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Sample records for post-closure monitoring al121125

  1. Barriers and post-closure monitoring (AL121125)

    International Nuclear Information System (INIS)

    Bostick, K.V.; Janecky, D.

    1995-01-01

    This project focuses on the rapid implementation of near-surface barriers, biotreatment, and post-closure monitoring technology. It uses water-permeable and biologic barriers that chemically capture and/or degrade contaminants without significantly altering the natural water flow regime. Barrier approaches are being tested for two different applications. The first is the use of barriers for confinement of chemical contaminants for in-trench treatments with leach systems or an in-place bioreactor. The second is an enhancement of the current practice of emplacing grout or clay slurry walls into direct horizontal surface and subsurface water flows around a contaminated area by integrating permeable reactive barriers and petroleum reservoir gel/foam/polymer technology

  2. Field test of a post-closure radiation monitor

    International Nuclear Information System (INIS)

    Reed, S.; Christy, C.E.; Heath, R.E.

    1995-01-01

    The DOE is conducting remedial actions at many sites contaminated with radioactive materials. After closure of these sites, long-term subsurface monitoring is typically required by law. This monitoring is generally labor intensive and expensive using conventional sampling and analysis techniques. The U.S. Department of Energy's Morgantown Energy Technology Center (METC) has contracted with Babcock and Wilcox to develop a Long-Term Post-Closure Radiation Monitoring System (LPRMS) to reduce these monitoring costs. A prototype LPRMS probe was built, and B ampersand W and FERMCO field tested this monitoring probe at the Fernald Environmental Management Project in the fall of 1994 with funding from the DOE's Office of Technology Development (EM-50) through METC. The system was used to measure soil and water with known uranium contamination levels, both in drums and in situ at depths up to 3 meters. For comparison purposes, measurements were also performed using a more conventional survey probe with a sodium iodide scintillator directly butt-coupled to detection electronics. This paper presents a description and the results of the field tests. The results were used to characterize the lower detection limits, precision and bias of the system, which allowed the DOE to judge the monitoring system's ability to meet its long-term post-closure radiation monitoring needs. Based on the test results, the monitoring system has been redesigned for fabrication and testing in a potential Phase III of this program. If the DOE feels that this system can meet its needs and chooses to continue into Phase III of this program, this redesigned full scale prototype system will be built and tested for a period of approximately a year. Such a system can be used at a variety of radioactively contaminated sites

  3. Amchitka Mud Pit Sites 2006 Post-Closure Monitoring and Inspection Report, Amchitka Island, Alaska, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick

    2006-09-01

    In 2001, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA/NSO) remediated six areas associated with Amchitka mud pit release sites located on Amchitka Island, Alaska. This included the construction of seven closure caps. To ensure the integrity and effectiveness of remedial action, the mud pit sites are to be inspected every five years as part of DOE's long-term monitoring and surveillance program. In August of 2006, the closure caps were inspected in accordance with the ''Post-Closure Monitoring and Inspection Plan for Amchitka Island Mud Pit Release Sites'' (Rev. 0, November 2005). This post-closure monitoring report provides the 2006 cap inspection results.

  4. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    Energy Technology Data Exchange (ETDEWEB)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996.

  5. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996

  6. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Bechtel Nevada

    2006-08-01

    This Post-Closure Inspection and Monitoring Report provides the results and inspections and monitoring for Corrective Action Unit 110: Area 3 Waste Management Division U-3ax/bl Crater, Nevada Test Site, Nevada. This report includes an analysis and summary of the site inpsections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at Corrective Action Unit 110, for the annual period July 2005 thrugh June 2006.

  7. IDENTIFICATION OF DOE'S POST-CLOSURE MONITORING NEEDS AND REQUIREMENTS

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian, Ph.D.

    1999-01-01

    The 2006 plan sets an ambitious agenda for the U.S. Department of Energy (DOE), Office of Environmental Management (EM) and the remediation of sites contaminated by decades of nuclear weapons production activities. The plan's primary objective is to reduce overall clean up costs by first eliminating the environmental problems that are most expensive to control and safely maintain. In the context of the 2006 Plan, closure refers to the completion of area or facility specific cleanup projects. The cleanup levels are determined by the planned future use of the site or facility. Use restrictions are still undecided for most sites but are highly probable to exclude residential or agricultural activities. Most of the land will be remediated to ''industrial use'' levels with access restrictions and some areas will be closed-off through containment. Portions of the site will be reserved for waste disposal, either as a waste repository or the in-situ immobilization of contaminated soil and groundwater, and land use will be restricted to waste disposal only. The land used for waste disposal will require monitoring and maintenance activities after closure. Most of the land used for industrial use may also require such postclosure activities. The required postclosure monitoring and maintenance activities will be imposed by regulators and stakeholders. Regulators will not approve closure plans without clearly defined monitoring methods using approved technologies. Therefore, among all other more costly and labor-intensive closure-related activities, inadequate planning for monitoring and lack of appropriate monitoring technologies can prevent closure. The purpose of this project is to determine, document, and track the current and evolving postclosure monitoring requirements at DOE-EM sites. This information will aid CMST-CP in guiding its postclosure technology development and deployment efforts.

  8. Development of a long-term post-closure radiation monitor: Phase 2, Topical report, March 1994--July 1995

    International Nuclear Information System (INIS)

    Reed, S.E.

    1995-07-01

    The long-term monitoring of a hazardous waste site for migration of radionuclides requires installation of radiation sensors at a large number of subsurface locations. The concept under development employs a passive in-ground measurement probe which contains a scintillator coupled to an optical lightguide. The overall goal of the Long-Term Post-Closure Radiation Monitor System (LPRMS) development program is to configure a long-term radiation monitor using commercially available, demonstrated components to the largest extent possible. The development program is planned as a three phase program spanning a total time of 53 months. The problems to be solved during Phase 1 were primarily those associated with selection of the most appropriate components (scintillator, coupling optics, optical fiber, and opto-electronics) to maximize the signal reaching the detectors and thereby minimizing the integration time required to obtain a reliable measure of radiation. Phase 2 (the current Phase) encompassed the fabrication and testing of the prototype LPRMS probe at a contaminated DOE site, the Fernald Environmental Management Project, in southwestern Ohio. Uranium isotopes are the primary contaminants of concern at this site. The single probe and opto-electronic device were used to made measurements in-situ at relatively shallow subsurface depths. The end objective of Phase 2 was the design of a full-scale prototype system which incorporates all the features expected to be necessary on a commercial system, including 50 meter depth of measurement, multiplexing of multiple probes, and remote transmission of data. This full-scale prototype will be fabricated and field tested for 12 months during Phase 3, and a commercial design will be developed based upon the data gathered and experience gained during the entire program

  9. Post-Closure Inspection and Monitoring Report for the Salmon, Mississippi, Site Calendar Year 2007

    International Nuclear Information System (INIS)

    2008-01-01

    This report summarizes inspection and monitoring activities performed on and near the Salmon, Mississippi, Site in calendar year 2007. The Draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities and the results of sample analyses. This report is submitted to comply with that requirement. The Tatum Salt Dome was used by the U.S. Atomic Energy Commission (AEC) for underground nuclear testing during the cold war. The land surface above the salt dome, the Salmon Site, is located in Lamar County, Mississippi, approximately 12 miles west of Purvis (Figure 1). The U.S. Department of Energy (DOE), the successor to the AEC, is responsible for long-term surveillance and maintenance of the site. The DOE Office of Legacy Management (LM) was assigned this responsibility effective October 2006

  10. Critical parameters and measurement methods for post closure monitoring: A review of the state of the art and recommendations for further studies

    International Nuclear Information System (INIS)

    Morrison, H.F.; Majer, E.L.; Tsang, C.F.

    1987-05-01

    Both NRC and EPA regulations require programs of post closure monitoring to detect substantial and detrimental deviations from expected performance. The unexpected in this case would involve anomalous stress changes that might rupture the canisters or changes in the hydrologic regime that might accelerate corrosion. In the event of leakage brought about by any means transport of radionuclides to the accessible environment could occur through unexpected changes in the hydrologic flow regime caused either by the long term effects of the thermal loading by the waste or by changes in regional stress or hydrology. Studies of performance confirmation have identified six parameters or conditions that should be monitored that are associated with the thermal, mechanical and hydrologic phenomena introduced by the waste heat: temperature, stress, displacement, pore pressure, groundwater velocity and permeability. Since it is the thermal load that continues to increase after decommissioning, and which continues to alter the stress field and the hydrological regime, these same six parameters remain the critical ones in post closure monitoring. At two of the repository sites fractures have been clearly shown to be critical in modelling and performance confirmation; at the tuff site fluid saturation is also a critical parameter and for all the sites estimates of the groundwater velocity through the site are very important. Changes in fracture properties, saturation and fluid flow are thus of continuing importance in post closure monitoring. 14 refs., 19 figs

  11. Monitoring in the post-closure phase. Development of wireless techniques for data transmission from the repository to the surface

    International Nuclear Information System (INIS)

    Schroeder, Thomas J.; Rosca-Bocancea, Ecaterina; Hart, Jaap

    2015-01-01

    When the in-situ monitoring in a geological disposal facility is continued during the post-closure phase, monitoring data need to be transmitted wirelessly from the repository to the surface. Wireless data transmission is used today in many applications, but the large attenuation by the geologic medium between the disposal facility and the surface makes the application of high-frequency based techniques impractical. As part of the EURATOM FP-7 project MoDeRn (Monitoring Developments for safe Repository operation and staged closure), NRG has investigated the feasibility of wireless data transmission through an argillaceous host rock (Boom Clay), making use of low frequency magnetic fields. The main focus of the contribution was to analyze and optimize the energy efficiency of this technique. Therefore, a mathematical model description has been developed that allows to estimate the expected signal strength on the earth's surface on basis of the most relevant characteristics of transmitter, receiver and transmission path. The model is used to analyze the complex interactions of different system parameters, and is applied to design an optimized set-up for through-the-earth data transmission and to estimate minimum energy demands for signal transmission. To demonstrate the potentials of this technique, experiments were performed in the 225 m deep underground research facility HADES in Mol, Belgium. Signal propagation and attenuation by the geologic medium between the HADES and the surface has been measured, and the site-specific magnetic background noise at the surface in Mol has been characterized. Based on the results, optimum conditions for signal transmission have been derived and data transmission experiments have been performed. Results show that despite large local interferences on the surface in Mol, wireless data transmission through 225 m of a geological medium is possible. Data transmission rates up to 100 bit/s has been successfully tested. The

  12. Monitoring in the post-closure phase. Development of wireless techniques for data transmission from the repository to the surface

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, Thomas J.; Rosca-Bocancea, Ecaterina; Hart, Jaap [Nuclear Research and Consultancy Group (NRG), Petten (Netherlands)

    2015-07-01

    When the in-situ monitoring in a geological disposal facility is continued during the post-closure phase, monitoring data need to be transmitted wirelessly from the repository to the surface. Wireless data transmission is used today in many applications, but the large attenuation by the geologic medium between the disposal facility and the surface makes the application of high-frequency based techniques impractical. As part of the EURATOM FP-7 project MoDeRn (Monitoring Developments for safe Repository operation and staged closure), NRG has investigated the feasibility of wireless data transmission through an argillaceous host rock (Boom Clay), making use of low frequency magnetic fields. The main focus of the contribution was to analyze and optimize the energy efficiency of this technique. Therefore, a mathematical model description has been developed that allows to estimate the expected signal strength on the earth's surface on basis of the most relevant characteristics of transmitter, receiver and transmission path. The model is used to analyze the complex interactions of different system parameters, and is applied to design an optimized set-up for through-the-earth data transmission and to estimate minimum energy demands for signal transmission. To demonstrate the potentials of this technique, experiments were performed in the 225 m deep underground research facility HADES in Mol, Belgium. Signal propagation and attenuation by the geologic medium between the HADES and the surface has been measured, and the site-specific magnetic background noise at the surface in Mol has been characterized. Based on the results, optimum conditions for signal transmission have been derived and data transmission experiments have been performed. Results show that despite large local interferences on the surface in Mol, wireless data transmission through 225 m of a geological medium is possible. Data transmission rates up to 100 bit/s has been successfully tested. The

  13. POST-CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 112: AREA 23 HAZARDOUS WASTE TRENCHES, NEVADA TEST SITE, NEVADA; FOR THE PERIOD OCTOBER 2003 - SEPTEMBER 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2004-01-01

    Corrective Action Unit (CAU) 112, Area 23 Hazardous Waste Trenches, Nevada Test Site (NTS), Nevada, is a Resource Conservation and Recovery Act (RCRA) unit located in Area 23 of the NTS. This annual Post-Closure Inspection and Monitoring Report provides the results of inspections and monitoring for CAU 112. This report includes a summary and analysis of the site inspections, repair and maintenance, meteorological information, and neutron soil moisture monitoring data obtained at CAU 112 for the current monitoring period, October 2003 through September 2004. Inspections of the CAU 112 RCRA unit were performed quarterly to identify any significant physical changes to the site that could impact the proper operation of the waste unit. The overall condition of the covers and facility was good, and no significant findings were observed. The annual subsidence survey of the elevation markers was conducted on August 23, 2004, and the results indicated that no cover subsidence4 has occurred at any of the markers. The elevations of the markers have been consistent for the past 11 years. The total precipitation for the current reporting period, october 2003 to September 2004, was 14.0 centimeters (cm) (5.5 inches [in]) (National Oceanographic and Atmospheric Administration, Air Resources Laboratory, Special Operations and Research Division, 2004). This is slightly below the average rainfall of 14.7 cm (5.79 in) over the same period from 1972 to 2004. Post-closure monitoring verifies that the CAU 112 trench covers are performing properly and that no water is infiltrating into or out of the waste trenches. Sail moisture measurements are obtained in the soil directly beneath the trenches and compared to baseline conditions for the first year of post-closure monitoring, which began in october 1993. neutron logging was performed twice during this monitoring period along 30 neutron access tubes to obtain soil moisture data and detect any changes that may indicate moisture movement

  14. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada, for Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    None

    2008-09-01

    This report presents data collected during the annual post-closure site inspection conducted at the Central Nevada Test Area Surface Corrective Action Unit (CAU) 417 in May 2007. The annual post-closure site inspection included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspection conducted at the UC-1 Central Mud Pit (CMP) indicated the site and soil cover were in good condition. No new cracks or fractures were observed in the soil cover during the annual inspection. A crack on the west portion of the cover was observed during the last quarterly inspection in December 2006. This crack was filled with bentonite as part of the maintenance activities conducted in February 2007 and will be monitored during subsequent annual inspections. The vegetation on the soil cover was adequate but showing signs of the area's ongoing drought. No issues were identified with the CMP fence, gate, or subsidence monuments. New DOE Office of Legacy Management signs with updated emergency phone numbers were installed as part of this annual inspection, no issues were identified with the warning signs and monuments at the other two UC-1 locations. The annual subsidence survey was conducted at UC-1 CMP and UC-4 Mud Pit C as part of the maintenance activities conducted in February 2007. The results of the subsidence surveys indicate that the covers are performing as expected, and no unusual subsidence was observed. A vegetation survey of the UC-1 CMP cover and adjacent areas was conducted as part of the annual inspection in May 2007. The vegetation survey indicated that revegetation continues to be successful, although stressed due to the area's prevailing drought conditions. The vegetation should continue to be monitored to document any changes in the plant community and to identify conditions that could potentially require remedial action to maintain a viable

  15. POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 417: CENTRAL NEVADA TEST AREA - SURFACE, HOT CREEK VALLEY, NEVADA, FOR CALENDAR YEAR 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA; NNSA NEVADA SITE OFFICE

    2005-04-01

    This post-closure inspection and monitoring report has been prepared according to the stipulations laid out in the Closure Report (CR) for Corrective Action Unit (CAU) 417, Central Nevada Test Area (CNTA)--Surface (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office [NNSA/NV], 2001), and the Federal Facility Agreement and Consent Order (FFACO, 1996). This report provides an analysis and summary of site inspections, subsidence surveys, meteorological information, and soil moisture monitoring data for CAU 417, which is located in Hot Creek Valley, Nye County, Nevada. This report covers Calendar Year 2004. Inspections at CAU 417 are conducted quarterly to document the physical condition of the UC-1, UC-3, and UC-4 soil covers, monuments, signs, fencing, and use restricted areas. The physical condition of fencing, monuments, and signs is noted, and any unusual conditions that could impact the integrity of the covers are reported. The objective of the soil moisture monitoring program is to monitor the stability of soil moisture conditions within the upper 1.2 meters (m) (4 feet [ft]) of the UC-1 Central Mud Pit (CMP) cover and detect changes that may be indicative of moisture movement exceeding the cover design performance expectations.

  16. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 342: Area 23 Mercury Fire Training Pit, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2006-01-01

    This report provides a summary and analysis of visual site inspections and soil gas sampling results for Corrective Action Unit (CAU) 342, Area 23 Mercury Fire Training Pit. CAU 342 is identified in the Federal Facility Agreement and Consent Order of 1996 and consists of Corrective Action Site 23-56-01, Former Mercury Fire Training Pit. This report covers calendar years 2004 and 2005. Visual site inspections were conducted on May 20 and November 14, 2004, and May 17 and November 15, 2005. No significant findings were observed during these inspections. The site was in good condition, and no repair activities were required. Soil gas samples were collected on November 29, 2005, for analysis of volatile organic compounds (VOCs) and semivolatile organic compounds (SVOCs), and samples were collected on December 1, 2005, for analysis of base gases. Base gas concentrations in the monitoring well show a high concentration of carbon dioxide and a low concentration of oxygen, which is an indication of biodegradation of total petroleum hydrocarbons (TPH) in the soil. Results for VOCs and SVOCs are unchanged, with VOCs below or near laboratory method detection limits and no SVOCs detected above laboratory method detection limits. Post-closure monitoring was required for six years after closure of the site. Therefore, since 2005 was the sixth year of monitoring, the effectiveness of natural attenuation of the TPH-impacted soil by biodegradation was evaluated. The base gas concentrations indicate that biodegradation of TPH in the soil is occurring; therefore, it is recommended that monitoring be discontinued. Visual site inspections should continue to be performed biannually to ensure that the signs are in place and readable and that the use restriction has been maintained. The results of the site inspections will be documented in a letter report and submitted annually

  17. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2006-08-01

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2005 through June 2006. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and UR warning signs was good. Settling was observed that exceeded the action level as specified in Section VILB.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Along the east edge of the cover (repaired previously in August 2003, December 2003, May 2004, October 2004), an area of settling was observed during the December 2005 inspection to again be above the action level, and required repair. This area and two other areas of settling on the cover that were first observed during the December 2005 inspection were repaired in February 2006. The semiannual subsidence surveys were done in September 2005 and March 2006. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.015 m [-0.05 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring on the cover. Soil moisture results obtained to date indicate that the CAU 110 cover is performing as expected. Time Domain Reflectometry (TDR) data indicated an increase in soil moisture (1

  18. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2006-01-01

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2005 through June 2006. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and UR warning signs was good. Settling was observed that exceeded the action level as specified in Section VILB.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Along the east edge of the cover (repaired previously in August 2003, December 2003, May 2004, October 2004), an area of settling was observed during the December 2005 inspection to again be above the action level, and required repair. This area and two other areas of settling on the cover that were first observed during the December 2005 inspection were repaired in February 2006. The semiannual subsidence surveys were done in September 2005 and March 2006. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.015 m [-0.05 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring on the cover. Soil moisture results obtained to date indicate that the CAU 110 cover is performing as expected. Time Domain Reflectometry (TDR) data indicated an increase in soil moisture (1

  19. POST-CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 91: AREA 3 U3 fi INJECTION WELL, NEVADA TEST SITE, NEVADA FOR THE PERIOD NOVEMBER 2003 - OCTOBER 2004

    International Nuclear Information System (INIS)

    2005-01-01

    This Post-Closure Inspection and Monitoring report provides an analysis and summary of inspections, meteorological information, and neutron soil moisture monitoring for Corrective Action Unit (CAU) 91: Area 3 U-3fi Injection Well, Nevada Test Site (NTS), Nevada. This report covers the annual period November 2003 through October 2004. Site inspections of CAU 91 are performed every six months to identify any significant changes that could impact the proper operation of the waste disposal unit. Inspection results for the current period indicate that the overall condition of the concrete pad, perimeter fence, and warning signs is good

  20. Calendar Year 2007 Resource Conservation and Recovery Act Annual Monitoring Report for the U.S. Department of Energy Y-12 National Security Complex, Oak Ridge, Tennessee - RCRA Post-Closure Permit Nos. TNHW-113, TNHW-116, and TNHW-128

