect the incompatibility between charges and dehydrated environments. A systematic study of pK a values of buried ionizable groups in staphylococcal nuclease (SNase) suggests that these pK a values are determined in part by conformational reorganization of the protein. Lys-66 is one of the most deeply buried residues in SNase. We show that its apparent pK a of 5.7 reflects the average of the pK a values of Lys-66 in different conformational states of the protein. In the fully folded state, Lys-66 is deeply buried in the hydrophobic core of SNase and must titrate with a pK a of ≪5.7. In other states, the side chain of Lys-66 is fully solvent-exposed and has a normal pK a of ≈10.4. We show that the pK a of Lys-66 can be shifted from 5.7 toward a more normal value of 7.1 via the insertion of flanking Gly residues at positions 64 and 67 to promote an "open" conformation of SNase. Crystal structures and nuclear magnetic resonance spectroscopy show that in these Gly-containing variants Lys-66 can access bulk water as a consequence of overwinding of the C-terminal end of helix 1. These data illustrate that the apparent pK a values of buried groups in proteins are governed in part by the difference in free energy between different conformational states of the protein and by differences in the pK a values of the buried groups in the different conformations.

Weapons-grade plutonium dispositioning. Volume 1: Executive summary

International Nuclear Information System (INIS)

Parks, D.L.; Sauerbrun, T.J.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

Technology evaluation report for the Buried Waste Robotics Program Subsurface Mapping Project

International Nuclear Information System (INIS)

Griebenow, B.E.

1992-01-01

This document presents a summary of the work performed in support of the Buried Waste Robotics Program Subsurface Mapping Project. The project objective was to demonstrate the feasibility of remotely characterizing buried waste sites. To fulfill this objective, a remotely-operated vehicle, equipped with several sensors, was deployed at the Idaho National Engineering Laboratory. Descriptions of the equipment and areas involved in the project are included in this report. Additionally, this document provides data that was obtained during characterization operations at the Cold Test Pit and the Subsurface Disposal Area, both at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex, and at the Idaho Chemical Processing Plant. The knowledge gained from the experience, that can be applied to the next generation remote-characterization system, is extensive and is presented in this report

Managing soil moisture on waste burial sites

International Nuclear Information System (INIS)

Anderson, J.E.; Ratzlaff, T.D.

1991-11-01

Shallow land burial is a common method of disposing of industrial, municipal, and low-level radioactive waste. The exclusion of water from buried wastes is a primary objective in designing and managing waste disposal sites. If wastes are not adequately isolated, water from precipitation may move through the landfill cover and into the wastes. The presence of water in the waste zone may promote the growth of plant roots to that depth and result in the transport of toxic materials to above-ground foliage. Furthermore, percolation of water through the waste zone may transport contaminants into ground water. This report presents results from a field study designed to assess the the potential for using vegetation to deplete soil moisture and prevent water from reaching buried wastes at the Idaho National Engineering Laboratory (INEL). Our results show that this approach may provide an economical means of limiting the intrusion of water on waste sites

Improving breakdown voltage and self-heating effect for SiC LDMOS with double L-shaped buried oxide layers

Science.gov (United States)

Bao, Meng-tian; Wang, Ying

2017-02-01

In this paper, a SiC LDMOS with double L-shaped buried oxide layers (DL-SiC LDMOS) is investigated and simulated. The DL-SiC LDMOS consists of two L-shaped buried oxide layers and two SiC windows. Using 2-D numerical simulation software, Atlas, Silvaco TCAD, the breakdown voltage, and the self-heating effect are discussed. The double-L shaped buried oxide layers and SiC windows in the active area can introduce an additional electric field peak and make the electric field distribution more uniform in the drift region. In addition, the SiC windows, which connect the active area to the substrate, can facilitate heat dissipation and reduce the maximum lattice temperature of the device. Compared with the BODS structure, the DL-SiC LDMOS and BODS structures have the same device parameters, except of the buried oxide layers. The simulation results of DL-SiC LDMOS exhibits outstanding characteristics including an increase of the breakdown voltage by 32.6% to 1220 V, and a low maximum lattice temperature (535 K) at room temperature.

Behaviour of nature and technogenic radioisotopes in buried geochemical barriers

International Nuclear Information System (INIS)

Kuznetsov, V.A.; Onoshko, M.P.; Generalova, V.A.

1998-01-01

Behaviour of potassium 40, radium 226, thorium 232, strontium 90 and cesium 137 on geochemical barriers connected with buried soils and cut-off meander sediments of the Holocene age of the Sozh river valley are examined. Some sides of the barrier geochemical structure caused by syngeneic and epigenetic processes have been taken into consideration

Buried Versus Exposed Kirschner Wires Following Fixation of Hand Fractures: l Clinician and Patient Surveys.

Science.gov (United States)

2018-04-01

Fractures of the metacarpals and phalanges are common. Placement of Kirschner wires (K-wires) is the most common form of surgical fixation. After placement, a key decision is whether to bury the end of a K-wire or leave it protruding from the skin (exposed). A recent systematic review found no evidence to support either approach. The aim of study was to investigate current clinical practice, understand the key factors influencing clinician decision-making, and explore patient preferences to inform the design of a randomized clinical trial. The steering group developed surveys for hand surgeons, hand therapists, and patients. Following piloting, they were distributed across the United Kingdom hand surgery units using the Reconstructive Surgery Trials Network. A total of 423 hand surgeons, 187 hand therapists, and 187 patients completed the surveys. Plastic surgeons and junior surgical trainees preferred to leave K-wires not buried. Ease of removal correlated with a decision to leave wires exposed, whereas perceived risk of infection correlated with burying wires. Cost did not affect the decision. Hand therapists were primarily concerned about infection and patient-related outcomes. Patients were most concerned about wire-related problems and pain. This national survey provides a new understanding of the use of K-wires to manage hand fractures in the United Kingdom. A number of nonevidence-based factors seem to influence the decision to bury or leave K-wires exposed. The choice has important clinical and health economic implications that justify a randomized controlled trial.

75 FR 32313 - Specifications and Drawings for Construction Direct Buried Plant

Science.gov (United States)

2010-06-08

... construction units for Fiber-to-the-Home, remove redundant or outdated requirements, and simplify the.... Because of Fiber-to-the-Home construction and advancements made in construction installation methods and... Construction Direct Buried Plant AGENCY: Rural Utilities Service, USDA. ACTION: Proposed Rule. SUMMARY: The...

Fabrication and experimental demonstration of photonic crystal laser with buried heterostructure

DEFF Research Database (Denmark)

Sakanas, Aurimas; Yu, Yi; Semenova, Elizaveta

2017-01-01

of separating active light amplification regions from passive regions for light propagation without induced absorption losses and surface recombination. The main focus of this work is the fabrication and experimental demonstration of a buried heterostructure (BH) photonic crystal laser bonded to a silicon wafer...

Laser-induced acoustic landmine detection with experimental results on buried landmines

NARCIS (Netherlands)

Heuvel, J.C. van den; Putten, F.J.M. van; Koersel, A.C. van; Schleijpen, H.M.A.

2004-01-01

Acoustic landmine detection (ALD) is a technique for the detection of buried landmines including non-metal mines. Since it gives complementary results with GPR or metal detection, sensor fusion of these techniques with acoustic detection would give promising results. Two methods are used for the

Fabrication of GaN with buried tungsten (W) structures using epitaxial lateral overgrowth (ELO) via LP-MOVPE

International Nuclear Information System (INIS)

Miyake, Hideto; Yamaguchi, Motoo; Haino, Masahiro

2000-01-01

A buried tungsten (W) mask structure with GaN is successfully obtained by epitaxial lateral overgrowth (ELO) technique via low-pressure metalorganic vapor phase epitaxy (LP-MOVPE). The selectivity of GaN growth on the window region vs. the mask region is good. An underlying GaN with a striped W metal mask is easily decomposed above 500 C by the W catalytic effect, by which radical hydrogen is reacted with GaN. It is difficult to bury the W mask because severe damage occurs in the GaN epilayer under the mask. It is found that an underlying AlGaN/GaN layer with a narrow W stripe mask width (mask/window - 2/2 microm) leads the ELO GaN layer to be free from damage, resulting in an excellent W-buried structure

Non-Destructive Detection of Rebar Buried in a Reinforced Concrete Wall with Wireless Passive SAW Sensor

Science.gov (United States)

Fan, Yanping; Ji, Xiaojun; Cai, Ping; Lu, Qianhui

2013-01-01

In order to reduce the damage to the old reinforced concrete walls and work out the best construction scheme during the renovation of old buildings, it is often required to detect the position of rebar buried in concrete walls. In this paper, we propose a non-destructive method to detect the buried rebar by self-inductive sensor combined with surface acoustic wave resonator (SAWR). The proposed method has the advantages of wireless, passive and convenient operations. In our new design, the sensing element of self-inductance coil was made as a component of SAWR matching network. The distribution of rebar could be measured according to the system resonant frequency, using a signal demodulation device set. The depth of buried rebar and the deviation of output resonant frequency from inherent frequency of SAWR have an inverse relation. Finally, the validity of the method was verified in theoretical calculation and simulation.

Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

Energy Technology Data Exchange (ETDEWEB)

Garza, I.A.

1996-12-01

About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency.

Evaluation of existing EPRI and INEL test data to determine the worm to worm gear coefficient of friction in Limitorque actuators

International Nuclear Information System (INIS)

Garza, I.A.

1996-01-01

About the last sizing parameter for motor operated valves which has not been determined by utility or NRC sponsored testing is actuator efficiency. A by-product of EPRI testing for valve factors is the measurement of the actuator efficiencies. Motor sizing in this testing provides efficiency testing for motors running near synchronous speed. INEL testing, sponsored by the NRC, for stem factors and rate of loading provides complimentary data for motors loaded down to zero speed. This paper analyzes the data from these two test programs to determine the coefficient of friction for the worm to worm gear interface. This allowed the development of an algorithm for determining the efficiency of actuators which have not been tested. This paper compares the results of this algorithm to the test data to provide a measure of the accuracy of this method for calculating actuator efficiency

A feasibility study on SiC optoinjected CCD with buried channels

International Nuclear Information System (INIS)

Ye Na; Chen Zhiming; Xie Longfei

2013-01-01

An SiC optoinjected charge-coupled device with buried channels (BCCD) is designed for the detection of ultraviolet light (UV), and its feasibility is studied by means of Silvaco numerical simulation software. Charge storage and transfer characteristics of the BCCD can be conformed by simulation results. The buried channel design is a key point to realize the high sensitivity of the device. The channel mobility of electrons in the 6H-SiC BCCD can be changed from 47 to 200 cm 2 /(V.s) when the channel is replaced from surface to the subsurface of 0.2 μm. With the optimized device parameters, the density of stored electrons can reach up to 1.062 × 10 11 cm −2 and the number of stored electrons is up to 1.826 × 10 8 for UV light with wavelengths from 200 to 380 nm and an intensity of 0.1 W/cm 2 under a driving voltage of 15 V at room temperature. (semiconductor devices)

Redistribution of erbium during the crystallization of buried amorphous silicon layers

International Nuclear Information System (INIS)

Aleksandrov, O.V.; Nikolaev, Yu.A.; Sobolev, N.A.; Sakharov, V.I.; Serenkov, I.T.; Kudryavtsev, Yu.A.

1999-01-01

The redistribution of Er during its implantation in silicon at doses close to the amorphization threshold and its subsequent solid-phase epitaxial (SPE) crystallization is investigated. The formation of a buried amorphous (a) layer is discovered at Er doses equal to 5x10 13 and 1x10 14 cm -2 using Rutherford backscattering. The segregation of Er in this case takes place inwardly from the two directions corresponding to the upper and lower boundaries of the buried αlayer and leads to the formation of a concentration peak at the meeting place of the two crystallization fronts. A method for calculating the coordinate dependence of the segregation coefficient k from the distribution profiles of the erbium impurity before and after annealing is proposed. The k(x) curve exhibits a drop, whose width increases with decreasing Er implantation dose. Its appearance is attributed to the nonequilibrium nature of the segregation process at the beginning of SPE crystallization

UNCOVERING BURIED VOLCANOES: NEW DATA FOR PROBABILISTIC VOLCANIC HAZARD ASSESSMENT AT YUCCA MOUNTAIN

International Nuclear Information System (INIS)

F.V. Perry

2005-01-01

Basaltic volcanism poses a potential hazard to the proposed Yucca Mountain nuclear waste repository because multiple episodes of basaltic volcanism have occurred in the Yucca Mountain region (YMR) in the past 11 Ma. Intervals between eruptive episodes average about 1 Ma. Three episodes have occurred in the Quaternary at approximately 1.1 Ma (5 volcanoes), 350 ka (2 volcanoes), and 80 ka (1 volcano). Because Yucca Mountain lies within the Basin and Range Province, a significant portion of the pre-Quaternary volcanic history of the YMR may be buried in alluvial-filled basins. An exceptionally high-resolution aeromagnetic survey and subsequent drilling program sponsored by the U.S. Department of Energy (DOE) began in 2004 and is gathering data that will enhance understanding of the temporal and spatial patterns of Pliocene and Miocene volcanism in the region (Figure 1). DOE has convened a ten-member expert panel of earth scientists that will use the information gathered to update probabilistic volcanic hazard estimates originally obtained by expert elicitation in 1996. Yucca Mountain is a series of north-trending ridges of eastward-tilted fault blocks that are bounded by north to northeast-trending normal faults. Topographic basins filled with up to 500 m of alluvium surround it to the east, south and west. In the past several decades, nearly 50 holes have been drilled in these basins, mainly for Yucca Mountain Project Site Characterization and the Nye County Early Warning Drilling Program. Several of these drill holes have penetrated relatively deeply buried (300-400 m) Miocene basalt; a Pliocene basalt dated at 3.8 Ma was encountered at a relatively shallow depth (100 m) in the northern Amargosa Desert (Anomaly B in Figure 1). The current drilling program is the first to specifically target and characterize buried basalt. Based on the new aeromagnetic survey and previous air and ground magnetic surveys (Connor et al. 2000; O'Leary et al. 2002), at least eight drill