    Energy Technology Data Exchange (ETDEWEB)

    Elvado Environmental

    2008-02-01

    This report contains groundwater quality monitoring data obtained during calendar year (CY) 2007 at the following hazardous waste treatment, storage, and disposal (TSD) units located at the US Department of Energy (DOE) Y-12 National Security Complex (hereafter referenced as Y-12) in Oak Ridge, Tennessee; this S-3 Site, Oil Landfarm, Bear Creek Burial Grounds/Walk-In Pits (BCBG/WIP), Eastern S-3 Site Plume, Chestnut Ridge Security Pits (CRSP), Chestnut Ridge Sediment Disposal Baste (CRSDB), few Hollow Quarry (KHQ), and East Chestnut Ridge Waste Pile (ECRWP). Hit monitoring data were obtained in accordance with the applicable Resource Conservation and Recovery Act of 1976 (RCRA) hazardous waste post-closure permit (PCP). The Tennessee Department of Environment and Conservation (TDEC) - Division of Solid Waste Management issued the PCPs to define the requirements for RCRA post-closure inspection, maintenance, and groundwater monitoring at the specified TSD units located within the Bear Creek Hydrogeologic Regime (PCP no. TNHW-116), Upper East Fork Poplar Creek Hydrogeologic Regime (PCP no. TNHW-113), and Chestnut Ridge Hydrogeologic Regime (PCP no. TNHW-128). Each PCP requires the Submittal of an annual RCRA groundwater monitoring report containing the groundwater sampling information and analytical results obtained at each applicable TSD unit during the preceding CY, along with an evaluation of groundwater low rates and directions and the analytical results for specified RCRA groundwater target compounds; this report is the RCRA annual groundwater monitoring report for CY 2007. The RCRA post-closure groundwater monitoring requirements specified in the above-referenced PCP for the Chestnut Ridge Regime replace those defined in the previous PCP (permit no. TNHW-088), which expired on September 18, 2005, but remained effective until the TDEC issued the new PCP in September 2006. The new PCP defines site-specific groundwater sampling and analysis requirements for the

  1. POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 417: CENTRAL NEVADA TEST AREA - SURFACE, HOT CREEK VALLEY, NEVADA; FOR CALENDAR YEAR 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-01

    Corrective Action Unit (CAU) 417, Central Nevada Test Area - Surface, is located in Hot Creek Valley in northern Nye County, Nevada, and consists of three areas commonly referred to as UC-1, UC-3, and UC-4. CAU 417 consists of 34 Corrective Action Sites (CASs) which were closed in 2000 (U. S. Department of Energy, National Nuclear Security Administration Nevada Operations Office, 2001). Three CASs at UC-1 were closed in place with administrative controls. At CAS 58-09-01, Central Mud Pit (CMP), a vegetated soil cover was constructed over the mud pit. At the remaining two sites CAS 58-09-02, Mud Pit and 58-09-05, Mud Pits (3), aboveground monuments and warning signs were installed to mark the CAS boundaries. Three CASs at UC-3 were closed in place with administrative controls. Aboveground monuments and warning signs were installed to mark the site boundaries at CAS 58-09-06, Mud Pits (5), CAS 58-25-01, Spill and CAS 58-10-01, Shaker Pad Area. Two CASs that consist of five sites at UC-4 were closed in place with administrative controls. At CAS 58-09-03, Mud Pits 9, an engineered soil cover was constructed over Mud Pit C. At the remaining three sites in CAS 58-09-03 and at CAS 58-10-05, Shaker Pad Area, aboveground monuments and warning signs were installed to mark the site boundaries. The remaining 26 CASs at CAU 417 were either clean-closed or closed by taking no further action. Quarterly post-closure inspections are performed at the CASs that were closed in place at UC-I, UC-3, and UC-4. During calendar year 2005, site inspections were performed on March 15, June 16, September 22, and December 7. The inspections conducted at the UC-1 CMP documented that the site was in good condition and continued to show integrity of the cover unit. No new cracks or fractures were observed until the December inspection. A crack on the west portion of the cover showed evidence of lateral expansion; however, it is not at an actionable level. The crack will be sealed by filling with

  2. POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 110: AREA 3 WMD U-3AX/BL CRATER, NEVADA TEST SITE, NEVADA FOR THE PERIOD JULY 2004 - JUNE 2005

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-08-01

    This Post-Closure Inspection and Monitoring report provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 Waste Management Division (WMD) U-3ax/bl Crater. This report includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2004 through June 2005. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and use restriction warning signs was good. Settling was observed that exceeded the action level as specified in Section VII.B.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (cm) (6 inches [in]) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection.

  3. First annual report RCRA post-closure monitoring and inspections for the U-3fi waste unit. Final report, July 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.

    1997-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi RCRA Unit, located in Area 3 of the Nevada Site (NTS), Nye County, Nevada during the July 1995 to October 1996 period. Inspections of the U-3fi RCRA Unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 420 ft ER3-3 borehole and detect changes that may be indicative of moisture movement in the regulated interval. This is the first annual report on the U-3fi closure and includes the first year baseline monitoring data as well as one quarter of compliance monitoring data

  4. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the period October 2000-July 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 2000--July 2001 monitoring period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in July 2001. There has been no subsidence at any of the markers since monitoring began eight years ago. Precipitation for the period October 2000 through July 2001 was 9.42 centimeters (cm) (3.71 inches [in]) (U.S. National Weather Service, 2001). The prior year annual rainfall (January 2000 through December 2000) was 10.44 cm (4.1 1 in.). The recorded average annual rainfall for this site from 1972 to January 2000 is 14.91 cm (5.87 in.). The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that may be indicative of moisture movement at a point located directly beneath each trench. All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the trenches

  5. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the Period October 1999-October 2000

    Energy Technology Data Exchange (ETDEWEB)

    D. F. Emer

    2001-03-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 1999-October 2000 period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in August 2000. There has been no subsidence at any of the markers since monitoring began seven years ago. The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that maybe indicative of moisture movement at a point located directly beneath each trench. Precipitation for the period October 1999 through October 2000 was 10.44 centimeters (cm) (4.11 inches [in.]) (U.S. National Weather Service, 2000). The prior year annual rainfall (January 1999 through December 1999) was 10.13cm (3.99 in.). The highest 30-day cumulative rainfall occurred on March 8, 2000, with a total of 6.63 cm (2.61 in.). The heaviest daily precipitation occurred on February 23,2000, with a total of 1.70 cm (0.67 in.) falling in that 24-hour period. The recorded average annual rainfall for this site, from 1972 to January 1999, is 15.06 cm (5.93 in.). All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the

  6. Financial risks of post-closure custodial care for the Barnwell radioactive waste disposal facility - 16155

    International Nuclear Information System (INIS)

    Baird, Robert D.; Newberry, William F.

    2009-01-01

    This paper reports evaluations of the adequacy of the Barnwell Extended Care Fund in light of identified risks, with the conclusion that the fund is sufficient to cover the costs and uncertainties associated with planned post-closure care of the Barnwell, South Carolina low-level radioactive waste disposal facility. It reviews background information pertinent to the facility's post-closure monitoring and maintenance and describes financial responsibility for post-closure activities. It identifies and briefly characterizes the activities planned to be conducted following facility closure and presents the midrange estimate of planned post-closure costs. The paper identifies and quantifies sources of uncertainty in activities and costs planned for post-closure care and presents 50-, 80-, and 95-percent confidence levels of planned costs. The fund is currently sufficient to cover some but not all of the costs that might be incurred as a result of unplanned events. The paper identifies, characterizes, and quantifies unplanned events, possible consequences, and probabilities of occurrence. The paper presents costs that might be incurred in responding to the unplanned initiating events and identifies levels of confidence that the fund is adequate to cover such costs. (authors)

  7. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada, For the Period July 2007-June 2008

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-08-01

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110 for the period July 2007 through June 2008. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, perimeter fence, and use restriction (UR) warning signs was good. However, settling was observed that exceeded the action level as specified in Section VII.B.7 of the Hazardous Waste Permit Number NEV HW021 (Nevada Division of Environmental Protection, 2005). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Two areas of settling and cracks were observed on the south and east edges of the cover during the September 2007 inspection that exceeded the action level and required repair. The areas were repaired in October 2007. Additional settling and cracks were observed along the east side of the cover during the December 2007 inspection that exceeded the action level, and the area was repaired in January 2008. Significant animal burrows were also observed during the March 2008 inspection, and small mammal trapping and relocation was performed in April 2008. The semiannual subsidence surveys were performed in September 2007 and March 2008. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.02 m [-0.08 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring overall on

  8. Interim status of closure/post-closure plan for 183-H solar evaporation basins

    International Nuclear Information System (INIS)

    1988-03-01

    This report describes a plan for decommissioning several solar evaporation basins on the Hanford reservation. The document describes procedures for sampling during decommissioning and a plan for certification of the resulting completed landfill. Additional plans deal with the training, security of the site, and post-closure monitoring

  9. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Silvas, A. J. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site; Lantow, Tiffany A. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site

    2015-03-25

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2014 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Photographs taken during inspections are included in Appendix D. The annual post-closure inspections were conducted on May 28, 2014. Maintenance was required at CAU 407. Animal burrows were backfilled and erosion repairs were performed. Vegetation monitoring was performed at CAU 407 in June 2014. The vegetation monitoring report is included in Appendix E.

  10. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-06-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

  11. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2008-01-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

  12. Design Alternative Evaluation No. 3: Post-Closure Ventilation

    International Nuclear Information System (INIS)

    Logan, R.C.

    1999-01-01

    The objective of this study is to provide input to the Enhanced Design Alternatives (EDA) for License Application Design Selection (LADS). Its purpose is to develop and evaluate conceptual designs for post-closure ventilation alternatives that enhance repository performance. Post-closure ventilation is expected to enhance repository performance by limiting the amount of water contacting the waste packages. Limiting the amount of water contacting the waste packages will reduce corrosion

  13. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 426: Cactus Spring Waste Trenches (TTR); (5) CAU 453: Area 9 UXO Landfill (TTR); (6) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR); and (7) CAU 487: Thunderwell Site (TTR). The annual post-closure inspections were conducted May 5-6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections

  14. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2010-05-28

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: · CAU 400: Bomblet Pit and Five Points Landfill (TTR) · CAU 407: Roller Coaster RadSafe Area (TTR) · CAU 424: Area 3 Landfill Complexes (TTR) · CAU 426: Cactus Spring Waste Trenches (TTR) · CAU 453: Area 9 UXO Landfill (TTR) · CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR) · CAU 487: Thunderwell Site (TTR) The annual post-closure inspections were conducted May 5–6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections required. Vegetation

  15. Post-Closure Inspection Report for the Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2007-06-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2006 and includes inspection and repair activities completed at the following nine CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 404: Roller Coaster Lagoons and Trench (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 426: Cactus Spring Waste Trenches (TTR); CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR). Post-closure inspections were conducted on May 9, 2006, May 31, 2006, and November 15, 2006. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2006, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 400, CAU 407, CAU 426, CAU 453, and CAU 487 in 2006. During the May inspection of CAU 400, it was identified that the east and west sections of chickenwire fencing beyond the standard fencing were damaged; they were repaired in June 2006. Also in June 2006, the southeast corner fence post and one warning sign at CAU 407 were reinforced and reattached, the perimeter fencing adjacent to the gate at CAU 426 was tightened, and large animal

  16. Post-Closure Inspection Report for the Tonopah Test Range, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2006 and includes inspection and repair activities completed at the following nine CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 404: Roller Coaster Lagoons and Trench (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 426: Cactus Spring Waste Trenches (TTR); CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR). Post-closure inspections were conducted on May 9, 2006, May 31, 2006, and November 15, 2006. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2006, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 400, CAU 407, CAU 426, CAU 453, and CAU 487 in 2006. During the May inspection of CAU 400, it was identified that the east and west sections of chickenwire fencing beyond the standard fencing were damaged; they were repaired in June 2006. Also in June 2006, the southeast corner fence post and one warning sign at CAU 407 were reinforced and reattached, the perimeter fencing adjacent to the gate at CAU 426 was tightened, and large animal

  17. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2011 and includes inspection and repair activities completed at the following CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 453: Area 9 UXO Landfill (TTR); and (5) CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Appendix B. The inspection checklists are included in Appendix C, field notes are included in Appendix D, and photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted May 3 and 4, 2011. Maintenance was performed at CAU 424, CAU 453, and CAU 487. At CAU 424, two surface grade monuments at Landfill Cell A3-3 could not be located during the inspection. The two monuments were located and marked with lava rock on July 13, 2011. At CAU 453, there was evidence of animal burrowing. Animal burrows were backfilled on July 13, 2011. At CAU 487, one use restriction warning sign was missing, and wording was faded on the remaining signs. A large animal burrow was also present. The signs were replaced, and the animal burrow was backfilled on July 12, 2011. As a best management practice, the use restriction warning signs at CAU 407 were replaced with standard Federal Facility Agreement and Consent Order signs on July 13, 2011. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2011, and the vegetation monitoring report is included in Appendix F.

  18. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-21

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2011 and includes inspection and repair activities completed at the following CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 453: Area 9 UXO Landfill (TTR); and (5) CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Appendix B. The inspection checklists are included in Appendix C, field notes are included in Appendix D, and photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted May 3 and 4, 2011. Maintenance was performed at CAU 424, CAU 453, and CAU 487. At CAU 424, two surface grade monuments at Landfill Cell A3-3 could not be located during the inspection. The two monuments were located and marked with lava rock on July 13, 2011. At CAU 453, there was evidence of animal burrowing. Animal burrows were backfilled on July 13, 2011. At CAU 487, one use restriction warning sign was missing, and wording was faded on the remaining signs. A large animal burrow was also present. The signs were replaced, and the animal burrow was backfilled on July 12, 2011. As a best management practice, the use restriction warning signs at CAU 407 were replaced with standard Federal Facility Agreement and Consent Order signs on July 13, 2011. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2011, and the vegetation monitoring report is included in Appendix F.

  19. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Silvas, A. J.

    2014-03-03

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2013 and includes inspection and repair activities completed at the following CAUs: • CAU 400: Bomblet Pit and Five Points Landfill (TTR) • CAU 407: Roller Coaster RadSafe Area (TTR) • CAU 424: Area 3 Landfill Complexes (TTR) • CAU 453: Area 9 UXO Landfill (TTR) • CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. Photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted on May 14, 2013. Maintenance was performed at CAU 400, CAU 424, and CAU 453. At CAU 400, animal burrows were backfilled. At CAU 424, erosion repairs were completed at Landfill Cell A3-3, subsidence was repaired at Landfill Cell A3-4, and additional lava rock was placed in high-traffic areas to mark the locations of the surface grade monuments at Landfill Cell A3-3 and Landfill Cell A3-8. At CAU 453, two areas of subsidence were repaired and animal burrows were backfilled. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2013. The vegetation monitoring report is included in Appendix F.

  20. Post-closure Safety of the Borehole Disposal Concept

    International Nuclear Information System (INIS)

    Little, R.

    2016-01-01

    Conclusion: • BDC post-closure safety assessments have been undertaken over last 15-20 years. • Consistent with best international practice and IAEA guidance: – used structure assessment approach; – peer reviewed; – iterative. • Built confidence in BDC as a safe long-term management option for DSRSs at both a generic and site-specific level

  1. 40 CFR 265.280 - Closure and post-closure.

    Science.gov (United States)

    2010-07-01

    ... contaminants caused by wind erosion; and (4) Compliance with § 265.276 concerning the growth of food-chain... and post-closure care objectives of paragraph (a) of this section: (1) Type and amount of hazardous..., including amount, frequency, and pH of precipitation; (5) Geological and soil profiles and surface and...

  2. Annual Report RCRA Post-Closure Monitoring and Inspections for Corrective Action Unit 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the Period October 2001 - October 2002

    International Nuclear Information System (INIS)

    Richardson, G.

    2003-01-01

    This annual monitoring and inspection report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2001 to October 2002 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 128-meter (m) (420-feet [ft]) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft)

  3. Post-Closure Monitoring Report for Corrective Action Unit 98, Frenchman Flat, Underground Test Area, Nevada National Security Site, Nevada for Calendar Year 2016 (January 2016–December 2016), Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Farnham, Irene [Navarro, Las Vegas, NV (United States)

    2017-06-01

    Corrective Action Unit (CAU) 98: Frenchman Flat on the Nevada National Security Site was the location of 10 underground nuclear tests. CAU 98 underwent a series of investigations and actions in accordance with the Federal Facility Agreement and Consent Order to assess contamination of groundwater by radionuclides from the tests. A Closure Report completed that process in 2016 and called for long-term monitoring, use restrictions (URs), and institutional controls to protect the public and environment from potential exposure to contaminated groundwater. Three types of monitoring are performed for CAU 98: water quality, water level, and institutional control. These are evaluated to determine whether the UR boundaries remain protective of human health and the environment, and to ensure that the regulatory boundary objectives are being met. Additionally, monitoring data are used to evaluate consistency with the groundwater flow and contaminant transport models because the contaminant boundaries (CBs) calculated with the models are the primary basis of the UR boundaries. In summary, the monitoring results from 2016 indicate the regulatory controls on the closure of CAU 98 remain effective in protection of human health and the environment. Recommendations resulting from this first year of monitoring activities include formally incorporating wells UE-5 PW-1, UE-5 PW-2, and UE-5 PW-3 into the groundwater-level monitoring network given their strategic location in the basin; and early development of a basis for trigger levels for the groundwater-level monitoring given the observed trends. Additionally, it is recommended to improve the Real Estate/Operations Permit process for capturing information important for evaluating the impact of activities on groundwater resources, and to shift the reporting requirement for this annual report from the second quarter of the federal fiscal year (end of March) to the second quarter of the calendar year (end of June).

  4. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the period October 2000-October 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2000 to October 2001 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron-logging program is to monitor the soil moisture conditions along the 128-meter (m) (420-ft) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft) or to detect changes that may be indicative of subsidence within the disposal unit itself

  5. Post-Closure Inspection Report for Corrective Action Unit 453: Area 9 UXO Landfill Tonopah Test Range, Nevada, Calendar Year 2000; TOPICAL

    International Nuclear Information System (INIS)

    K. B. Campbell

    2001-01-01

    Post-closure monitoring requirements for the Area 9 Unexploded Ordnance Landfill (Corrective Action Unit[CAU] 453) (Figure 1) are described in Closure Report for Corrective Action Unit 453: Area 9 UXO Landfill, Tonopah Test Range, Nevada, report number DOE/NV-284. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on August 5,1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on September 10,1999. Post-closure monitoring at CAU 453 consists of the following: (1) Site inspections done twice a year to evaluate the condition of the unit; (2) Verification that the site is secure; (3) Notice of any subsidence or deficiencies that may compromise the integrity of the unit; (4) Remedy of any deficiencies within 90 days of discovery; and (5) Preparation and submittal of an annual report. Site inspections were conducted on June 20, 2000 and November 21, 2000. Both site inspections were conducted after NDEP approval of the CR, and in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of the inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and inspection photographs are found in Attachment C

  6. Performance Assessment of a Post-Closure Pyrophoric Event

    International Nuclear Information System (INIS)

    Duguid, J.O.; Senger, R.K.; Leem, J.

    2002-01-01

    This paper describes analyses of a potential post-closure pyrophoric event in a waste package containing uranium metal spent fuel. The analyses include temperature at adjacent waste packages caused by the event and the dose to humans due to the event. The thermal analyses show that the event would not be expected to damage the adjacent waste packages. The dose analyses show that the doses due to the event are small. These analyses provide support to screening arguments used to demonstrate that the pyrophoric event should not be considered in the total system performance assessment model

  7. Post-closure resaturation of a deep radioactive waste repository

    International Nuclear Information System (INIS)

    Cox, I.C.S.; Rodwell, W.R.