Reducing Thermal Losses and Gains With Buried and Encapsulated Ducts in Hot-Humid Climates

Energy Technology Data Exchange (ETDEWEB)

Shapiro, C.; Magee, A.; Zoeller, W.

2013-02-01

The Consortium for Advanced Residential Buildings (CARB) monitored three houses in Jacksonville, FL, to investigate the effectiveness of encapsulated and encapsulated/buried ducts in reducing thermal losses and gains from ductwork in unconditioned attics. Burying ductwork beneath loose-fill insulation has been identified as an effective method of reducing thermal losses and gains from ductwork in dry climates, but it is not applicable in humid climates where condensation may occur on the outside of the duct jacket. By encapsulating the ductwork in closed cell polyurethane foam (ccSPF) before burial beneath loose-fill mineral fiber insulation, the condensation potential may be reduced while increasing the R-value of the ductwork.

Charge accumulation in the buried oxide of SOI structures with the bonded Si/SiO2 interface under γ-irradiation: effect of preliminary ion implantation

International Nuclear Information System (INIS)

Naumova, O V; Fomin, B I; Ilnitsky, M A; Popov, V P

2012-01-01

In this study, we examined the effect of preliminary boron or phosphorous implantation on charge accumulation in the buried oxide of SOI-MOSFETs irradiated with γ-rays in the total dose range (D) of 10 5 –5 × 10 7 rad. The buried oxide was obtained by high-temperature thermal oxidation of Si, and it was not subjected to any implantation during the fabrication process of SOI structures. It was found that implantation with boron or phosphorous ions, used in fabrication technologies of SOI-MOSFETs, increases the concentration of precursor traps in the buried oxide of SOI structures. Unlike in the case of boron implantation, phosphorous implantation leads to an increased density of states at the Si/buried SiO 2 interface during subsequent γ-irradiation. In the γ-irradiated SOI-MOSFETs, the accumulated charge density and the density of surface states in the Si/buried oxide layer systems both vary in proportion to k i ln D. The coefficients k i for as-fabricated and ion-implanted Si/buried SiO 2 systems were evaluated. From the data obtained, it was concluded that a low density of precursor hole traps was a factor limiting the positive charge accumulation in the buried oxide of as-fabricated (non-implanted) SOI structures with the bonded Si/buried SiO 2 interface. (paper)

48 CFR 552.217-71 - Notice Regarding Option(s).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Notice Regarding Option(s... Notice Regarding Option(s). As prescribed in 517.208(b), insert the following provision: Notice Regarding Option(s) (NOV 1992) The General Services Administration (GSA) has included an option to [Insert...

LUMINOUS BURIED ACTIVE GALACTIC NUCLEI AS A FUNCTION OF GALAXY INFRARED LUMINOSITY REVEALED THROUGH SPITZER LOW-RESOLUTION INFRARED SPECTROSCOPY

International Nuclear Information System (INIS)

Imanishi, Masatoshi

2009-01-01

We present the results of Spitzer Infrared Spectrograph 5-35 μm low-resolution spectroscopic energy diagnostics of ultraluminous infrared galaxies (ULIRGs) at z> 0.15, classified optically as non-Seyferts. Based on the equivalent widths of polycyclic aromatic hydrocarbon emission and the optical depths of silicate dust absorption features, we searched for signatures of intrinsically luminous, but optically elusive, buried active galactic nuclei (AGNs) in these optically non-Seyfert ULIRGs. We then combined the results with those of non-Seyfert ULIRGs at z IR 12 L sun . We found that the energetic importance of buried AGNs clearly increases with galaxy infrared luminosity, becoming suddenly discernible in ULIRGs with L IR > 10 12 L sun . For ULIRGs with buried AGN signatures, a significant fraction of infrared luminosities can be accounted for by the detected buried AGN and modestly obscured (A V < 20 mag) starburst activity. The implied masses of spheroidal stellar components in galaxies for which buried AGNs become important roughly correspond to the value separating red massive and blue less-massive galaxies in the local universe. Our results may support the widely proposed AGN-feedback scenario as the origin of galaxy downsizing phenomena, where galaxies with currently larger stellar masses previously had higher AGN energetic contributions and star formation originating infrared luminosities, and have finished their major star formation more quickly, due to stronger AGN feedback.