    1989-03-01

    The post-closure resaturation of a deep radioactive waste repository has been modelled for a number of generic disposal concepts. A combination of numerical ground water flow simulations and analytical calculations has been used to investigate the variation of repository fluid pressure and degree of water saturation with time, and to determine the factors influencing resaturation times. The host rock permeability was found to be the most important determining factor. For geological environments regarded as likely for a waste repository, resaturation is predicted to be a short term process compared with gas generation and contaminant migration timescales. (author)

  8. Corrective Action Management Unit Report of Post-Closure Care Activities Calendar Year 2017.

    Energy Technology Data Exchange (ETDEWEB)

    Ziock, Robert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Little, Bonnie Colleen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-02-01

    The Corrective Action Management Unit (CAMU) at Sandia National Laboratories, New Mexico (SNL/NM) consists of a containment cell and ancillary systems that underwent regulatory closure in 2003 in accordance with the Closure Plan in Appendix D of the Class 3 Permit Modification (SNL/NM September 1997). The containment cell was closed with wastes in place. On January 27, 2015, the New Mexico Environment Department (NMED) issued the Hazardous Waste Facility Operating Permit (Permit) for Sandia National Laboratories (NMED January 2015). The Permit became effective February 26, 2015. The CAMU is undergoing post-closure care in accordance with the Permit, as revised and updated. This CAMU Report of Post-Closure Care Activities documents all activities and results for Calendar Year (CY) 2017 as required by the Permit. The CAMU containment cell consists of engineered barriers including a cover system, a bottom liner with a leachate collection and removal system (LCRS), and a vadose zone monitoring system (VZMS). The VZMS provides information on soil conditions under the cell for early leak detection. The VZMS consists of three monitoring subsystems, which include the primary subliner (PSL), a vertical sensor array (VSA), and the Chemical Waste Landfill (CWL) sanitary sewer (CSS) line. The PSL, VSA, and CSS monitoring subsystems are monitored quarterly for soil moisture concentration, the VSA is monitored quarterly for soil temperature, and the VSA and CSS monitoring subsystems are monitored annually for volatile organic compound (VOC) concentrations in the soil vapor at various depths. Baseline data for the soil moisture, soil temperature, and soil vapor were established between October 2003 and September 2004.

  9. POST-CLOSURE INSPECTION REPORT FOR THE TONOPAH TEST RANGE, NEVADA, FOR CALENDAR YEAR 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-04-01

    This Post-Closure Inspection Report provides an analysis and summary of the semi-annual inspections conducted at the Tonopah Test Range (TTR) during Calendar Year 2004. The report includes the inspection and/or repair activities completed at the following nine Corrective Action Units (CAUs) located at TTR, Nevada: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR) (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2,6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). Site inspections were conducted on July 7,2004, and November 9-10,2004. All inspections were conducted according to the post-closure plans in the approved Closure Reports (CRs). The post-closure inspection plan for each CAU is included in Appendix B, with the exception of CAU 400 and CAU 423. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. In addition, post-closure inspections are not currently required at CAU 423; however, the CR is being revised to include inspection requirements. The inspection checklists for each site inspection are included in Appendix C, the field notes are included in Appendix D, and the site photographs are included in Appendix E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2004, and the vegetation monitoring report is included in Appendix F. In addition, topographic survey results of two repaired landfill cells in CAU 424 are included in Appendix G. Maintenance and/or repairs were performed at the CAU 400 Five Points Landfill, CAU 407, CAU 424, CAU 427, and CAU 487. CAU 400 repairs included mending the fence, reseeding of a flood damaged area, and

  10. Post-closure radiation dose assessment for Yucca Mountain repository

    International Nuclear Information System (INIS)

    Jia Mingyan; Zhang Xiabin; Yang Chuncai

    2006-01-01

    A brief introduction of post-closure long-term radiation safety assessment results was represented for the yucca mountain high-level waste geographic disposal repository. In 1 million years after repository closure, for the higher temperature repository operating mode, the peak annual dose would be 150 millirem (120 millirem under the lower-temperature operating mode) to a reasonably maximally exposed individual approximately 18 kilometers (11 miles) from the repository. The analysis of a drilling intrusion event occurring at 30,000 years indicated a peak of the mean annual dose to the reasonably maximally exposed individual approximately 18 kilometers (11 miles) downstream of the repository would be 0.002 millirem. The analysis of an igneous activity scenario, including a volcanic eruption event and igneous intrusion event indicated a peak of the mean annual dose to the reasonably maximally exposed individual approximately 18 kilometers downstream of the repository would be 0.1 millirem. (authors)

  11. Integrating scientific results for a post-closure safety demonstration

    International Nuclear Information System (INIS)

    Taylor, E.C.; Ramspott, L.D.; Sinnock, S.; Sprecher, W.M.

    1994-01-01

    The U.S. Department of Energy (DOE) is developing a nuclear waste management system that will accept high-level radioactive waste, transport it, store it, and ultimately emplace it in a deep geologic repository. The key activity now is determining whether Yucca Mountain, Nevada is suitable as a site for the repository. If so, the crucial technological advance will be the demonstration that disposal of nuclear waste will be safe for thousands of years after closure. Recent regulatory, legal, and scientific developments imply that the safety demonstration must be simple. The scientific developments taken together support a simple set of hypotheses that constitute a post-closure safety argument for a repository at Yucca Mountain. If the understanding of Yucca Mountain hydrology presented in the Site Characterization Plan proves correct, then these hypotheses might be confirmed by combining results of Surface-Based Testing with early testing results in the Exploratory Studies Facility

  12. Performance Assessment of a Post-Closure Pyrophoric Event

    International Nuclear Information System (INIS)

    Duguid, James; Senger, R.; Leem, J.

    2001-01-01

    The U.S. Department of Energy (DOE) spent nuclear fuel (DSNF) is categorized into eleven different spent fuel groups. Group 7, is predominantly uranium metal spent fuel from N Reactor that could oxidize rapidly in the presence of air when a waste package is breached. Such rapid oxidation constitutes a pyrophoric event. The consequences of a post closure pyrophoric event were evaluated in terms of its potential to damage adjacent waste packages and consequences of it in terms of long-term dose to humans. This work was conducted as part of the total system performance assessment (TSPA) of DOE spent fuel for the National Spent Nuclear Fuel Program. These analyses were performed in support of the site recommendation for a repository at Yucca Mountain, Nevada

  13. Post-closure performance assessment treatment of the biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Broderick, M A [UK Nirex Ltd., Harwell, Oxfordshire (United Kingdom); Egan, M J [AEA Technology, Risley, Cheshire (United Kingdom); Thorne, M C [Electrowatt, Horsham, Sussex (United Kingdom); Williams, J A [AEA Technology, Risley, Cheshire (United Kingdom)

    1996-07-01

    The Nirex strategy for radioactive waste disposal is based on a system of engineered and natural barriers, providing long-term isolation of the waste from those parts of the environment that are in contact with or readily available for use by humans (i.e. the biosphere). Even so, there remains the possibility that, on a timescale of thousands to tens of thousands of years, small quantities of poorly-sorbed, long-lived radionuclides may be released from the engineered disposal system, ultimately to emerge into the biosphere. Biosphere models are used in post-closure performance assessments to quantify the competing effects of dilution and accumulation processes on radionuclide concentrations in the accessible environment. Understanding biosphere processes and their time dependence is necessary not only to determine the radiological impact of possible future releases, but also to characterise the dynamics of transport in groundwater and the location, duration and extent of any such releases. Nirex is developing a new biosphere model for use in post-closure radiological assessments for the proposed Sellafield repository. A compartment modelling approach has been adopted, as in studies performed previously, but the system will be dynamic, allowing changes with time in both the properties of compartments and the transfers between compartments. The transport model considers both mass transport within the biosphere and the migration of radionuclides, thereby ensuring that a self-consistent description of the biosphere, in a spatially-extensive domain is maintained. The above approach is designed to link the assessment models used by the Nirex assessment team more closely into the Nirex biosphere research programme than has hitherto been possible with time-invariant assessment models. (author)

  14. Post-closure performance assessment treatment of the biosphere

    International Nuclear Information System (INIS)

    Broderick, M.A.; Egan, M.J.; Thorne, M.C.; Williams, J.A.

    1996-01-01

    The Nirex strategy for radioactive waste disposal is based on a system of engineered and natural barriers, providing long-term isolation of the waste from those parts of the environment that are in contact with or readily available for use by humans (i.e. the biosphere). Even so, there remains the possibility that, on a timescale of thousands to tens of thousands of years, small quantities of poorly-sorbed, long-lived radionuclides may be released from the engineered disposal system, ultimately to emerge into the biosphere. Biosphere models are used in post-closure performance assessments to quantify the competing effects of dilution and accumulation processes on radionuclide concentrations in the accessible environment. Understanding biosphere processes and their time dependence is necessary not only to determine the radiological impact of possible future releases, but also to characterise the dynamics of transport in groundwater and the location, duration and extent of any such releases. Nirex is developing a new biosphere model for use in post-closure radiological assessments for the proposed Sellafield repository. A compartment modelling approach has been adopted, as in studies performed previously, but the system will be dynamic, allowing changes with time in both the properties of compartments and the transfers between compartments. The transport model considers both mass transport within the biosphere and the migration of radionuclides, thereby ensuring that a self-consistent description of the biosphere, in a spatially-extensive domain is maintained. The above approach is designed to link the assessment models used by the Nirex assessment team more closely into the Nirex biosphere research programme than has hitherto been possible with time-invariant assessment models. (author)

  15. Post-Closure Inspection Report for the Tonopah Test Range, Nevada. For Calendar Year 2015, Revision 0

    International Nuclear Information System (INIS)

    Matthews, Patrick; Petrello, Jaclyn

    2016-01-01

    This report provides the results of the annual post-closure inspections conducted at the closed corrective action units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2015 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved closure reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. The annual post-closure inspections were conducted on May 12, 2015. Maintenance was required at CAU 453. Cracking along the north trench was repaired. One monument is missing at CAU 424; it will be replaced in 2016. Postings at CAUs 407, 424, 453, and 487 contain contact information for TTR Security. It was noted that protocols may not be in place to ensure that the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) is notified if access is needed at these sites. NNSA/NFO is working with the U.S. Air Force and Sandia to determine whether more appropriate contact information or new protocols are warranted for each CAU. Based on these inspections, there has not been a significant change in vegetation, and vegetation monitoring was not recommended at CAU 400 or CAU 407 in 2015.

  16. Post-Closure Inspection Report for the Tonopah Test Range, Nevada. For Calendar Year 2015, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States); Petrello, Jaclyn [Navarro, Las Vegas, NV (United States)

    2016-03-01

    This report provides the results of the annual post-closure inspections conducted at the closed corrective action units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2015 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved closure reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. The annual post-closure inspections were conducted on May 12, 2015. Maintenance was required at CAU 453. Cracking along the north trench was repaired. One monument is missing at CAU 424; it will be replaced in 2016. Postings at CAUs 407, 424, 453, and 487 contain contact information for TTR Security. It was noted that protocols may not be in place to ensure that the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) is notified if access is needed at these sites. NNSA/NFO is working with the U.S. Air Force and Sandia to determine whether more appropriate contact information or new protocols are warranted for each CAU. Based on these inspections, there has not been a significant change in vegetation, and vegetation monitoring was not recommended at CAU 400 or CAU 407 in 2015.

  17. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments

  18. Proposed modifications to the RCRA post-closure permit for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Bear Creek Hydrogeologic Regime (BCHR). These permit conditions define the requirements for RCRA post-closure corrective action groundwater monitoring at the S-3 Ponds, the Oil Landfarm, and the Bear Creek Burial Grounds (units A, C-West, and Walk-in Pits). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for the Bear Creek Valley (BCV) Watershed, (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA post-closure corrective action monitoring program during 1996, and (3) update applicable technical procedures with revised versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP). With these modifications, the Y-12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2.0 provides the technical justification for each proposed permit modification. The proposed changes to permit language are provided in Section 3.0 (S-3 Ponds), Section 4.0 (Oil Landfarm), and Section 5.0 (Bear Creek Burial Grounds). Sections 6.0 and 7.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the PCP Attachments.

  19. Post-Closure Strategy for Use-Restricted Sites on the Nevada National Security Site, Nevada Test and Training Range, and Tonopah Test Range, Nevada

    International Nuclear Information System (INIS)

    Silvas, A. J.

    2014-01-01

    intended to be a permanent long-term stewardship plan. However, it is intended to clarify requirements and identify components to effectively manage the sites until regulatory requirements are met or management of the site changes. The Environmental Management Program is required to manage these sites until the NNSS Environmental Restoration program is completed, currently planned for 2030. Prior to completion of the Environmental Restoration program, additional planning will be conducted to ensure that long-term stewardship of the sites is maintained. A comprehensive post-closure plan can be transitioned effectively into any future site-wide long-term stewardship program that may be developed. Therefore, the post-closure plan will include current aspects of the post-closure program that are also important aspects of long-term stewardship, including the following: · Management of physical and engineering controls such as fences, signs, and soil covers · Management of institutional and administrative controls such as use restrictions and real estate systems · Management of monitoring and maintenance programs · Management of information related to the sites such as geographic information system data and related documentation The strategy will also allow for periodic review and modification of any aspect of the program to ensure continued effectiveness.

  20. Post-Closure Inspection Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench Tonopah Test Range, Nevada, Calendar Year 2000

    Energy Technology Data Exchange (ETDEWEB)

    K. B. Campbell

    2001-06-01

    Post-closure monitoring requirements for the Roller Coaster Sewage Lagoons and North Disposal Trench (Corrective Action Unit [CAW 404]) (Figure 1) are described in Closure Report for Corrective Action Unit 404, Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, report number DOE/NV--187. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on September 11, 1998. Permeability results of soils adjacent to the engineered cover and a request for closure of CAU 404 were transmitted to the NDEP on April 29, 1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on May 18, 1999. Post-closure monitoring at CAU 404 consists of the following: (1) Site inspections done twice a year to evaluate the condition of the unit; (2) Verification that the site is secure; (3) Notice of any subsidence or deficiencies that may compromise the integrity of the unit; (4) Remedy of any deficiencies within 90 days of discovery; and (5) Preparation and submittal of an annual report. Site inspections were conducted on June 19, 2000, and November 21, 2000. The site inspections were conducted after completion of the revegetation activities (October 30, 1997) and NDEP approval of the CR (May 18, 1999). All site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are found in Attachment C.

  1. Post-Closure Inspection Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench Tonopah Test Range, Nevada, Calendar Year 2000; TOPICAL

    International Nuclear Information System (INIS)

    K. B. Campbell

    2001-01-01

    Post-closure monitoring requirements for the Roller Coaster Sewage Lagoons and North Disposal Trench (Corrective Action Unit[CAW 404]) (Figure 1) are described in Closure Report for Corrective Action Unit 404, Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, report number DOE/NV-187. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on September 11, 1998. Permeability results of soils adjacent to the engineered cover and a request for closure of CAU 404 were transmitted to the NDEP on April 29, 1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on May 18, 1999. Post-closure monitoring at CAU 404 consists of the following: (1) Site inspections done twice a year to evaluate the condition of the unit; (2) Verification that the site is secure; (3) Notice of any subsidence or deficiencies that may compromise the integrity of the unit; (4) Remedy of any deficiencies within 90 days of discovery; and (5) Preparation and submittal of an annual report. Site inspections were conducted on June 19, 2000, and November 21, 2000. The site inspections were conducted after completion of the revegetation activities (October 30, 1997) and NDEP approval of the CR (May 18, 1999). All site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are found in Attachment C

  2. Tonopah Test Range Post-Closure Inspection Annual Report, Tonopah Test Range, Nevada, Calendar Year 2003

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Bechtel Nevada

    2004-04-01

    This post-closure inspection report provides documentation of the semiannual inspection activities, maintenance and repair activities, and conclusions and recommendations for calendar year 2003 for eight corrective action units located on the Tonopah Test Range, Nevada.

  3. POST-CLOSURE INSPECTION REPORT FOR THE TONOPAH TEST RANGE, NEVADA FOR CALENDAR YEAR 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-06-01

    This post-closure inspection report includes the results of inspections, maintenance and repair activities, and conclusions and recommendations for Calendar Year 2005 for nine Corrective Action Units located on the Tonopah Test Range , Nevada.

  4. 40 CFR 265.118 - Post-closure plan; amendment of plan.

    Science.gov (United States)

    2010-07-01

    ... mail. In addition, for facilities without approved post-closure plans, it must also be provided during... requirements. At the end of the specified period of suspension, the Regional Ad-min-is-tra-tor would then...

  5. Knowledge based ranking algorithm for comparative assessment of post-closure care needs of closed landfills

    International Nuclear Information System (INIS)

    Sizirici, Banu; Tansel, Berrin; Kumar, Vivek

    2011-01-01

    Post-closure care (PCC) activities at landfills include cap maintenance; water quality monitoring; maintenance and monitoring of the gas collection/control system, leachate collection system, groundwater monitoring wells, and surface water management system; and general site maintenance. The objective of this study was to develop an integrated data and knowledge based decision making tool for preliminary estimation of PCC needs at closed landfills. To develop the decision making tool, 11 categories of parameters were identified as critical areas which could affect future PCC needs. Each category was further analyzed by detailed questions which could be answered with limited data and knowledge about the site, its history, location, and site specific characteristics. Depending on the existing knowledge base, a score was assigned to each question (on a scale 1-10, as 1 being the best and 10 being the worst). Each category was also assigned a weight based on its relative importance on the site conditions and PCC needs. The overall landfill score was obtained from the total weighted sum attained. Based on the overall score, landfill conditions could be categorized as critical, acceptable, or good. Critical condition indicates that the landfill may be a threat to the human health and the environment and necessary steps should be taken. Acceptable condition indicates that the landfill is currently stable and the monitoring should be continued. Good condition indicates that the landfill is stable and the monitoring activities can be reduced in the future. The knowledge base algorithm was applied to two case study landfills for preliminary assessment of PCC performance.

  6. Knowledge based ranking algorithm for comparative assessment of post-closure care needs of closed landfills.

    Science.gov (United States)

    Sizirici, Banu; Tansel, Berrin; Kumar, Vivek

    2011-06-01

    Post-closure care (PCC) activities at landfills include cap maintenance; water quality monitoring; maintenance and monitoring of the gas collection/control system, leachate collection system, groundwater monitoring wells, and surface water management system; and general site maintenance. The objective of this study was to develop an integrated data and knowledge based decision making tool for preliminary estimation of PCC needs at closed landfills. To develop the decision making tool, 11 categories of parameters were identified as critical areas which could affect future PCC needs. Each category was further analyzed by detailed questions which could be answered with limited data and knowledge about the site, its history, location, and site specific characteristics. Depending on the existing knowledge base, a score was assigned to each question (on a scale 1-10, as 1 being the best and 10 being the worst). Each category was also assigned a weight based on its relative importance on the site conditions and PCC needs. The overall landfill score was obtained from the total weighted sum attained. Based on the overall score, landfill conditions could be categorized as critical, acceptable, or good. Critical condition indicates that the landfill may be a threat to the human health and the environment and necessary steps should be taken. Acceptable condition indicates that the landfill is currently stable and the monitoring should be continued. Good condition indicates that the landfill is stable and the monitoring activities can be reduced in the future. The knowledge base algorithm was applied to two case study landfills for preliminary assessment of PCC performance. Copyright © 2011 Elsevier Ltd. All rights reserved.

  7. Considering timescales in the post-closure safety of geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    2009-01-01

    A key challenge in the development of safety cases for the deep geological disposal of radioactive waste is handling the long time frame over which the radioactive waste remains hazardous. The intrinsic hazard of the waste decreases with time, but some hazard remains for extremely long periods. Safety cases for geological disposal typically address performance and protection for thousands to millions of years into the future. Over such periods, a wide range of events and processes operating over many different timescales may impact on a repository and its environment. Uncertainties in the predictability of such factors increase with time, making it increasingly difficult to provide definite assurances of a repository's performance and the protection it may provide over longer timescales. Timescales, the level of protection and the assurance of safety are all linked. Approaches to handling timescales for the geological disposal of radioactive waste are influenced by ethical principles, the evolution of the hazard over time, uncertainties in the evolution of the disposal system (and how these uncertainties themselves evolve) and the stability and predictability of the geological environment. Conversely, the approach to handling timescales can affect aspects of repository planning and implementation including regulatory requirements, siting decisions, repository design, the development and presentation of safety cases and the planning of pre- and post-closure institutional controls such as monitoring requirements. This is an area still under discussion among NEA member countries. This report reviews the current status and ongoing discussions of this issue. (author)

  8. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada, for Fiscal Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Silvas, Alissa J. [Nevada Field Office, Las Vegas, NV (United States)

    2015-01-01

    This report serves as the combined annual report for post-closure activities for several Corrective Action Units (CAUs). The locations of the sites are shown in Figure 1. This report covers fiscal year 2014 (October 2013–September 2014). The post-closure requirements for these sites are described in Resource Conservation and Recovery Act Permit Number NEV HW0101 and summarized in each CAU-specific section in Section 1.0 of this report. The results of the inspections, a summary of maintenance activities, and an evaluation of monitoring data are presented in this report. Site inspections are conducted semiannually at CAUs 90 and 91 and quarterly at CAUs 92, 110, 111, and 112. Additional inspections are conducted at CAU 92 if precipitation occurs in excess of 0.50 inches (in.) in a 24-hour period and at CAU 111 if precipitation occurs in excess of 1.0 in. in a 24-hour period. Inspections include an evaluation of the condition of the units, including covers, fences, signs, gates, and locks. In addition to visual inspections, soil moisture monitoring, vegetation evaluations, and subsidence surveys are conducted at CAU 110. At CAU 111, soil moisture monitoring, vegetation evaluations, subsidence surveys, direct radiation monitoring, air monitoring, radon flux monitoring, and groundwater monitoring are conducted. The results of the vegetation surveys and an analysis of the soil moisture monitoring data at CAU 110 are presented in this report. Results of additional monitoring at CAU 111 are documented annually in the Nevada National Security Site Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites and in the Nevada National Security Site Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site, which will be prepared in approximately June 2015. All required inspections, maintenance, and monitoring were conducted in accordance with the post-closure requirements of the permit. It is recommended to continue

  9. Safe disposal of radioactive waste. Post-closure safety assessment of permanent repository in Novi han

    International Nuclear Information System (INIS)

    Mateeva, M.

    2007-01-01

    A presented material is the third part of the monograph with title 'Safe disposal of radioactive waste. Post-closure safety assessment of the permanent repository in Novi Han'. This part deals with review of the scenario selection procedure. The process system of permanent repository for radioactive waste is describing in details for different levels. Preliminary screening process of features, events and processes is presented here. Interaction matrixes for basic disposal system components are constructed. Final selection and grouping between the included features, events and processes is done. Selected and defined scenarios for post-closure safety assessment are presented too. Key words: post-closure safety assessment, scenario generation procedure, process system, process influence diagram, and interaction matrix

  10. Proposed modifications to the RCRA post-closure permit for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Chestnut Ridge Hydrogeologic Regime (CRHR) (permit number TNHW-088, EPA ID No. TN3 89 009 0001). These permit conditions define the requirements for RCRA post-closure detection groundwater monitoring at the Chestnut Ridge Sediment Disposal Basin (CRSDB) and Kerr Hollow Quarry (KHQ), and RCRA post-closure corrective action groundwater monitoring at the Chestnut Ridge Security Pits (CRSPs). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring at the CRSPs with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) record of decision (ROD), (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA monitoring programs during 1996, (3) replace several of the technical procedures included in the PCP with updated versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP), and (4) correct inaccurate regulatory citations and references to permit conditions and permit attachments. With these modifications, the Y- 12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2 provides the technical justification for each proposed permit modification. Section 3.0 contains proposed changes to Section II of the PCP. Modifications to site-specific permit conditions are presented in Section 4.0 (CRSDB), Section 5.0 (CRSPs), and Section 6.0 (KHQ). Sections 7.0 and 8.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the permit attachments

  11. Proposed modifications to the RCRA post-closure permit for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to several conditions of the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Chestnut Ridge Hydrogeologic Regime (CRHR) (permit number TNHW-088, EPA ID No. TN3 89 009 0001). These permit conditions define the requirements for RCRA post-closure detection groundwater monitoring at the Chestnut Ridge Sediment Disposal Basin (CRSDB) and Kerr Hollow Quarry (KHQ), and RCRA post-closure corrective action groundwater monitoring at the Chestnut Ridge Security Pits (CRSPs). Modification of these PCP conditions is requested to: (1) clarify the planned integration of RCRA post-closure corrective action groundwater monitoring at the CRSPs with the monitoring program to be established in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) record of decision (ROD), (2) revise several of the current technical requirements for groundwater monitoring based on implementation of the RCRA monitoring programs during 1996, (3) replace several of the technical procedures included in the PCP with updated versions recently issued by the Y-12 Plant Groundwater Protection Program (GWPP), and (4) correct inaccurate regulatory citations and references to permit conditions and permit attachments. With these modifications, the Y- 12 Plant will continue to meet the full intent of all regulatory obligations for post-closure care of these facilities. Section 2 provides the technical justification for each proposed permit modification. Section 3.0 contains proposed changes to Section II of the PCP. Modifications to site-specific permit conditions are presented in Section 4.0 (CRSDB), Section 5.0 (CRSPs), and Section 6.0 (KHQ). Sections 7.0 and 8.0 reference updated and revised procedures for groundwater sampling, and monitoring well plugging and abandonment, respectively. Appendix A includes all proposed revisions to the permit attachments.

  12. 40 CFR 264.228 - Closure and post-closure care.

    Science.gov (United States)

    2010-07-01

    ... remaining wastes to a bearing capacity sufficient to support final cover; and (iii) Cover the surface....112 must include both a plan for complying with paragraph (a)(1) of this section and a contingent plan... practicably removed at closure; and (ii) The owner or operator must prepare a contingent post-closure plan...

  13. 40 CFR 258.61 - Post-closure care requirements.

    Science.gov (United States)

    2010-07-01

    ... the final cover; (2) Maintaining and operating the leachate collection system in accordance with the...) Maintaining and operating the gas monitoring system in accordance with the requirements of § 258.23. (b) The... stop managing leachate if the owner or operator demonstrates that leachate no longer poses a threat to...

  14. Calculation of Post-Closure Natural Convection Heat and Mass Transfer in Yucca Mountain Drifts

    International Nuclear Information System (INIS)

    Webb, S.; Itamura, M.

    2004-01-01

    Natural convection heat and mass transfer under post-closure conditions has been calculated for Yucca Mountain drifts using the computational fluid dynamics (CFD) code FLUENT. Calculations have been performed for 300, 1000, 3000, and 10,000 years after repository closure. Effective dispersion coefficients that can be used to calculate mass transfer in the drift have been evaluated as a function of time and boundary temperature tilt

  15. An approach to handling timescales in post-closure safety assessment

    International Nuclear Information System (INIS)

    Bailey, L.; Littleboy, A.

    2002-01-01

    Previous Nirex post-closure assessments of deep geological disposal have been based on the use of probabilistic safety analysis covering many millions of years. However, Nirex has also published an assessment methodology in which the assessment timescale is divided into a number of discrete periods of time (time frames). Nirex is currently at the stage of planning the next update to its generic post-closure performance assessment and is considering the merits of using an assessment methodology based on time frames, in order to improve links with operational assessments and the provision of advice on the packaging of wastes, and to encourage stakeholder dialogue. This paper has been prepared as part of Nirex's aim, wherever possible, to 'preview', or seek input from others on, its ideas for new work to generate discussion and feedback. It describes an evolution of Nirex's published assessment methodology and outlines how it could be applied in an updated post-closure performance assessment of the Nirex generic phased disposal concept. (authors)

  16. Post-closure permit application for the Chestnut Ridge Sediment Disposal Basin at the Y-12 Plant

    International Nuclear Information System (INIS)

    Greer, J.K. Jr.; Kimbrough, C.W.

    1989-01-01

    This report contains information related to the closure and post closure of the Chestnut Ridge Sediment Disposal Basin of the Y-12 plant. Information concerning the background of the basin, geology, hydrology, and analysis of the sediments is included

  17. Post-Closure Inspection Report for Corrective Action Unit 424: Area 3 Landfill Complexes Tonopah Test Range, Nevada Calendar Year 2001; TOPICAL

    International Nuclear Information System (INIS)

    K. B. Campbell

    2002-01-01

    Corrective Action Unit (CAU) 424, the Area 3 Landfill Complexes at Tonopah Test Range, consists of eight Corrective Action Sites (CASs), seven of which are landfill cells that were closed previously by capping. (The eighth CAS, A3-7, was not used as a landfill site and was closed without taking any corrective action.) Figure 1 shows the general location of the landfill cells. Figure 2 shows in more detail the location of the eight landfill cells. CAU 424 closure activities included removing small volumes of soil containing petroleum hydrocarbons, repairing cell covers that were cracked or had subsided, and installing above-grade and at-grade monuments marking the comers of the landfill cells. Post-closure monitoring requirements for CAU 424 are detailed in Section 5.0, Post-Closure Inspection Plan, contained in the Closure Report for Corrective Action Unit 424: Area 3 Landfill Complexes, Tonopah Test Range, Nevada, report number DOE/NV-283, July 1999. The Closure Report (CR) was approved by the Nevada Division of Environmental Protection (NDEP) in July 1999. The CR includes compaction and permeability results of soils that cap the seven landfill cells. As stated in Section 5.0 of the NDEP-approved CR, post-closure monitoring at CAU 424 consists of the following: (1) Site inspections conducted twice a year to evaluate the condition of the unit. (2) Verification that landfill markers and warning signs are in-place, intact, and readable. (3) Notice of any subsidence, erosion, unauthorized use, or deficiencies that may compromise the integrity of the landfill covers. (4) Remedy of any deficiencies within 90 days of discovery. (5) Preparation and submittal of an annual report. Site inspections were conducted on May 16, 2001, and November 6, 2001. The inspections were preformed after the NDEP approval of the CR. This report includes copies of the inspection checklist, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in

  18. Novi Han Radioactive Waste Repository post-closure safety assessment, ver.2

    International Nuclear Information System (INIS)

    Mateeva, M.

    2003-01-01

    The methodology for the post-closure safety assessment is presented. The assessment context includes regulatory framework (protection principles); scope and time frame; radiological and technical requirements; modeling etc. The description of the Novi Han disposal system contains site location. meteorological, hydrological and seismological characteristics; waste and repository description and human activities characteristics. The next step in the methodology is scenario development and justification. The systematic generation os exposure scenarios is considered as central to the post-closure safety assessment. The most important requirements for the systematic scenario generation approach are: transparency, comprehensiveness (all possible FEPs influencing the the disposal system and the radionuclide release should be considered); relevant future evolutions; identification of critical issues and investigation of the robustness of the system. For the source-pathway-receptor analysis the Process System is divided into near-field, geosphere/atmosphere and biosphere, describing the key facets controlling the potential radionuclide migration to the environment. The schematic division of the Novi Han near-field Process System into lower-level conceptual features is presented and discussed. As a result of the examinations of the FEPs three classes of scenarios are identified for the Novi Han post-closure safety assessment: Environmental evolution scenarios (geological change and climate change); future human action scenarios (human intrusion and archaeological action); Scenarios with very low probability (terrorism, crashes, explosions). The safety assessment iteration leads to identification of a modern scenario generation approach, assessment of key radionuclide releases, geological and hydrological evaluation, identification of the key parameters from sensitivity analysis etc. Examples of conceptual models are given. For the mathematical modeling the AMBER code is used

  19. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2010

    International Nuclear Information System (INIS)

    2011-01-01

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2010 and includes inspection and repair activities completed at the following seven CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 426: Cactus Spring Waste Trenches (TTR); (5) CAU 453: Area 9 UXO Landfill (TTR); (6) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR); and (7) CAU 487: Thunderwell Site (TTR).

  20. Development of database and QA systems for post closure performance assessment on a potential HLW repository

    International Nuclear Information System (INIS)

    Hwang, Y. S.; Kim, S. G.; Kang, C. H.

    2002-01-01

    In TSPA of long-term post closure radiological safety on permanent disposal of HLW in Korea, appropriate management of input and output data through QA is necessary. The robust QA system is developed using the T2R3 principles applicable for five major steps in R and D's. The proposed system is implemented in the web-based system so that all participants in TSRA are able to access the system. In addition, the internet based input database for TSPA is developed. Currently data from literature surveys, domestic laboratory and field experiments as well as expert elicitation are applied for TSPA

  1. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2013-01-28

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2012 and includes inspection and repair activities completed at the following CAUs: · CAU 400: Bomblet Pit and Five Points Landfill (TTR) · CAU 407: Roller Coaster RadSafe Area (TTR) · CAU 424: Area 3 Landfill Complexes (TTR) · CAU 453: Area 9 UXO Landfill (TTR) · CAU 487: Thunderwell Site (TTR)

  2. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada: For Fiscal Year 2015 (October 2014–September 2015), Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States)

    2016-03-01

    This report serves as the combined annual report for post-closure activities for the following closed corrective action units (CAUs); CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well; CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and CAU 112, Area 23 Hazardous Waste Trenches. This report covers fiscal year 2015 (October 2014 through September 2015). The post-closure requirements for these sites are described in Resource Conservation and Recovery Act Permit Number NEV HW0101 and are summarized in each CAU-specific section in Section 1.0 of this report. The results of the inspections, a summary of maintenance activities, and an evaluation of monitoring data are presented in this report.

  3. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada: For Fiscal Year 2015 (October 2014-September 2015), Revision 0

    International Nuclear Information System (INIS)

    Matthews, Patrick

    2016-01-01

    This report serves as the combined annual report for post-closure activities for the following closed corrective action units (CAUs); CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well; CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and CAU 112, Area 23 Hazardous Waste Trenches. This report covers fiscal year 2015 (October 2014 through September 2015). The post-closure requirements for these sites are described in Resource Conservation and Recovery Act Permit Number NEV HW0101 and are summarized in each CAU-specific section in Section 1.0 of this report. The results of the inspections, a summary of maintenance activities, and an evaluation of monitoring data are presented in this report.

  4. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2008

    International Nuclear Information System (INIS)

    2009-01-01

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2008 and includes inspection and repair activities completed at the following ten CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR) CAU 404: Roller Coaster Lagoons and Trench (TTR) CAU 407: Roller Coaster RadSafe Area (TTR) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR) CAU 424: Area 3 Landfill Complexes (TTR) CAU 426: Cactus Spring Waste Trenches (TTR) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR) CAU 453: Area 9 UXO Landfill (TTR) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR) CAU 487: Thunderwell Site (TTR)

  5. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2008

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2009-03-19

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2008 and includes inspection and repair activities completed at the following ten CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR) CAU 404: Roller Coaster Lagoons and Trench (TTR) CAU 407: Roller Coaster RadSafe Area (TTR) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR) CAU 424: Area 3 Landfill Complexes (TTR) CAU 426: Cactus Spring Waste Trenches (TTR) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR) CAU 453: Area 9 UXO Landfill (TTR) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR) CAU 487: Thunderwell Site (TTR)

  6. Making the post-closure safety case for the proposed yucca mountain repository

    International Nuclear Information System (INIS)

    Swift, P.; Van Luik, A.

    2008-01-01

    This presentation provided an overview of the Yucca Mountain repository post-closure safety case. The safety case concept is being integrated into the license application being prepared for Yucca Mountain, by giving particularly close attention to the treatment of uncertainties, thereby bringing available lines of evidence into the supporting information, as appropriate, to build a comprehensive argument for safety and regulatory compliance. For Yucca Mountain, it is expected that there will be open questions in the safety case to be presented to the regulator and a programme will be outlined on what information is to be gathered (and how) prior to the next iteration in the licensing process to address such open issues. A one-hundred year operational phase is foreseen and planned, and the changes in knowledge and approaches that occur over time will have to be accommodated through the formal licensing process. (authors)

  7. The 2002 Drigg post-closure safety case: implementation of a multiple factor safety case

    International Nuclear Information System (INIS)

    Lean, C.B.; Grimwood, P.D.; Watts, L.; Fowler, L.; Thomson, G.; Kelly, E.; Hodgkinson, D.

    2004-01-01

    British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site, which is the UK's principal facility for the disposal of low level radioactive waste (LLW). Disposals are carried out under the terms of an authorization granted by the UK Environment Agency (the Agency). The Agency periodically reviews the authorization to take account of new information and any revisions to regulatory requirements. In September 2002 new Operational Environmental and Post-Closure Safety Cases (OESC and PCSC respectively) were submitted to the Agency to support the next authorization review. The OESC assesses radiological safety aspects up until closure of the site, including a post-operational management phase, whilst the PCSC considers the longer-term radiological safety. The Drigg disposal facility has been operational since 1959. For the first 3 decades of operations, disposals were solely by tumble tipping wastes into excavated trenches. This was phased out in favour of vault disposal and disposals to the trenches were completed in 1995. The first vault (Vault 8) commenced operations in 1988 and construction of future vaults is planned up to the estimated end of disposal operations in about 50 years time. This paper describes the main components of the 2002 Drigg PCSC and how they relate to each other. Central to the safety case is a systematic comprehensive post-closure radiological safety assessment (PCRSA). However, the importance of the more qualitative aspects of the safety case, including a demonstration of optimisation, is also highlighted. In addition, other confidence-building activities which are key to developing and presenting the safety case are discussed. (author)

  8. Consideration of post-closure controls for a near surface low level waste disposal site

    International Nuclear Information System (INIS)

    Clegg, R.; Pinner, A.; Smith, A.; Quartermaine, J.

    1997-01-01

    There is currently an ongoing programme of disposal of low level radioactive wastes by British Nuclear Fuels plc (BNFL) at Drigg, Cumbria, and this programme is likely to continue through the first few decades of the 21st century. Although control of the site is anticipated for a period of about 100 years post-closure, eventually restrictions on access will lapse. Thereafter, the possibility of human actions leading to exposure to, and/or exhumation of, the wastes exists and has to be addressed in post-closure radiological performance assessments. Potential modes of intrusion into the Drigg site have been studied using a suite of computer codes developed specifically for this purpose. Required inputs to these codes include information on possible future uses of the site and the various human actions associated with those uses. This information was obtained from a group of experts using formal elicitation procedures. Although the most likely site uses, notably those involving agricultural activities, are unlikely to result in intrusion into the wastes, others, such a urban development, do have the potential to result in such intrusion. In these circumstances, it seemed appropriate to give consideration to the degree to which documentary records and markers could protect the Drigg site against intrusive activities. Overall, it is concluded that provided that a variety of documentary records are established, ranging from local council archives to mass produced maps, then memory of the site can realistically be assumed whilst civilization continues to exist. However, if this first line of defence fails, markers constitute a second warning system. Finally, assessment calculations can be used to demonstrate that, even if these two lines of defence fail, risks from intrusion and radiation doses contingent upon intrusive events having occurred would not be unacceptably large. (author). 10 refs, 1 fig., 1 tab

  9. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Lee, Seunghee; Kim, Juyoul

    2017-01-01

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

  10. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seunghee; Kim, Juyoul, E-mail: gracemi@fnctech.com

    2017-03-15

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • {sup 14}C, {sup 226}Ra, {sup 241}Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing {sup 14}C, {sup 226}Ra and {sup 241}Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10{sup −7} mSv/yr, for both disposal options and satisfied the regulatory limit

  11. What do implementers need in terms of regulatory safety criteria for the post-closure phase?

    International Nuclear Information System (INIS)

    Cahen, B.