Numerical simulation of seismic performance of the underground structure buried in the dense saturated sand

International Nuclear Information System (INIS)

Kawai, Tadashi

2006-01-01

The applicability of the advanced earthquake resistant performance verification method on reinforced concrete underground structures developed by CRIEPI was investigated for the structures which buried in the dry sand. For the advancement of the method in practical use, the applicability to the structures buried in the saturated ground is expected to be verified. In this study the applicability of the effective stress based soil modeling method in numerical analysis, which was proposed through the modification of the formerly developed model by CRIEPI, was verified through the non-linear dynamic numerical simulations of the large centrifuge tests conducted by using a model comprised of fully saturated sand and a aluminium duct type structure specially prepared for the measurement of the load acting on the structure surface with the soil-structure interaction. The magnitudes of the simulated loads and the resultant deformations of the structure were almost same as those of experiments. As a result it is confirmed that the performance verification method is useful for the structures buried in the saturated ground with using the proposed effective stress based ground modeling method. (author)

Test plan for dig-face characterization performance testing

International Nuclear Information System (INIS)

Josten, N.E.

1993-09-01

The dig-face characterization concept has been under development at the Idaho National Engineering Laboratory (INEL) since FY 1992 through the support of the Buried Waste Integrated Demonstration Program. A Dig-face Characterization System conducts continuous subsurface characterization simultaneously with retrieval of hazardous and radioactive waste from buried waste sites. The system deploys multiple sensors at the retrieval operation dig-face and collects data that provide a basis for detecting, locating, and identifying hazardous conditions before they are disturbed by the retrieval equipment. This test plan describes initial efforts to test the dig-face characterization concept at the INEL Cold Test Pit using a simplified prototype apparatus and off-the-shelf sensors. The Cold Test Pit is a simulated waste site containing hazardous and radioactive waste surrogates at known locations. Testing will be directed toward three generic characterization problems: metal detection, plume detection, and radioactive source detection. The prototype apparatus will gather data using magnetometers, a ground conductivity meter, a trace gas analyzer, and a gamma ray sensor during simulated retrieval of the surrogate waste materials. The data acquired by a dig-face characterization system are unique because of the high precision, high data density, and multiple viewpoints attainable through the dig-face deployment approach. The test plan establishes procedures for collecting and validating a representative dig-face characterization data set. Analysis of these data will focus on developing criteria for predicting the depth, location, composition, and other characteristics of the surrogate waste materials. If successful, this proof-of-concept exercise will provide a foundation for future development of a fully-operational system that is capable of operating on an actual waste site

Front buried metallic contacts and thin porous silicon combination for efficient polycrystalline silicon solar cells

International Nuclear Information System (INIS)

Ben Rabha, M.; Boujmil, M.F.; Meddeb, N.; Saadoun, M.; Bessais, B.

2006-01-01

We investigate the impacts of achieving buried grid metallic contacts (BGMC), with and without application of a front porous silicon (PS) layer, on the photovoltaic properties of polycrystalline silicon (pc-Si) solar cells. A grooving method based on Chemical Vapor Etching (CVE) was used to perform buried grid contacts on the emitter of pc-Si solar cells. After realizing the n + /p junction using a phosphorus diffusion source, BGMCs were realized using the screen printing technique. We found that the buried metallic contacts improve the short circuit current from 16 mA/cm 2 (for reference cell without buried contacts) to about 19 mA/cm 2 . After application of a front PS layer on the n + emitter, we observe an enhancement of the short circuit current from 19 to 24 mA/cm 2 with a decrease of the reflectivity by about 40% of its initial value. The dark I-V characteristics of the pc-Si cells with PS-based emitter show an important reduction of the reverse current together with an improvement of the rectifying behaviour. Spectral response measurements performed at a wavelength range of 400-1100 nm showed a significant increase in the quantum efficiency, particularly at shorter wavelength (400-650 nm). These results indicate that the BGMCs improve the carrier collection and that the PS layer acts as an antireflective coating that reduces reflection losses and passivates the front surface. This low cost and simple technology based on the CVE technique could enable preparing efficient polycrystalline silicon solar cells