    2010-01-01

    Bruno Cahen, Director Safety Division (ANDRA) presented the point of view of the NEA Integration Group for the Safety Case (IGSC) on 'What do implementers need in terms of regulatory safety criteria for the post-closure phase?' B. Cahen acknowledged that the national experience in siting and developing conceptual designs of geological disposal is growing rapidly. It implies increasing opportunities for interactions between implementers and regulators. There has been large development of international guidance in the recent years. Many regulators have already developed a regulatory framework. The implementers need practical, transparent and deliverable regulations. These regulations should draw on experiences gained from development of geological disposal projects. The IGSC has identified five key questions that the RF may focus on: 1. Over what time frame are the waste deemed to present a hazard? 2. Over what time frames are regulatory criteria applied and do they change over time? 3. Over what time frame(s) are safety assessments required to be conducted? 4. How do implementers have to address uncertainties in the long time frames? 5. What happens after cut-offs: are additional analyses needed? What types of arguments are to be used? Stable, understandable and practical criteria mean, namely, that they need to be developed on a strong scientific and societal basis, that there is consistency of safety options and requirements for different types of waste, that, in the longer time frames, the emphasis is given to robust systems, passive safety and multiple safety functions and that the criteria should fit the various phases of the project (siting, designing, operating, closure and post-closure). Experience feedback from safety cases shows that safety priorities depend very much on time frames. The derived safety criteria for the individual components should lead to measurable, verifiable specifications. The assessment of geological repository post-closure safety

  12. Fall 2010 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility and the CPP 601/627/640 Facility at the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Boehmer, Ann

    2010-11-01

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment. The post closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report, as agreed between the Idaho Cleanup Project and Idaho Department of Environmental Quality. The Permit Condition III.H. portion of this report includes a description and the results of field methods associated with groundwater monitoring of the Waste Calcining Facility. Analytical results from groundwater sampling, results of inspections and maintenance of monitoring wells in the Waste Calcining Facility groundwater monitoring network, and results of inspections of the concrete cap are summarized. The Permit Condition I.U. portion of this report includes noncompliances not otherwise required to be reported under Permit Condition I.R. (advance notice of planned changes to facility activity which may result in a noncompliance) or Permit Condition I.T. (reporting of noncompliances which may endanger human health or the environment). This report also provides groundwater sampling results for wells that were installed and monitored as part of the Phase 1 post-closure period of the landfill closure components in accordance with HWMA/RCRA Landfill Closure Plan for the CPP-601 Deep

  13. Post-Closure Inspection Letter Report for Corrective Action Unit 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, Revision 0, January 2007

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This letter selves as the post closure monitoring letter report for the above CAU for the period October 2005 - September 2006. Quarterly inspections were conducted on December 12,2005, on March 23, 2006, on June 20,2006, and on September 19,2006, to observe the condition of the gate, use-restriction warning signs, monuments, fencing, trenches, soil covers, and monitoring well covers. The first inspection was conducted on December 12, 2005. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The second inspection was conducted on March 23, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The third inspection was conducted on June 20, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The fourth inspection was conducted on September 19, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended

  14. SR 97: post-closure safety of a deep repository for spent nuclear fuel in Sweden

    International Nuclear Information System (INIS)

    2000-01-01

    A major activity of the Nuclear Energy Agency (NEA) in the field of radioactive waste management is the organisation of independent, international peer reviews of national studies and projects. The NEA peer reviews help national programmes to assess their achievements. The review reports also provide reference information to be shared with others on what is desirable and what is feasible. This report presents the common views of the International Review Team (IRT) established by the NEA Secretariat on behalf of the Swedish Nuclear Power Inspectorate (SKI) to perform a peer review of a post-closure safety study of a deep repository for spent nuclear fuel in Sweden, Safety Report 97, produced by the Swedish Spent Fuel and Waste Management Company (SKB). The review is based on the main reports of the project and supporting documents, on information exchanged with SKB staff both through the intermediary of SKI and in direct interaction at a week-long workshop in Sweden, on a visit of the SKB's Aespoe Hard Rock Laboratory and Canister Laboratory, as well as on internal discussions within the IRT. (authors)

  15. NEA perspectives on timescales and criteria in post-closure safety of geological disposal

    International Nuclear Information System (INIS)

    Preter, P. de; Smith, P.; Pescatore, C.; Forinash, B.

    2006-01-01

    A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

  16. NEA perspectives on timescales and criteria in post-closure safety of geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    Preter, P. de [ONDRAF/NIRAS, Brussels (Belgium); Smith, P. [Safety Assessment Management Ltd, SAM Ltd. (United Kingdom); Pescatore, C.; Forinash, B. [OECD/NEA, Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

    2006-07-01

    A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

  17. The treatment of climate-driven environmental change and associated uncertainty in post-closure assessments

    International Nuclear Information System (INIS)

    Wilmot, R.D.

    1993-01-01

    The post-closure performance of radioactive waste repositories is influenced by a range of processes such as groundwater flow and fracture movement which are in turn affected by conditions in the surface environment. For deep repositories the period for which an assessment must be performed is in the order of 10 6 years. The geological record of the last 10 6 years shows that surface environmental conditions have varied considerably over such time-scales. A model of surface environmental change, known as TIME4, has been developed on behalf of the UK Department of the Environment for use with the probabilistic risk assessment code VANDAL. This paper describes the extent of surface environmental change, discusses possible driving mechanisms for such changes and summarises the processes which have been incorporated within the TIME4 model. The underlying cause of change in surface environment sub-systems is inferred to be climate change but considerable uncertainty remains over the mechanisms of such change. Methods for treating these uncertainties are described. (author)

  18. Chemical Waste Landfill Annual Post-Closure Care Report Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Michael Marquand [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Little, Bonnie Colleen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-03-01

    The CWL is a 1.9-acre remediated interim status landfill located in the southeastern corner of SNL/NM Technical Area III (Figures 2-1 and 2-2) undergoing post-closure care in accordance with the PCCP (NMED October 2009 and subsequent revisions). From 1962 until 1981, the CWL was used for the disposal of chemical and solid waste generated by SNL/NM research activities. Additionally, a small amount of radioactive waste was disposed of during the operational years. Disposal of liquid waste in unlined pits and trenches ended in 1981, and after 1982 all liquid waste disposal was terminated. From 1982 through 1985, only solid waste was disposed of at the CWL, and after 1985 all waste disposal ended. The CWL was also used as a hazardous waste drum-storage facility from 1981 to 1989. A summary of the CWL disposal history is presented in the Closure Plan (SNL/NM December 1992) along with a waste inventory based upon available disposal records and information.

  19. Development and Presentation of the Drigg Post-Closure Safety Case

    International Nuclear Information System (INIS)

    Kelly, Eugene; Watts, Len; Grimwood, Paul

    2001-01-01

    Drigg is an operational facility for the near-surface disposal of solid low level radioactive waste (LLW). The disposal facility is located in Cumbria, north-west England, near the Sellafield nuclear site, and is owned and operated by British Nuclear Fuels plc (BNFL). Disposals at Drigg are carried out under the terms of an authorisation granted by the UK Environment Agency. Periodically the Drigg authorisation is subject to formal regulatory review. The current regulatory guidance, 'Disposal Facilities on Land for Low and Intermediate Level Radioactive Wastes: Guidance on Requirements for Authorisation' (the GRA) was published in 1997 and contains guidance on the principles and requirements against which the Environment Agency will consider applications for disposal authorisation. BNFL has undertaken to produce an updated Drigg postclosure safety case (PCSC) in September 2002 to support the next authorisation review. In preparation for this, BNFL published a 'Status Report on the Development of the 2002 Drigg PCSC' in March 2000. This paper discusses the main components of the Drigg PCSC and how they relate to each other. Central to the safety case will be a systematic, post-closure radiological safety assessment (PCRSA). However the main focus of this paper is on the other main components of the PCSC which are presented in conjunction with the PCRSA to make a complete and integrated safety case. In addition other confidence building activities which are key to developing and presenting the safety case are discussed, in particular communications with the stakeholders

  20. RIP Input Tables From WAPDEG for LA Design Selection: Continuous Post-Closure Ventilation Design- Open Loop

    International Nuclear Information System (INIS)

    K.G. Mon; P.K. Mast; R. Howard; J.H. Lee

    1999-01-01

    The purpose of this calculation is to document (1) the Waste Package Degradation (WAPDEG) version 3.09 (CRWMS M and O 1998b). Software Routine Report for WAPDEG (Version 3.09) simulations used to analyze waste package degradation and failure under the repository exposure conditions characterized by the open loop option of the post-closure ventilation design and, (2) post-processing of these results into tables of waste package degradation time histories suitable for use as input into the Integrated Probabilistic Simulator for Environmental Systems version 5.19.0 1 (RIP) computer program (Golder Associates 1998). Specifically, the WAPDEG simulations discussed in this calculation correspond to waste package emplacement conditions (repository environment and design) defined in the Total System Performance Assessment-Viability Assessment (TSPA-VA), with the exception that the open loop option of the post-closure ventilation License Application Design Selection (LADS) Design Alternative (Design Alternative 3b) was analyzed. The open loop post-closure ventilation design alternative, under which airways to the surface remain open after repository closure, could result in substantial cooling and drying of the potential repository. In open loop post-closure ventilation, expanded air heated by waste decay would move up an exhaust shaft, pulling denser, cooler air into the repository through intake shafts. The exchange of air with the atmosphere could remove more heat and moisture. As a result of the enhanced ventilation relative to the TSPA-VA base-case design, different temperature and relative humidity time histories at the waste package surface are calculated (input to the WAPDEG simulations), and consequently different waste package failure histories (as calculated by WAPDEG) result

  1. Pre/post-closure assessment of groundwater pharmaceutical fate in a wastewater‑facility-impacted stream reach

    Science.gov (United States)

    Bradley, Paul M.; Barber, Larry B.; Clark, Jimmy M.; Duris, Joseph W.; Foreman, William T.; Furlong, Edward T.; Givens, Carrie E.; Hubbard, Laura E.; Hutchinson, Kasey J.; Journey, Celeste A.; Keefe, Steffanie H.; Kolpin, Dana W.

    2016-01-01

    Pharmaceutical contamination of contiguous groundwater is a substantial concern in wastewater-impacted streams, due to ubiquity in effluent, high aqueous mobility, designed bioactivity, and to effluent-driven hydraulic gradients. Wastewater treatment facility (WWTF) closures are rare environmental remediation events; offering unique insights into contaminant persistence, long-term wastewater impacts, and ecosystem recovery processes. The USGS conducted a combined pre/post-closure groundwater assessment adjacent to an effluent-impacted reach of Fourmile Creek, Ankeny, Iowa, USA. Higher surface-water concentrations, consistent surface-water to groundwater concentration gradients, and sustained groundwater detections tens of meters from the stream bank demonstrated the importance of WWTF effluent as the source of groundwater pharmaceuticals as well as the persistence of these contaminants under effluent-driven, pre-closure conditions. The number of analytes (110 total) detected in surface water decreased from 69 prior to closure down to 8 in the first post-closure sampling event approximately 30 d later, with a corresponding 2 order of magnitude decrease in the cumulative concentration of detected analytes. Post-closure cumulative concentrations of detected analytes were approximately 5 times higher in proximal groundwater than in surface water. About 40% of the 21 contaminants detected in a downstream groundwater transect immediately before WWTF closure exhibited rapid attenuation with estimated half-lives on the order of a few days; however, a comparable number exhibited no consistent attenuation during the year-long post-closure assessment. The results demonstrate the potential for effluent-impacted shallow groundwater systems to accumulate pharmaceutical contaminants and serve as long-term residual sources, further increasing the risk of adverse ecological effects in groundwater and the near-stream ecosystem.

  2. Post-Closure Inspection Report for Corrective Action Unit 90: Area 2 Bitcutter Containment, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Corrective Action Unit (CAU) 90, Area 2 Bitcutter Containment, is identified in the ''Federal Facility Agreement and Consent Order'' of 1996. The post-closure requirements for CAU 90 are described in Section VII.B.8.b of the Nevada Test Site ''Resource Conservation and Recovery Act'' Permit for a Hazardous Waste Management Facility Number NEV HW0021, dated November 2005. Post-closure activities consist of the following: Semiannual inspections of the site using inspection checklists; Photographic documentation; Field note documentation; and Preparation and submittal of an annual Post-Closure Inspection Report. This annual report covers the period of July 2006 to June 2007 and consists of a summary of the results of the inspections, copies of the inspection checklists and field notes, maintenance and repair records (if any), photographs, and conclusions and recommendations. The inspection checklists are provided in Appendix A, a copy of the field notes is provided in Appendix B, and copies of photographs taken during the inspections are provided in Appendix C

  3. Post-Closure Inspection Report for Corrective Action Unit 90: Area 2 Bitcutter Containment, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2008-01-01

    Corrective Action Unit (CAU) 90, Area 2 Bitcutter Containment, is identified in the Federal Facility Agreement and Consent Order of 1996, as amended February 2008. The post-closure requirements for CAU 90 are described in Section VII.B.8.b of the Nevada Test Site Resource Conservation and Recovery Act Permit for a Hazardous Waste Management Facility Number NEV HW0021, dated November 2005. Post-closure activities consist of the following: (1) Semiannual inspections of the site using inspection checklists; (2) Photographic documentation; (3) Field note documentation; and (4) Preparation and submittal of an annual Post-Closure Inspection Report. This annual report covers the period of July 2007 to June 2008 and consists of a summary of the results of the inspections, copies of the inspection checklists and field notes, maintenance and repair records (if any), photographs, and conclusions and recommendations. The inspection checklists are provided in Appendix A, a copy of the field notes is provided in Appendix B, and copies of photographs taken during the inspections are provided in Appendix C

  4. Post-closure permit application for the Kerr Hollow Quarry at the Y-12 plant

    International Nuclear Information System (INIS)

    1995-06-01

    The Kerr Hollow Quarry (KHQ) is located on U.S. Department of Energy (DOE) property at the Y-12 Plant, Oak Ridge, Tennessee. The Oak Ridge Y-12 Plant was built by the U.S. Army Corps of Engineers in 1943 as part of the Manhattan Project. Until 1992, the primary mission of the Y-12 Plant was the production and fabrication of nuclear weapons components. Activities associated with these functions included production of lithium compounds, recovery of enriched uranium from scrap material, and fabrication of uranium and other materials into finished parts for assemblies. The Kerr Hollow Quarry was used for waste disposal of a variety of materials including water-reactive and shock-sensitive chemicals and compressed gas cylinders. These materials were packaged in various containers and sank under the water in the quarry due to their great weight. Disposal activities were terminated in November, 1988 due to a determination by the Tennessee Department of Environment and Conservation that the quarry was subject to regulations under the Resource Conservation and Recovery Act of 1993. Methods of closure for the quarry were reviewed, and actions were initiated to close the quarry in accordance with closure requirements for interim status surface impoundments specified in Tennessee Rules 1200-1-11-.05(7) and 1200-1-11-.05(11). As part of these actions, efforts were made to characterize the physical and chemical nature of wastes that had been disposed of in the quarry, and to remove any containers or debris that were put into the quarry during waste disposal activities. Closure certification reports (Fraser et al. 1993 and Dames and Moore 1993) document closure activities in detail. This report contains the post-closure permit application for the Kerr Hollow Quarry site

  5. Methods of calculating the post-closure performance of high-level waste repositories

    International Nuclear Information System (INIS)

    Ross, B.

    1989-02-01

    This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs

  6. Methods of calculating the post-closure performance of high-level waste repositories

    Energy Technology Data Exchange (ETDEWEB)

    Ross, B. (ed.)

    1989-02-01

    This report is intended as an overview of post-closure performance assessment methods for high-level radioactive waste repositories and is designed to give the reader a broad sense of the state of the art of this technology. As described here, ''the state of the art'' includes only what has been reported in report, journal, and conference proceedings literature through August 1987. There is a very large literature on the performance of high-level waste repositories. In order to make a review of this breadth manageable, its scope must be carefully defined. The essential principle followed is that only methods of calculating the long-term performance of waste repositories are described. The report is organized to reflect, in a generalized way, the logical order to steps that would be taken in a typical performance assessment. Chapter 2 describes ways of identifying scenarios and estimating their probabilities. Chapter 3 presents models used to determine the physical and chemical environment of a repository, including models of heat transfer, radiation, geochemistry, rock mechanics, brine migration, radiation effects on chemistry, and coupled processes. The next two chapters address the performance of specific barriers to release of radioactivity. Chapter 4 treats engineered barriers, including containers, waste forms, backfills around waste packages, shaft and borehole seals, and repository design features. Chapter 5 discusses natural barriers, including ground water systems and stability of salt formations. The final chapters address optics of general applicability to performance assessment models. Methods of sensitivity and uncertainty analysis are described in Chapter 6, and natural analogues of repositories are treated in Chapter 7. 473 refs., 19 figs., 2 tabs.

  7. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada for Fiscal Year 2011 (October 2010-September 2011)

    International Nuclear Information System (INIS)

    2012-01-01

    This report serves as the combined annual report for post-closure activities for the following closed Corrective Action Units (CAUs): (1) CAU 90, Area 2 Bitcutter Containment; (2) CAU 91, Area 3 U-3fi Injection Well; (3) CAU 92, Area 6 Decon Pond Facility; (4) CAU 110, Area 3 WMD U-3ax/bl Crater; and (5) CAU 112, Area 23 Hazardous Waste Trenches. This report covers fiscal year 2011 (October 2010-September 2011). The post-closure requirements for these sites are described in Resource Conservation and Recovery Act Permit Number NEV HW0101 and summarized in each CAU-specific section in Section 1.0 of this report. Site inspections are conducted semiannually at CAUs 90 and 91 and quarterly at CAUs 92, 110, and 112. Additional inspections are conducted at CAU 92 if precipitation occurs in excess of 0.50 inches in a 24-hour period. Inspections include an evaluation of the condition of the units and identification of any deficiencies that may compromise the integrity of the units. The condition of covers, fencing, signs, gates, and locks is documented. In addition, soil moisture monitoring and subsidence surveys are conducted at CAU 110. The results of the inspections, summary of maintenance activities, results of vegetations surveys, and analysis of monitoring data are presented in this report. Copies of the inspection checklists are included as Appendix A. Field notes completed during each inspection are included in Appendix B. Photographs taken during the inspections are included in Appendix C. It is recommended to continue semiannual inspections at CAUs 90 and 91; quarterly inspections at CAUs 92, 110, and 112; and additional inspections at CAU 92 if precipitation occurs in excess of 0.50 inches in a 24-hour period. At CAU 92, it is recommended to remove the wave barriers, as they have not proven to be necessary to protect the cover. At CAU 110, it is recommended to continue annual vegetation monitoring and soil moisture monitoring, and to reduce the frequency of

  8. Post-closure permit application for the Upper East Fork Poplar Creek hydrogeologic regime at the Y-12 Plant: New Hope Pond and Eastern S-3 ponds plume. Revision 2

    International Nuclear Information System (INIS)

    1995-02-01

    The intent of this Post-Closure, Permit Application (PCPA) is to satisfy the post-closure permitting requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-11. This application is for the entire Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), which is within the Bear Creek Valley (BCV). This PCPA has been prepared to include the entire East Fork Regime because, although there are numerous contaminant sources within the regime, the contaminant plumes throughout the East Fork Regime have coalesced and can no longer be distinguished as separate plumes. This PCPA focuses on two recognized Resource Conservation and Recovery Act (RCRA) interim status units: New Hope Pond (NHP) and the eastern S-3 Ponds plume. This PCPA presents data from groundwater assessment monitoring throughout the regime, performed since 1986. Using this data, this PCPA demonstrates that NHP is not a statistically discernible source of groundwater contaminants and that sites upgradient of NHP are the likely sources of groundwater contamination seen in the NHP vicinity. As such, this PCPA proposes a detection monitoring program to replace the current assessment monitoring program for NHP

  9. Effectiveness of the Vertical Gas Ventilation Pipes for Promoting Waste Stabilization in Post-Closure Phase

    Directory of Open Access Journals (Sweden)

    Yasumasa Tojo

    2015-06-01

    Full Text Available To make inside of the municipal solid waste (MSW landfill aerobic as much as possible is thought to be preferable for promoting waste stabilization, reducing pollutant's load in leachate, minimizing greenhouse gas emission and shortening post-closure-care period. In Japan, installation of semi-aerobic landfill structure has widely spread in order to promote waste stabilization in MSW landfill from 1980s. In semi-aerobic landfill structure, outlet of main leachate collection pipe is opened to atmosphere. Heat generated by aerobic degradation of waste causes natural convection and natural aeration arises from the outlet of leachate collection pipe to the gas vents. It is so-called stack effect. This air flow is thought to be effective for purifying leachate flowing through drainage layer and leachate collection pipes. And it is also thought to be contributing to expanding aerobic region in waste layer in landfill. Recently, measures attempting the promotion of waste stabilization are taken at several landfills at where stabilization of waste delays, in which many vertical gas vents are newly installed and close structure to semi-aerobic landfill is created. However, in many cases, these gas vents are not connected to leachate collection pipes. Many vertical gas vents are just installed without scientific proof regarding whether they can contribute for waste stabilization. In this study, how such installation of gas vents is effective for waste stabilization and aerobization of waste layer was discussed by numerical analysis. In numerical analysis, heat transfer, gas movement by pressure, gas diffusion, biological degradation of organic matter, and heat generation by biodegradation were taken into account. Simulations were carried out by using the general purpose simulator of finite element method. Three types of landfill structure were assumed. As the results, the following information were obtained. In dig-down type landfill, installation of gas

  10. Post-Closure Inspection Report for the Tonopah Test Range, Nevada: For Calendar Year 2017, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Alvarado, Juan; Matthews, Patrick

    2018-05-01

    This report provides the results of the annual post-closure inspections conducted at the closed corrective action units (CAUs) located on the Tonopah Test Range (TTR) and the Nevada Test and Training Range (NTTR). This report covers calendar year 2017 and includes visual inspection and repair activities completed at the following CAUs: • CAU 400: Bomblet Pit and Five Points Landfill (TTR) • CAU 407: Roller Coaster RadSafe Area (TTR) • CAU 424: Area 3 Landfill Complexes (TTR) • CAU 453: Area 9 UXO Landfill (TTR) • CAU 487: Thunderwell Site (TTR) Visual inspections were conducted according to the post-closure plans in the approved closure reports and subsequent correspondence with the Nevada Division of Environmental Protection. The annual post-closure inspections were conducted on May 23, 2017. No maintenance or repair issues were noted at CAU 400 and CAU 487. Maintenance items and subsequent repairs include the following: • CAU 407: A large animal burrow was observed in the southeast corner of the cover during the inspection. Two additional animal burrows were discovered during repair actions. All cover defects were repaired on January 9, 2018. • CAU 424: CAS 03-08-002-A304 (Landfill Cell A3-4): A new monument was installed and the subsidence area was repaired on January 9, 2018. • CAU 424: CAS 03-08-002-A308 (Landfill Cell A3-8): Lava rock, used to mark the two eastern monument locations, was noted as missing during the inspection. The lava rock was replaced on January 9, 2018. • CAU 453: Five large animal burrows, located near the east–central portion of cover, was noted during the inspection. Eight additional animal burrows were discovered during repair actions. All cover defects were repaired on January 9, 2018.

  11. A successful environmental remediation program closure and post-closure activities (CAPCA) Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Bowers, M.H.

    1991-01-01

    The Resource Conservation and Recovery Act (RCRA) closure of eleven waste management units at the Department of Energy's (DOE's) Oak Ridge Y-12 Plant is nearing completion. The Oak Ridge Y-12 Plant is managed by Martin Marietta Energy Systems, Inc. for the US Department of Energy under Contract DE-AC05-84OR21400. The Closure and Post Closure Program (CAPCA) has been accomplished on an accelerated schedule through the efforts of a dedicated team from several organizations. This paper relates experience gained from the program that can be of benefit on other DOE environmental remediation projects. Technical design and construction aspects, as well as project management considerations, are discussed

  12. Consideration of timescales in post-closure safety of geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    2006-11-01

    by a number of general considerations, which are described first. Three broad areas in the regulation and practice of repository planning and implementation affected by timescales issues are then discussed: - repository siting and design and the levels of protection required in regulation; - the planning of pre- and post-closure actions; and - developing and presenting a safety case. Finally, a synthesis of findings is made, including a review of the statements made in the 2004 'lessons learnt' report in light of the discussions contained in the present report. Many of the issues treated in the course of the project are subject to various interpretations, and remain under discussion in national programmes, as well as internationally. Therefore, the findings in this report should not be viewed as conclusive, but rather as a contribution in moving ahead the debate and understanding the similarities and differences among approaches in national programmes. (authors)

  13. Addendum to the post-closure permit application for the Bear Creek Hydrogeologic Regime at the Y-12 Plant: Walk-in pits. Revision 2

    International Nuclear Information System (INIS)

    1995-04-01

    The revised Closure Plan was initially intended to apply to A Area, C-West, B Area, and the Walk-In Pits (WIPs) of the Bear Creek Burial Grounds (BCBG). However, a strategy was developed to include the B Area [a solid waste management unit (SWMU)] with the WIPs so that both areas would be closed under one cap. The plan was presented to the State of Tennessee on March 8, 1990, and the Department of Energy was requested to review other unique alternatives to close the site. Therefore, in November 1992, the Closure Plan for B Area and the WIPs was prepared separately from that of the other sites associated with the BCBG and was presented in a RCRA Closure Plan. The Closure Plan revision issued April 1993 was intended to reflect the placement of the Kerr Hollow Quarry debris at the WIPs, revise the closure data, and acknowledge that the disposition of a monitoring well within the closure site could not be verified. A Post-Closure Permit Application (PCPA) was to include the WIPs; however, at the time of submittal, closure of the WIPs had not been certified. This addendum contains information on the WIPs to accompany the BCBG PCPA. The purpose of this document is to supplement the information provided in the BCBG PCPA. This document is not intended to be a stand-alone document. Only additional information regarding the WIPs is included in the sections of this document, which correspond to sections of the PCPA submitted in June 1994

  14. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    International Nuclear Information System (INIS)

    Traynor, J. L.

    2001-01-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure

  15. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    Energy Technology Data Exchange (ETDEWEB)

    J. L. Traynor

    2001-03-01

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure.

  16. Preliminary post-closure safety assessment of repository concepts for low level radioactive waste at the Bruce Site, Ontario

    International Nuclear Information System (INIS)

    Little, R.H.; Penfold, J.S.S.; Egan, M.J.; Leung, H.

    2005-01-01

    The preliminary post-closure safety assessment of permanent repository concepts for low-level radioactive waste (LLW) at the Ontario Power Generation (OPG) Bruce Site is described. The study considered the disposal of both short and long-lived LLW. Four geotechnically feasible repository concepts were considered (two near-surface and two deep repositories). An approach consistent with best international practice was used to provide a reasoned and comprehensive analysis of post-closure impacts of the repository concepts. The results demonstrated that the deep repository concepts in shale and in limestone, and the surface repository concept on sand should meet radiological protection criteria. For the surface repository concept on glacial till, it appears that increased engineering such as grouting of waste and voids should be considered to meet the relevant dose constraint. Should the project to develop a permanent repository for LLW proceed, it is expected that this preliminary safety assessment would need to be updated to take account of future site-specific investigations and design updates. (author)

  17. Project Management Approach to Transition of the Miamisburg Closure Project From Environmental Cleanup to Post-Closure Operations

    International Nuclear Information System (INIS)

    Carpenter, C.P.; Marks, M.L.; Smiley, S.L.; Gallaher, D.M.; Williams, K.D.

    2006-01-01

    The U.S. Department of Energy (DOE) used a project management approach to transition the Miamisburg Closure Project from cleanup by the Office of Environmental Management (EM) to post-closure operations by the Office of Legacy Management (LM). Two primary DOE orders were used to guide the site transition: DOE Order 430.1B, Real Property Asset Management, for assessment and disposition of real property assets and DOE Order 413.3, Program and Project Management for Acquisition of Capital Assets, for project closeout of environmental cleanup activities and project transition of post-closure activities. To effectively manage these multiple policy requirements, DOE chose to manage the Miamisburg Closure Project as a project under a cross-member transitional team using representatives from four principal organizations: DOE-LM, the LM contractor S.M. Stoller Corporation, DOE-EM, and the EM contractor CH2M Hill Mound Inc. The mission of LM is to manage the Department's post-transition responsibilities and long-term care of legacy liabilities and to ensure the future protection of human health and the environment for cleanup sites after the EM has completed its cleanup activities. (authors)

  18. Post-Closure Inspection Report for Corrective Action Unit 427: Septic Waste Systems 2 and 6 Tonopah Test Range, Nevada Calendar Year 2000; TOPICAL

    International Nuclear Information System (INIS)

    K. B. Campbell

    2001-01-01

    Post-closure inspection requirements for the Area 3 Septic Waste Systems 2 and 6 (Corrective Action Unit[CAU] 427) (Figure 1) are described in Closure Report for Corrective Action Unit 427. Area 3 Septic Waste Systems 2 and 6. Tonopah Test Range, Nevada, report number DOE/NV-561. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on August 16, 1999. The CR (containing the Post-Closure Inspection Plan) was approved by the NDEP on August 27, 1999. The annual post-closure inspection at CAU 427 consists of the following: Verification of the presence of all leachfield and septic tank below-grade markers; Verification that the warning signs are in-place, intact, and readable; and Visual observation of the soil and asphalt cover for indications of subsidence, erosion, and unauthorized use. The site inspections were conducted on June 20, 2000, and November 21, 2000. All inspections were made after NDEP approval of the CR and were conducted in accordance with the Post-Closure Inspection Plan in the NDEP-approved CR. No maintenance or repairs were conducted at the site. This report includes copies of inspection checklists, photographs, recommendations, and conclusions. Copies of the Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and a copy of the inspection photographs is found in Attachments C

  19. Addendum to the post-closure permit application for the Bear Creek hydrogeologic regime at the Y-12 plant: Walk-in pits

    International Nuclear Information System (INIS)

    1995-04-01

    In June 1987, the Resource Conservation and Recovery Act (RCRA) Closure/Post-Closure Plan for the Bear Creek Burial Grounds (BCBG) located at the Y-12 Plant on the Oak Ridge Reservation in Oak Ridge, Tennessee was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval.The Closure Plan has been modified and revised several times. This document is an addendum to the Post-Closure Permit Application submitted to TDEC in June, 1994. This addendum contains information on the Walk-In Pits of the BCBG which is meant to supplement the information provided in the Post-Closure Permit Application submitted for the BCBG. This document is not intended to be a stand-alone document.

  20. Characterization of Uranium Contamination, Transport, and Remediation at Rocky Flats - Across Remediation into Post-Closure

    Science.gov (United States)

    Janecky, D. R.; Boylan, J.; Murrell, M. T.

    2009-12-01

    The Rocky Flats Site is a former nuclear weapons production facility approximately 16 miles northwest of Denver, Colorado. Built in 1952 and operated by the Atomic Energy Commission and then Department of Energy, the Site was remediated and closed in 2005, and is currently undergoing long-term surveillance and monitoring by the DOE Office of Legacy Management. Areas of contamination resulted from roughly fifty years of operation. Of greatest interest, surface soils were contaminated with plutonium, americium, and uranium; groundwater was contaminated with chlorinated solvents, uranium, and nitrates; and surface waters, as recipients of runoff and shallow groundwater discharge, have been contaminated by transport from both regimes. A region of economic mineralization that has been referred to as the Colorado Mineral Belt is nearby, and the Schwartzwalder uranium mine is approximately five miles upgradient of the Site. Background uranium concentrations are therefore elevated in many areas. Weapons-related activities included work with enriched and depleted uranium, contributing anthropogenic content to the environment. Using high-resolution isotopic analyses, Site-related contamination can be distinguished from natural uranium in water samples. This has been instrumental in defining remedy components, and long-term monitoring and surveillance strategies. Rocky Flats hydrology interlinks surface waters and shallow groundwater (which is very limited in volume and vertical and horizontal extent). Surface water transport pathways include several streams, constructed ponds, and facility surfaces. Shallow groundwater has no demonstrated connection to deep aquifers, and includes natural preferential pathways resulting primarily from porosity in the Rocky Flats alluvium, weathered bedrock, and discontinuous sandstones. In addition, building footings, drains, trenches, and remedial systems provide pathways for transport at the site. Removal of impermeable surfaces (buildings

  1. Development of vault model 'VERMIN' for post closure behaviour of repositories for non-heat generating radioactive wastes

    International Nuclear Information System (INIS)

    1983-10-01

    The computer model VERMIN has been developed to simulate the post closure time dependent behaviour of the vault section of a Land 3 and a Land 2 type repository. Development was carried out within the constraints of the computer code SYVAC. Output from the new model, in terms of radionuclide fluxes versus time, provides the source term for that code. A number of conceptual designs for different geological conditions were produced and used to develop the model. Unlike SYVAC, the boundary of the vault was considered to be at the interface between the damaged rock zone and the undamaged host rock. VERMIN treats the vault as a series of engineered barriers namely: waste matrix, waste package, backfill material liner and the damaged rock zone. For the Land 3 repository, the vault was considered to be fully saturated and consequently corrosion, leading to eventual package failure, will occur. VERMIN allows for package failure and subsequent leaching and then calculates the migration of nuclides from within the vault out to its boundary. One dimensional advection and two dimensional diffusion/dispersion are modelled allowing for retardation due to sorption radionuclide saturation and radionuclide decay. Radioactive decay chains up to eight members can be modelled by VERMIN. (author)

  2. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This report summarizes the 2012 annual inspection, sampling, measurement, and maintenance activities performed at the Salmon, Mississippi, Site (Salmon site). The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities with the results of sample analyses. A revised plan is in preparation. The Long-Term Surveillance Plan for the Salmon, Mississippi, Site is intended for release in 2013. The Salmon site consists of 1,470 acres. The site is located in Lamar County, Mississippi, approximately 10 miles west of Purvis, Mississippi, and about 21 miles southwest of Hattiesburg, Mississippi The State of Mississippi owns the surface real estate subject to certain restrictions related to subsurface penetration. The State is the surface operator; the Mississippi Forestry Commission is its agent. The federal government owns the subsurface real estate (including minerals and some surface features), shares right-of-entry easements with the State, and retains rights related to subsurface monitoring. The U.S. Department of Energy (DOE) Office of Legacy Management (LM), a successor agency to the U.S. Atomic Energy Commission, is responsible for the long-term surveillance of the subsurface real estate.

  3. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-03-01

    This report summarizes the 2012 annual inspection, sampling, measurement, and maintenance activities performed at the Salmon, Mississippi, Site (Salmon site). The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities with the results of sample analyses. A revised plan is in preparation. The Long-Term Surveillance Plan for the Salmon, Mississippi, Site is intended for release in 2013. The Salmon site consists of 1,470 acres. The site is located in Lamar County, Mississippi, approximately 10 miles west of Purvis, Mississippi, and about 21 miles southwest of Hattiesburg, Mississippi The State of Mississippi owns the surface real estate subject to certain restrictions related to subsurface penetration. The State is the surface operator; the Mississippi Forestry Commission is its agent. The federal government owns the subsurface real estate (including minerals and some surface features), shares right-of-entry easements with the State, and retains rights related to subsurface monitoring. The U.S. Department of Energy (DOE) Office of Legacy Management (LM), a successor agency to the U.S. Atomic Energy Commission, is responsible for the long-term surveillance of the subsurface real estate

  4. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON PAD FACILITY, NEVADA. TEST SITE NEVADA, FOR THE PERIOD JANUARY 2004 - DECEMBER 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2005-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection, 1995) and the Federal Facility Agreement and Consent Order of 1996 on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02, Decontamination Pond (RCRA), requires post-closure inspections. CAS 06-04-01, Decon Pad Oil/Water Separator, is located inside the fence at the Building 6-605 compound. This report covers the annual period January 2004 through December 2004

  5. The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

    International Nuclear Information System (INIS)

    Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.

    2002-01-01

    The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme

  6. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada, for fiscal year 2013 (October 2012 - September 2013)

    International Nuclear Information System (INIS)

    2014-01-01

    This report serves as the combined annual report for post-closure activities for the following closed Corrective Action Units (CAUs): CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well; CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and, CAU 112, Area 23 Hazardous Waste Trenches

  7. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada for fiscal year 2013 (October 2012 - September 2013)

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-01-31

    This report serves as the combined annual report for post-closure activities for the following closed Corrective Action Units (CAUs): CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well; CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and, CAU 112, Area 23 Hazardous Waste Trenches.

  8. 40 CFR 194.42 - Monitoring.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Monitoring. 194.42 Section 194.42... § 194.42 Monitoring. (a) The Department shall conduct an analysis of the effects of disposal system...-closure and post-closure monitoring required pursuant to paragraphs (c) and (d) of this section. The...

  9. Climate change and landscape development in post-closure safety assessment of solid radioactive waste disposal: Results of an initiative of the IAEA.

    Science.gov (United States)

    Lindborg, T; Thorne, M; Andersson, E; Becker, J; Brandefelt, J; Cabianca, T; Gunia, M; Ikonen, A T K; Johansson, E; Kangasniemi, V; Kautsky, U; Kirchner, G; Klos, R; Kowe, R; Kontula, A; Kupiainen, P; Lahdenperä, A-M; Lord, N S; Lunt, D J; Näslund, J-O; Nordén, M; Norris, S; Pérez-Sánchez, D; Proverbio, A; Riekki, K; Rübel, A; Sweeck, L; Walke, R; Xu, S; Smith, G; Pröhl, G

    2018-03-01

    The International Atomic Energy Agency has coordinated an international project addressing climate change and landscape development in post-closure safety assessments of solid radioactive waste disposal. The work has been supported by results of parallel on-going research that has been published in a variety of reports and peer reviewed journal articles. The project is due to be described in detail in a forthcoming IAEA report. Noting the multi-disciplinary nature of post-closure safety assessments, here, an overview of the work is given to provide researchers in the broader fields of radioecology and radiological safety assessment with a review of the work that has been undertaken. It is hoped that such dissemination will support and promote integrated understanding and coherent treatment of climate change and landscape development within an overall assessment process. The key activities undertaken in the project were: identification of the key processes that drive environmental change (mainly those associated with climate and climate change), and description of how a relevant future may develop on a global scale; development of a methodology for characterising environmental change that is valid on a global scale, showing how modelled global changes in climate can be downscaled to provide information that may be needed for characterising environmental change in site-specific assessments, and illustrating different aspects of the methodology in a number of case studies that show the evolution of site characteristics and the implications for the dose assessment models. Overall, the study has shown that quantitative climate and landscape modelling has now developed to the stage that it can be used to define an envelope of climate and landscape change scenarios at specific sites and under specific greenhouse-gas emissions assumptions that is suitable for use in quantitative post-closure performance assessments. These scenarios are not predictions of the future, but

  10. Transparency in risk assessments - Presenting the 'expectation value' of post-closure risks from radioactive waste repositories

    International Nuclear Information System (INIS)

    Wilmot, R.D.; Galson, D.A.; Pollard, S.J.T.; Smith, R.E.; Yearsley, R.A.

    1999-01-01

    The Environment Agency of England and Wales (the 'Agency') has an extremely broad regulatory remit covering aspects of flood defence, integrated pollution control, water quality, waste management, abstraction control, navigation, fisheries, conservation and recreation. Risk assessment, as a regulatory and management tool plays an essential role in the targeting and prioritisation of this activity, as well as in aiding site-specific decisions on authorisations for abstraction, discharge and/or disposal. From a regulatory perspective, the majority of the Agency's risk assessment activity is focused on critically reviewing risk assessments submitted to the Agency in support of requests for authorisation. With increasing calls for openness in all areas of regulatory decision-making, new demands are being placed on risk assessments with a view to allowing far more transparency and traceability of 'process' and 'content' than has historically been the case. The Agency is responsible for the licensing of radioactive waste disposal facilities in England and Wales. It has issued guidance on what is expected of an application for an authorisation to dispose of low and intermediate level radioactive waste to land - the 'Guidance on Requirements for Authorisation' (the 'GRA'). The GRA includes a risk target and places a strong emphasis on confidence-building during the preparation and assessment of post-closure safety cases for such facilities. In this paper we discuss a recent study commissioned by the Agency which has examined the use of expectation value of risk in assessments and considered ways of improving transparency. The study has concluded that the expectation value is an appropriate measure of risk for comparison with a single-value criterion, provided that the scope of the assessment does not involve undue speculation regarding the FEPs (Features, Events and Processes) to be included. Low probability or speculative events and processes for which no data can be

  11. Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

    International Nuclear Information System (INIS)

    Torres, C.

    2000-01-01

    The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

  12. POST-CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON POND FACILITY, NEVADA TEST SITE, NEVADA FOR CALENDAR YEAR 2005

    International Nuclear Information System (INIS)

    2006-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection (NDEP), 1995) and the Federal Facility Agreement and Consent Order of 1996. Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by the NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period. This report covers calendar year 2005. Quarterly site inspections were performed in March, June, September, and December of 2005. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Five additional inspections were performed after precipitation events that exceeded 1.28 cm (0.50 in) within a 24-hour period during 2005. No significant changes in site conditions were noted during these inspections, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Precipitation records for 2005 are included in Appendix C

  13. Validation of a physically based catchment model for application in post-closure radiological safety assessments of deep geological repositories for solid radioactive wastes.

    Science.gov (United States)

    Thorne, M C; Degnan, P; Ewen, J; Parkin, G

    2000-12-01

    The physically based river catchment modelling system SHETRAN incorporates components representing water flow, sediment transport and radionuclide transport both in solution and bound to sediments. The system has been applied to simulate hypothetical future catchments in the context of post-closure radiological safety assessments of a potential site for a deep geological disposal facility for intermediate and certain low-level radioactive wastes at Sellafield, west Cumbria. In order to have confidence in the application of SHETRAN for this purpose, various blind validation studies have been undertaken. In earlier studies, the validation was undertaken against uncertainty bounds in model output predictions set by the modelling team on the basis of how well they expected the model to perform. However, validation can also be carried out with bounds set on the basis of how well the model is required to perform in order to constitute a useful assessment tool. Herein, such an assessment-based validation exercise is reported. This exercise related to a field plot experiment conducted at Calder Hollow, west Cumbria, in which the migration of strontium and lanthanum in subsurface Quaternary deposits was studied on a length scale of a few metres. Blind predictions of tracer migration were compared with experimental results using bounds set by a small group of assessment experts independent of the modelling team. Overall, the SHETRAN system performed well, failing only two out of seven of the imposed tests. Furthermore, of the five tests that were not failed, three were positively passed even when a pessimistic view was taken as to how measurement errors should be taken into account. It is concluded that the SHETRAN system, which is still being developed further, is a powerful tool for application in post-closure radiological safety assessments.

  14. Local-scale modelling of density-driven flow for the phases of repository operation and post-closure at Beberg

    International Nuclear Information System (INIS)

    Jaquet, O.; Siegel, P.

    2004-09-01

    A hydrogeological model was developed for Beberg with the aim of evaluating the impact of a repository (for the operational and post-closure phases) while accounting for the effects of density-driven flow. Two embedded scales were taken into account for this modelling study: a local scale at which the granitic medium was considered as a continuum and a repository scale, where the medium is fractured and therefore was regarded to be discrete. The following step-wise approach was established to model density-driven flow at both repository and local scale: (a) modelling fracture networks at the repository scale, (b) upscaling the hydraulic properties to a continuum at local scale and (c) modelling density-driven flow to evaluate repository impact at local scale. The results demonstrate the strong impact of the repository on the flow field during the phase of operation. The distribution of the salt concentration is affected by a large upcoming effect with increased relative concentration and by the presence of fracture zones carrying freshwater from the surface. The concentrations obtained for the reference case, expressed in terms of percentage with respect to the maximum (prescribed) value in the model, are as follows: ca 30% for the phase of desaturation, and ca 20% for the resaturation phase. For the reference case, the impact of repository operations appears no longer visible after a resaturation period of about 20 years after repository closure; under resaturation conditions, evidence of the operational phase has already disappeared in terms of the observed hydraulic and concentration fields. Sensitivity calculations have proven the importance of explicitly discretising repository tunnels when assessing resaturation time and maximum concentration values. Furthermore, the definition of a fixed potential as boundary condition along the model's top surface is likely to provide underestimated values for the maximum concentration and overestimated flow rates in the

  15. Post-Closure Inspection Report for Corrective Action Unit 92: Area 6 Decon Pond Facility, Nevada Test Site, Nevada, for Calendar Year 2006

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility. CAU 92 was closed according to the ''Resource Conservation and Recovery Act'' (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP], 1995) and the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 (FFACO, 1996). Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs), CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in.]) in a 24-hour period. This report covers calendar year 2006. Quarterly site inspections were performed in March, June, September, and December of 2006. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A of this report, and photographs taken during the site inspections are included in Appendix B of this report. One additional inspection was performed after a precipitation event that exceeded 1.28 cm (0.50 in.) within a 24-hour period during 2006. No significant changes in site conditions were noted during this inspection, and no corrective actions were necessary. A copy of the inspection checklist and field notes completed during this additional inspection is included in Appendix A of this report. Precipitation records for 2006

  16. The post-closure radiological safety case for a spent fuel repository in Sweden - An international peer review of the SKB license-application study of March 2011

    International Nuclear Information System (INIS)

    2012-01-01

    Sweden is at the forefront among countries developing plans for a deep geological repository of highly radioactive waste. There is no such repository in operation yet worldwide, but Sweden, Finland and France are approaching the licensing stage. At the request of the Swedish government, the NEA organised an international peer review of the post-closure radiological safety case produced by the Swedish Nuclear Fuel and Waste Management Company (SKB) in support of the application for a general licence to construct and operate a spent nuclear fuel geological repository in the municipality of Oesthammar. The purpose of the review was to help the Swedish government, the public and relevant organisations by providing an international reference regarding the maturity of SKB's spent fuel disposal programme vis-a-vis best practices in long-term disposal safety and radiological protection. The International Review Team (IRT) consisted of ten international specialists, who were free of conflict of interest with the SKB and brought complementary expertise to the review. This report provides the background and findings of the international peer review. The review's findings are presented at several levels of detail in order to be accessible to both specialist and non-specialist readers

  17. Study on a monitoring strategy to support decision making for geological repository closure

    International Nuclear Information System (INIS)

    Suyama, Yasuhiro; Tanabe, Hiromi; Eto, Jiro; Yoshimura, Kimitaka

    2010-01-01

    Japan currently plans to dispose of high-level radioactive wastes (vitrified HLWs) produced from the reprocessing of spent nuclear fuel in deep geological formations, in order to isolate the radioactive wastes from the human environment for tens of thousands of years. Such a geological repository must be designed to ensure operational safety and post-closure safety. Then, following the closure of the geological repository, post-closure safety will be provided by an engineered barrier system (EBS) and a natural barrier system (NBS) without relying on monitoring or institutional control. However, from a technical standpoint, monitoring has been required during backfilling in current studies. Additionally, there has been strong social pressure to continue monitoring during all the phases including post-closure. On the basis of the current situations, a monitoring strategy for geological disposal must be studied to ensure the long term safety of geological disposal. Focusing on decision making for geological repository closure, the authors have created a basic logical structure for the decision making process with the principles for ensuring safety and have developed a monitoring strategy based on the logical structure. The monitoring strategy is founded on three key aspects: the role of monitoring, boundary conditions of monitoring at the time of decision making, and a methodology for monitoring planning. Then, the monitoring strategy becomes a starting point of monitoring planning during site characterization, construction, operation and staged closure, as well as post-closure with institutional control, and of social science studies. (author)

  18. Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 1: hydrogeological model development - conceptual basis and data

    International Nuclear Information System (INIS)

    Degnan, P.; Littleboy, A.

    1997-01-01

    United Kingdom Nirex Limited ('Nirex') is responsible for providing and managing facilities for the safe disposal of intermediate and certain low-level radioactive waste (ILW and LLW respectively). Government policy is that the preferred disposal route for such wastes is a deep geological repository. The repository concept aims to use a combination of natural and engineered barriers to achieve the necessary degree of long-term isolation and containment of the radioactive wastes. Since 1987, Nirex has carried out an extensive technical programme directed at the science of safe disposal. The work comprises a research programme into the long-term performance of waste forms and the engineered and natural barriers, including the characterisation of candidate geological settings to assess their suitability to host a deep waste repository ('DWR'). Between mid-1991 and March 1997 the geological characterisation programme was concentrated on establishing the suitability, or otherwise, of a candidate site at Sellafield, West Cumbria. In July 1994, as part of a detailed site investigation programme, Nirex applied for planning permission to develop an underground Rock Characterisation Facility (RCF) at Longlands Farm near Sellafield. This application was rejected by the planning authority and Nirex's appeal against that decision led to a local planning inquiry which ran from September 1995 until February 1996. In line with the Inspector's Report, in March 1997 the Nirex appeal was dismissed by the Secretary of State for the Environment. The Company's response to that decision, and its readiness to contribute to the new government's review of the way forward, are described in the Nirex Annual Report for 1996-97. This report - Nirex 97 - is founded on the understanding developed through the Nirex technical programme. It reports the outcome of an assessment of the post-closure safety performance, over hundreds of thousands of years, of a repository system located in a potential

  19. Contingent post-closure plan, hazardous waste management units at selected maintenance facilities, US Army National Training Center, Fort Irwin, California

    International Nuclear Information System (INIS)

    1992-01-01

    The National Training Center (NTC) at Fort Irwin, California, is a US Army training installation that provides tactical experience for battalion/task forces and squadrons in a mid- to high-intensity combat scenario. Through joint exercises with US Air Force and other services, the NTC also provides a data source for improvements of training doctrines, organization, and equipment. To meet the training and operational needs of the NTC, several maintenance facilities provide general and direct support for mechanical devices, equipment, and vehicles. Maintenance products used at these facilities include fuels, petroleum-based oils, lubricating grease, various degreasing solvents, antifreeze (ethylene glycol), transmission fluid, brake fluid, and hydraulic oil. Used or spent petroleum-based products generated at the maintenance facilities are temporarily accumulated in underground storage tanks (USTs), collected by the NTC hazardous waste management contractor (HAZCO), and stored at the Petroleum, Oil, and Lubricant (POL) Storage Facility, Building 630, until shipped off site to be recovered, reused, and/or reclaimed. Spent degreasing solvents and other hazardous wastes are containerized and stored on-base for up to 90 days at the NTC's Hazardous Waste Storage Facility, Building 703. The US Environmental Protection Agency (EPA) performed an inspection and reviewed the hazardous waste management operations of the NTC. Inspections indicated that the NTC had violated one or more requirements of Subtitle C of the Resource Conservation and Recovery Act (RCRA) and as a result of these violations was issued a Notice of Noncompliance, Notice of Necessity for Conference, and Proposed Compliance Schedule (NON) dated October 13, 1989. The following post-closure plan is the compliance-based approach for the NTC to respond to the regulatory violations cited in the NON

  20. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada For Calendar Year 2006

    International Nuclear Information System (INIS)

    2007-01-01

    Corrective Action Unit (CAU) 417, Central Nevada Test Area - Surface, is located in Hot Creek Valley in northern Nye County, Nevada, and consists of three areas commonly referred to as UC-1, UC-3, and UC-4. CAU 417 consists of 34 Corrective Action Sites (CASs) which were closed in 2000 (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office, 2001). Three CASs at UC-1 were closed in place with administrative controls. At CAS 58-09-01, Central Mud Pit (CMP), a vegetated soil cover was constructed over the mud pit. At the remaining two sites, CAS 58-09-02, Mud Pit, and CAS 58-09-05, Mud Pits (3), aboveground monuments and warning signs were installed to mark the CAS boundaries. Three CASs at UC-3 were closed in place with administrative controls. Aboveground monuments and warning signs were installed to mark the site boundaries at CAS 58-09-06, Mud Pits (5), CAS 58-25-01, Spill, and CAS 58-10-01, Shaker Pad Area. Two CASs that consist of five sites at UC-4 were closed in place with administrative controls. At CAS 58-09-03, Mud Pits (5), an engineered soil cover was constructed over Mud Pit C. At the remaining three sites in CAS 58-09-03 and at CAS 58-10-05, Shaker Pad Area, aboveground monuments and warning signs were installed to mark the site boundaries. The remaining 26 CASs at CAU 417 were either clean-closed or closed by taking no further action.

  1. Calendar Year 1997 Annual Groundwater Monitoring Report For The Upper East Fork Poplar Creek Hydrogeologic Regime At The U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Jones, S.B.

    1998-02-01

    This report contains the groundwater monitoring data obtained during calendar year (CY) 1997 in compliance with the Resource Conservation Wd Recovery Act (RCRA) post-closure permit (PCP) for the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime) at the U.S. Department of Energy (DOE) Y-12 Plant in Oak Ridge, Tennessee. Issued by the Tennessee Department of Environment and Conservation (TDEC), the PCP defines the RCRA post-closure corrective action monitoring requirements for the portion of the groundwater contaminant plume that has migrated into the East Fork Regime ftom the S-3 Ponds, a closed RCW-regulated former surface impoundment located in Bear Creek Valley near the west end of the Y-12 Plant. In addition to the RCIL4 post-closure corrective action monitoring results, this report contains the groundwater and surface water monitoring data obtained during CY 1997 to fulfill requirements of DOE Order 5400.1.

  2. Soil radium, soil gas radon and indoor radon empirical relationships to assist in post-closure impact assessment related to near-surface radioactive waste disposal.

    Science.gov (United States)

    Appleton, J D; Cave, M R; Miles, J C H; Sumerling, T J

    2011-03-01

    Least squares (LS), Theil's (TS) and weighted total least squares (WTLS) regression analysis methods are used to develop empirical relationships between radium in the ground, radon in soil and radon in dwellings to assist in the post-closure assessment of indoor radon related to near-surface radioactive waste disposal at the Low Level Waste Repository in England. The data sets used are (i) estimated ²²⁶Ra in the < 2 mm fraction of topsoils (eRa226) derived from equivalent uranium (eU) from airborne gamma spectrometry data, (ii) eRa226 derived from measurements of uranium in soil geochemical samples, (iii) soil gas radon and (iv) indoor radon data. For models comparing indoor radon and (i) eRa226 derived from airborne eU data and (ii) soil gas radon data, some of the geological groupings have significant slopes. For these groupings there is reasonable agreement in slope and intercept between the three regression analysis methods (LS, TS and WTLS). Relationships between radon in dwellings and radium in the ground or radon in soil differ depending on the characteristics of the underlying geological units, with more permeable units having steeper slopes and higher indoor radon concentrations for a given radium or soil gas radon concentration in the ground. The regression models comparing indoor radon with soil gas radon have intercepts close to 5 Bq m⁻³ whilst the intercepts for those comparing indoor radon with eRa226 from airborne eU vary from about 20 Bq m⁻³ for a moderately permeable geological unit to about 40 Bq m⁻³ for highly permeable limestone, implying unrealistically high contributions to indoor radon from sources other than the ground. An intercept value of 5 Bq m⁻³ is assumed as an appropriate mean value for the UK for sources of indoor radon other than radon from the ground, based on examination of UK data. Comparison with published data used to derive an average indoor radon: soil ²²⁶Ra ratio shows that whereas the published data are

  3. Evaluation of SKB's report 'Deep repository for spent nuclear fuel: SR 97 - Post-closure safety', Focusing on the assessment of transport processes in the geosphere

    International Nuclear Information System (INIS)

    Woerman, A.; Shulan Xu

    2000-01-01

    This report describes a critical review of the safety assessment performed on the final repository for nuclear waste in Sweden that is proposed by SKB in 'Deep Repository for Spent Nuclear Fuel: SR 97 - Post-closure Safety'. The review was requested by the Swedish Nuclear Power Inspectorate (SKI). The waste repository consists of several barriers that work together with the purpose of delaying radionuclide migration and reducing the activity that eventually affects the biosphere. A main criticism is the lack of a formal risk analysis and uncertainties in several analyses that make it difficult to comprehend the overall risk of the repository. A formal risk analysis should comprise a probabilistic treatment of all components included in the system. This is not the case in the SKB's report since the probabilistic analyses are limited only to certain aspects. The use of conservative model parameters are not a substitute for risk analysis nor can they compensate for possible model biases. Bias can be expected in most of the existing models of radionuclide migration in fractured bedrock. SKB should present a clear comparison on the importance of the different barrier components (uranium-dioxide matrix, copper canister, buffer and bedrock) on the retardation of radionuclides. It is unclear as to what extent the capacity of the bedrock to retain migrating radionuclides is critical to the capacity of the repository. A large part of the SR 97 report is focused on retardation processes in bedrock and a reader can interpret this as the technical weight given on retardation in the bedrock. However, with the present state of knowledge, it is our opinion that we cannot with an acceptable degree of accuracy predict the radionuclide transport in bedrock or quantify risk levels associated with radioactivity in the biosphere. There are large uncertainties concerning the way by which sorption processes should be formulated and the impact of colloids on the transport that can be

  4. Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 2; hydrogeological conceptual model development - effective parameters and calibration appendix

    International Nuclear Information System (INIS)

    Jackson, C.; Watson, S.

    1997-01-01

    United Kingdom Nirex Limited ('Nirex') is responsible for providing and managing facilities for the safe disposal of intermediate and certain low-level radioactive waste (ILW and LLW respectively). Government policy is that the preferred disposal route for such wastes is a deep geological repository. The repository concept aims to use a combination of natural and engineered barriers to achieve the necessary degree of long-term isolation and containment of the radioactive wastes. Since 1987, Nirex has carried out an extensive technical programme directed at the science of safe disposal. The work comprises a research programme into the long-term performance of waste forms and the engineered and natural barriers, including the characterisation of candidate geological settings to assess their suitability to host a deep waste repository ('DWR'). Between mid-1991 and March 1997 the geological characterisation programme was concentrated on establishing the suitability, or otherwise, of a candidate site at Sellafield, West Cumbria. In July 1994, as part of a detailed site investigation programme, Nirex applied for planning permission to develop an underground Rock Characterisation Facility (RCF) at Longlands Farm near Sellafield. This application was rejected by the planning authority and Nirex's appeal against that decision led to a local planning inquiry which ran from September 1995 until February 1996. In line with the Inspector's Report, in March 1997 the Nirex appeal was dismissed by the Secretary of State for the Environment. The Company's response to that decision, and its readiness to contribute to the new government's review of the way forward, are described in the Nirex Annual Report for 1996-97. This report - Nirex 97 - is founded on the understanding developed through the Nirex technical programme. It reports the outcome of an assessment of the post-closure safety performance, over hundreds of thousands of years, of a repository system located in a potential

  5. Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 3; the groundwater pathway

    International Nuclear Information System (INIS)

    Baker, A.; Chambers, A.; Jackson, C.

    1997-01-01

    United Kingdom Nirex Limited ('Nirex') is responsible for providing and managing facilities for the safe disposal of intermediate and certain low-level radioactive waste (ILW and LLW respectively). Government policy is that the preferred disposal route for such wastes is a deep geological repository. The repository concept aims to use a combination of natural and engineered barriers to achieve the necessary degree of long-term isolation and containment of the radioactive wastes. Since 1987, Nirex has carried out an extensive technical programme directed at the science of safe disposal. The work comprises a research programme into the long-term performance of waste forms and the engineered and natural barriers, including the characterisation of candidate geological settings to assess their suitability to host a deep waste repository ('DWR'). Between mid-1991 and March 1997 the geological characterisation programme was concentrated on establishing the suitability, or otherwise, of a candidate site at Sellafield, West Cumbria. In July 1994, as part of a detailed site investigation programme, Nirex applied for planning permission to develop an underground Rock Characterisation Facility (RCF) at Longlands Farm near Sellafield. This application was rejected by the planning authority and Nirex's appeal against that decision led to a local planning inquiry which ran from September 1995 until February 1996. In line with the Inspector's Report, in March 1997 the Nirex appeal was dismissed by the Secretary of State for the Environment. The Company's response to that decision, and its readiness to contribute to the new government's review of the way forward, are described in the Nirex Annual Report for 1996-97. This report - Nirex 97 - is founded on the understanding developed through the Nirex technical programme. It reports the outcome of an assessment of the post-closure safety performance, over hundreds of thousands of years, of a repository system located in a potential

  6. Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 2; hydrogeological conceptual model development - effective parameters and calibration

    International Nuclear Information System (INIS)

    Jackson, C.; Watson, S.

    1997-01-01

    United Kingdom Nirex Limited ('Nirex') is responsible for providing and managing facilities for the safe disposal of intermediate and certain low-level radioactive waste (ILW and LLW respectively). Government policy is that the preferred disposal route for such wastes is a deep geological repository. The repository concept aims to use a combination of natural and engineered barriers to achieve the necessary degree of long-term isolation and containment of the radioactive wastes. Since 1987, Nirex has carried out an extensive technical programme directed at the science of safe disposal. The work comprises a research programme into the long-term performance of waste forms and the engineered and natural barriers, including the characterisation of candidate geological settings to assess their suitability to host a deep waste repository ('DWR'). Between mid-1991 and March 1997 the geological characterisation programme was concentrated on establishing the suitability, or otherwise, of a candidate site at Sellafield, West Cumbria. In July 1994, as part of a detailed site investigation programme, Nirex applied for planning permission to develop an underground Rock Characterisation Facility (RCF) at Longlands Farm near Sellafield. This application was rejected by the planning authority and Nirex's appeal against that decision led to a local planning inquiry which ran from September 1995 until February 1996. In line with the Inspector's Report, in March 1997 the Nirex appeal was dismissed by the Secretary of State for the Environment. The Company's response to that decision, and its readiness to contribute to the new government's review of the way forward, are described in the Nirex Annual Report for 1996-97. This report - Nirex 97 - is founded on the understanding developed through the Nirex technical programme. It reports the outcome of an assessment of the post-closure safety performance, over hundreds of thousands of years, of a repository system located in a potential

  7. Calendar Year 1997 Annual Groundwater Monitoring Report For The Bear Creek Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Jones, S.B.

    1998-02-01

    This report contains the groundwater and surface water monitoring data obtained during calendar year (CY) 1997 in compliance with the Resource Conservation and Recovery Act (RCIU) post- closure permit (PCP) for the Bear Creek Hydrogeologic Regime (Bear Creek Regime), and as otherwise required by U.S. Department of Energy (DOE) Order 5400.1. In July 1997, the Temessee Department of Environment and Conservation (TDEC) approved several modifications to the RCRA post-closure corrective action monitoring requirements specified in the PCP. This report has been prepared in accordimce with these modified requirements.

  8. Evolution of chemical conditions and estimated solubility controls on radionuclides in the residual waste layer during post-closure aging of high-level waste tanks

    Energy Technology Data Exchange (ETDEWEB)

    Denham, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Millings, M. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2012-08-28

    This document provides information specific to H-Area waste tanks that enables a flow and transport model with limited chemical capabilities to account for varying waste release from the tanks through time. The basis for varying waste release is solubilities of radionuclides that change as pore fluids passing through the waste change in composition. Pore fluid compositions in various stages were generated by simulations of tank grout degradation. The first part of the document describes simulations of the degradation of the reducing grout in post-closure tanks. These simulations assume flow is predominantly through a water saturated porous medium. The infiltrating fluid that reacts with the grout is assumed to be fluid that has passed through the closure cap and into the tank. The results are three stages of degradation referred to as Reduced Region II, Oxidized Region II, and Oxidized Region III. A reaction path model was used so that the transitions between each stage are noted by numbers of pore volumes of infiltrating fluid reacted. The number of pore volumes to each transition can then be converted to time within a flow and transport model. The bottoms of some tanks in H-Area are below the water table requiring a different conceptual model for grout degradation. For these simulations the reacting fluid was assumed to be 10% infiltrate through the closure cap and 90% groundwater. These simulations produce an additional four pore fluid compositions referred to as Conditions A through D and were intended to simulate varying degrees of groundwater influence. The most probable degradation path for the submerged tanks is Condition C to Condition D to Oxidized Region III and eventually to Condition A. Solubilities for Condition A are estimated in the text for use in sensitivity analyses if needed. However, the grout degradation simulations did not include sufficient pore volumes of infiltrating fluid for the grout to evolve to Condition A. Solubility controls for use

  9. Proposed modifications to the RCRA post-closure permit for the Upper East Fork Poplar Creek Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-05-01

    This report presents proposed modifications to the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Upper East Fork Poplar Creek Hydrogeologic Regime (permit number TNHW-088, EPA ID No. TN3 89 009 0001). The modifications are proposed to: (1) revise the current text for two of the Permit Conditions included in Permit Section II - General Facility Conditions, and (2) update the PCP with revised versions of the Y-12 Plant Groundwater Protection Program (GWPP) technical field procedures included in several of the Permit Attachments. The updated field procedures and editorial revisions are Class 1 permit modifications, as specified in Title 40, Code of Federal Regulations (CFR) section 270.42; Appendix I - Classification of Permit Modifications. These modifications are summarized below

  10. Proposed modifications to the RCRA post-closure permit for the Upper East Fork Poplar Creek Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This report presents proposed modifications to the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit (PCP) for the Upper East Fork Poplar Creek Hydrogeologic Regime (permit number TNHW-088, EPA ID No. TN3 89 009 0001). The modifications are proposed to: (1) revise the current text for two of the Permit Conditions included in Permit Section II - General Facility Conditions, and (2) update the PCP with revised versions of the Y-12 Plant Groundwater Protection Program (GWPP) technical field procedures included in several of the Permit Attachments. The updated field procedures and editorial revisions are Class 1 permit modifications, as specified in Title 40, Code of Federal Regulations (CFR) {section}270.42; Appendix I - Classification of Permit Modifications. These modifications are summarized below.

  11. Environmental monitoring plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-09-01

    This document presents an Environmental Monitoring Plan (EMP) for Waste Area Grouping (WAG 6) at Oak Ridge National Laboratory (ORNL). This document updates a draft monitoring plan developed in 1993. The draft plan was never finalized awaiting resolution of the mechanisms for addressing RCRA concerns at a site where the CERCLA process resulted in a decision to defer action, i.e., postpone closure indefinitely. Over the past two years the Tennessee Department of Environment and Conservation (TDEC), US Department of Energy (DOE), and US Environmental Protection Agency (EPA) Region IV, have agreed that RCRA authority at the site will be maintained through a post- closure permit; ''closure'' in this case referring to deferred action. Both a Revised Closure Plan (DOE 1995a) and a Post-Closure Permit Application (DOE 1995b) have been developed to document this agreement; relevant portions of the EMP will be included in the RCRA Post-Closure Permit Application. As the RCRA issues were being negotiated, DOE initiated monitoring at WAG 6. The purpose of the monitoring activities was to (1) continue to comply with RCRA groundwater quality assessment requirements, (2) install new monitoring equipment, and (3) establish the baseline conditions at WAG 6 against which changes in contaminant releases could be measured. Baseline monitoring is scheduled to end September 30, 1995. Activities that have taken place over the past two years are summarized in this document

  12. Post-Closure Evaluation of the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site in Support of the Site-Wide Environmental Impact Statement

    International Nuclear Information System (INIS)

    2011-01-01

    The post-closure performance of the Area 3 Radioactive Waste Management Site (RWMS) and Area 5 RWMS are evaluated for the Site-Wide Environmental Impact Statement using current performance assessment and composite analysis methods and models. Two alternatives with different future waste volumes and inventories are evaluated. The No Action Alternative evaluates the inventory disposed through fiscal year (FY) 2010 plus an additional 4.5E5 cubic meters (m3) (1.59E7 cubic feet (ft3)) of waste disposed at the Area 5 RWMS. The Expanded Operations Alternative evaluates the FY 2010 inventory plus an additional 1.42E6 m3 (5.03E7 ft3) of waste disposed at the Area 5 RWMS and 4.93E4 m3 (1.74E6 ft3) disposed at the Area 3 RWMS. Both the No Action and Expanded Operations Alternatives have a reasonable expectation of meeting all performance objectives of U.S. Department of Energy Order DOE O 435.1, 'Radioactive Waste Management.' No significant difference between the two alternatives was found because the waste concentrations are similar. The performance assessment model assesses radiological risk for residents at the RWMS boundary where risk is more closely related to waste concentration than total waste inventory. Results for the composite analysis also indicate that the dose constraint and dose limit can be met for both alternatives.

  13. Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage (3). Progress report on NUMO-JAEA collaborative research in FY2013 (Joint research)

    International Nuclear Information System (INIS)

    Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Kitamura, Akira; Oda, Chie; Ishidera, Takamitsu; Suyama, Tadahiro; Hatanaka, Koichiro; Kamei, Gento; Yoshikawa, Hideki; Senba, Takeshi; Seo, Toshihiro; Kurosawa, Susumu; Goto, Junichi; Shibutani, Sanae; Goto, Takahiro; Kubota, Shigeru; Inagaki, Manabu; Moriya, Toshifumi; Suzuki, Satoru; Ishida, Keisuke; Nishio, Hikaru; Makiuchi, Akie; Fujihara, Hiroshi

    2015-03-01

    JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and post-closure performance assessment in preliminary investigation stage. With regard to (1) study on host rock suitability in terms of hydrology, based on some examples of developing method of hydro-geological structure model, acquired knowledge are arranged using the tree diagram, and model uncertainty and its influence on the evaluation items were discussed. With regard to (2) study on scenario development, the developed approach for “defining conditions” has been reevaluated and improved from practical viewpoints. In addition, the uncertainty evaluation for the effect of use of cementitious material, as well as glass dissolution model, was conducted with analytical evaluation. With regard to (3) study on setting radionuclide migration parameters, based on survey of precedent procedures, multiple-approach for distribution coefficient of rocks was established, and the adequacy of the approach was confirmed through its application to sedimentary rock and granitic rock. Besides, an approach for solubility setting was developed including the procedure of selection of solubility limiting solid phase. The adequacy of the approach was confirmed through its application to key radionuclides. (author)

  14. Potential for post-closure radionuclide redistribution due to biotic intrusion: aboveground biomass, litter production rates, and the distribution of root mass with depth at material disposal area G, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    French, Sean B.; Christensen, Candace; Jennings, Terry L.; Jaros, Christopher L.; Wykoff, David S.; Crowell, Kelly J.; Shuman, Rob

    2008-01-01

    Low-level radioactive waste (LLW) generated at the Los Alamos National Laboratories (LANL) is disposed of at LANL's Technical Area (T A) 54, Material Disposal Area (MDA) G. The ability of MDA G to safely contain radioactive waste during current and post-closure operations is evaluated as part of the facility's ongoing performance assessment (PA) and composite analysis (CA). Due to the potential for uptake and incorporation of radio nuclides into aboveground plant material, the PA and CA project that plant roots penetrating into buried waste may lead to releases of radionuclides into the accessible environment. The potential amount ofcontamination deposited on the ground surface due to plant intrusion into buried waste is a function of the quantity of litter generated by plants, as well as radionuclide concentrations within the litter. Radionuclide concentrations in plant litter is dependent on the distribution of root mass with depth and the efficiency with which radionuclides are extracted from contaminated soils by the plant's roots. In order to reduce uncertainties associated with the PA and CA for MDA G, surveys are being conducted to assess aboveground biomass, plant litter production rates, and root mass with depth for the four prominent vegetation types (grasses, forbs, shrubs and trees). The collection of aboveground biomass for grasses and forbs began in 2007. Additional sampling was conducted in October 2008 to measure root mass with depth and to collect additional aboveground biomass data for the types of grasses, forbs, shrubs, and trees that may become established at MDA G after the facility undergoes final closure, Biomass data will be used to estimate the future potential mass of contaminated plant litter fall, which could act as a latent conduit for radionuclide transport from the closed disposal area. Data collected are expected to reduce uncertainties associated with the PA and CA for MDA G and ultimately aid in the assessment and subsequent

  15. Calendar year 1996 annual groundwater monitoring report for the Chestnut Ridge Hydrogeologic Regime at the U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-02-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained in the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime) during calendar year (CY) 1996. The Chestnut Ridge Regime encompasses a section of Chestnut Ridge west of Scarboro Road and east of an unnamed drainage feature southwest of the US Department of Energy (DOE) Oak Ridge Y-12 Plant (unless otherwise noted, directions are in reference to the Y-12 Plant administrative grid). The Chestnut Ridge Regime contains several sites used for management of hazardous and nonhazardous wastes associated with plant operations. Groundwater and surface water quality monitoring associated with these waste management sites is performed under the auspices of the Y-12 Plant Groundwater Protection Program (GWPP). Included in this annual monitoring report are the groundwater monitoring data obtained in compliance with the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit for the Chestnut Ridge Regime (post-closure permit) issued by the Tennessee Department of Environment and Conservation (TDEC) in June 1996. Besides the signed certification statement and the RCRA facility information summarized below, condition II.C.6 of the post-closure permit requires annual reporting of groundwater monitoring activities, inclusive of the analytical data and results of applicable data evaluations, performed at three RCRA hazardous waste treatment, storage, or disposal (TSD) units: the Chestnut Ridge Sediment Disposal Basin (Sediment Disposal Basin), the Chestnut Ridge Security Pits (Security Pits), and Kerr Hollow Quarry

  16. Calandar year 1996 annual groundwater monitoring report for the Bear Creek Hydrogeologic Regime at the US Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained in the Bear Creek Hydrogeologic Regime (Bear Creek Regime) during calendar year (CY) 1996. The Bear Creek Regime encompasses a portion of Bear Creek Valley (BCV) west of the U.S. Department of Energy (DOE) Oak Ridge Y-12 Plant (unless otherwise noted, directions are in reference to the Y-12 Plant administrative grid) that contains several sites used for management of hazardous and nonhazardous wastes associated with plant operations. Groundwater and surface water quality monitoring in the Bear Creek Regime is performed under the auspices of the Y-12 Plant Groundwater Protection Program (GWPP). This report contains the information and monitoring data required under the Resource Conservation and Recovery Act (RCRA) Post-Closure Permit for the Bear Creek Hydrogeologic Regime (post-closure permit), as modified and issued by the Tennessee Department of Environment and Conservation (TDEC) in September 1995 (permit no. TNHW-087). In addition to the signed certification statement and the RCRA facility information summarized below, permit condition II.C.6 requires the annual monitoring report to address groundwater monitoring activities at the three RCRA Hazardous Waste Disposal Units (HWDUs) in the Bear Creek Regime that are in post-closure corrective action status (the S-3 Site, the Oil Landfarm, and the Bear Creek Burial Grounds/Walk-In Pits).

  17. Procedural method for the development of scenarios in the post-closure phase. Report on the working package 1. Development of the international status of science and technology concerning methods and tools for operational and long-term safety cases; Vorgehensweise bei der Entwicklung von Szenarien fuer die Nachverschlussphase. Bericht zum Arbeitspaket 1. Weiterentwicklung des internationalen Stands von Wissenschaft und Technik zu Methoden und Werkzeugen fuer Betriebs- und Langzeitsicherheitsnachweise

    Energy Technology Data Exchange (ETDEWEB)

    Beuth, Thomas; Mayer, Kim-Marisa

    2016-09-15

    The report on the procedural method for the development of scenarios in the post-closure phase covers the following topics: development of scenarios and derivation of calculation cases, approaches for verification of derived scenarios, human penetration in a final repository (including national and international regulations and guidelines and safety standards).

  18. Evaluation of SKB's report 'Deep repository for spent nuclear fuel: SR 97 - Post-closure safety', Focusing on the assessment of transport processes in the geosphere

    Energy Technology Data Exchange (ETDEWEB)

    Woerman, A.; Shulan Xu [Uppsala Univ. (Sweden). Dept. of Geoscience

    2000-12-01

    This report describes a critical review of the safety assessment performed on the final repository for nuclear waste in Sweden that is proposed by SKB in 'Deep Repository for Spent Nuclear Fuel: SR 97 - Post-closure Safety'. The review was requested by the Swedish Nuclear Power Inspectorate (SKI). The waste repository consists of several barriers that work together with the purpose of delaying radionuclide migration and reducing the activity that eventually affects the biosphere. A main criticism is the lack of a formal risk analysis and uncertainties in several analyses that make it difficult to comprehend the overall risk of the repository. A formal risk analysis should comprise a probabilistic treatment of all components included in the system. This is not the case in the SKB's report since the probabilistic analyses are limited only to certain aspects. The use of conservative model parameters are not a substitute for risk analysis nor can they compensate for possible model biases. Bias can be expected in most of the existing models of radionuclide migration in fractured bedrock. SKB should present a clear comparison on the importance of the different barrier components (uranium-dioxide matrix, copper canister, buffer and bedrock) on the retardation of radionuclides. It is unclear as to what extent the capacity of the bedrock to retain migrating radionuclides is critical to the capacity of the repository. A large part of the SR 97 report is focused on retardation processes in bedrock and a reader can interpret this as the technical weight given on retardation in the bedrock. However, with the present state of knowledge, it is our opinion that we cannot with an acceptable degree of accuracy predict the radionuclide transport in bedrock or quantify risk levels associated with radioactivity in the biosphere. There are large uncertainties concerning the way by which sorption processes should be formulated and the impact of colloids on the transport

  19. Annual report of 1995 groundwater monitoring data for the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-02-01

    The Kerr Hollow Quarry (KHQ) and the Chestnut Ridge Sediment Disposal Basin (CRSDB) are inactive waste management sites located at the Oak Ridge Y-12 Plant. The KHQ and CRSDB are regulated as treatment, storage, or disposal (TSD) facilities under the Resource Conservation and Recovery Act (RCRA). The facilities were granted interim status in calendar year (CY) 1986 under Tennessee Department of Environment and Conservation (TDEC) Hazardous Waste Management Rule 1200-1-11-.05. Historical environmental monitoring data and baseline characterization under interim status indicated that releases of contaminants to groundwater had not occurred; thus, the detection monitoring was implemented at the sites until either clean closure was completed or post-closure permits were issued. The CRSDB was closed in Cy 1989 under a TDEC-approved RCRA closure plan. A revised RCRA PCPA for the CRSDB was submitted by DOE personnel to TDEC staff in September 1994. A final post-closure permit was issued by the TDEC on September 18, 1995. Closure activities at KHQ under RCRA were completed in October 1993. The Record of Decision will also incorporate requirements of the RCRA post-closure permit once it is issued by the TDEC

  20. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels: FY2015 and FY2016

    Energy Technology Data Exchange (ETDEWEB)

    Mizell, Steve A [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Campbell, Scott A [Desert Research Inst. (DRI), Las Vegas, NV (United States)

    2017-10-01

    The Desert Research Institute (DRI) is conducting a field assessment of the potential for contaminated soil to be transported from the Smoky Contamination Area (CA) as a result of storm runoff. This activity supports Nevada Nuclear Security Administration (NNSA) efforts to complete regulatory closure of the Soils Corrective Action Unit (CAU) contamination areas. The work is intended to confirm the likely mechanism of transport and determine the meteorological conditions that might cause movement of contaminated soils, as well as determine the particle size fraction that is most closely associated with transported radionuclide-contaminated soils. These data will facilitate the appropriate closure design and post-closure monitoring program.

  1. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels: FY2013 and FY2014 (revised)

    Energy Technology Data Exchange (ETDEWEB)

    Mizell, Steve A. [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J. [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg D. [Desert Research Inst. (DRI), Reno, NV (United States); Campbell, Scott A. [Desert Research Inst. (DRI), Las Vegas, NV (United States)

    2017-06-01

    The Desert Research Institute (DRI) is conducting a field assessment of the potential for contaminated soil to be transported from the Smoky Contamination Area (CA) as a result of storm runoff, which supports National Nuclear Security Administration (NNSA) efforts to complete regulatory closure of the Soils Corrective Action Unit (CAU) contamination areas. The work is intended to confirm the likely mechanism of transport and determine the meteorological conditions that might cause movement of contaminated soils, as well as determine the particle size fraction that is most closely associated with transported radionuclide-contaminated soils. These data will facilitate the appropriate closure design and post-closure monitoring program.

  2. Study of the post-closure provisions for managing solid tailings from the extraction and processing of uranium ores resulting from the industrial activities of the COMUF company at Mounana, Gabon

    International Nuclear Information System (INIS)

    Loueyit, C.J.; Keiffer, B.; Fourcade, S.; Nzengue, J.C.; Bernhard, S.

    2002-01-01

    Between 1961 and 1999 COMUF extracted about 28 000 metric tons of uranium from the Mounana mining district. This production generated about 7.5 million tons of processing tailings that are stored in areas close to the installations. In the context of the European programme 'SYSMIN', the government of the Gabonese Republic commissioned a study to specify the measures to be taken for the restoration of the Mounana mining site and the radiological monitoring to be put in place after the COMUF installations close down. The methodology applied and the restoration and monitoring work undertaken must respect the requirement for an annual added effective dose of less than 1 mSv for persons in the critical population groups. (author)

  3. Spring 2009 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post-Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    International Nuclear Information System (INIS)

    Boehmer, Ann M.

    2009-01-01

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under and approved Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure plan. Vessels and spaces were grouted and then covered with a concrete cap. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment.

  4. Spring 2009 Semiannual (III.H. and I.U.) Report for the HWMA/RCRA Post-Closure Permit for the INTEC Waste Calcining Facility at the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Boehmer, Ann M.

    2009-05-31

    The Waste Calcining Facility is located at the Idaho Nuclear Technology and Engineering Center. In 1999, the Waste Calcining Facility was closed under and approved Hazardous Waste Management Act/Resource Conservation and Recovery Act Closure plan. Vessels and spaces were grouted and then covered with a concrete cap. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the Waste Calcining Facility to ensure continued protection of human health and the environment.

  5. Calendar Year 1997 Annual Groundwater Monitoring Report For The Chestnut Ridge Hydrogeologic Regime At The U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Jones, S.B.

    1998-02-01

    This report contains the groundwater monitoring data obtained during calendar year (CY) 1997 in compliance with the Resource Conservation and Recovery Act (RCRA) post-closure permit (PCP) for the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). In July 1997, the Tennessee Department of Environment and Conservation (TDEC) approved modifications to several of the permit conditions that address RCRA pow-closure corrective action groundwater monitoring at the Chestnut Ridge Security Pits (Security Pits), and RCIU4 post-closure detection groundwater monitoring at the Chestnut Ridge Sediment Disposal Basin (Sediment Disposal Basin) and Kerr Hollow Quarry. This report has been prepared in accordance with these modified permit requirements. Also included in this report are the groundwater and surface water monitoring data obtained during CY 1997 for the purposes ofi (1) detection monitoring at nonhazardous solid waste disposal facilities (SWDFS) in accordance with operating permits and applicable regulations, (2) monitoring in accordance with Comprehensive Environmental Response, Compensation, and Recove~ Act Records of Decision (now pefiormed under the Integrated Water Quality Program for the Oak Ridge Reservation), and (3) monitoring needed to comply with U.S. Department of Energy Order 5400.1.

  6. Multi-physical process and system analysis for geological underground repositories in clay formations in the post closure phase; Multiphysikalische Prozess- und Systemanalyse fuer geologische Tiefenlager im Tonsteingebirge in der Nachverschlussphase

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, Juan

    2017-09-21

    generic repository system in clay stone rock mass without or with consideration of a monitoring level. Variation parameters are the corrosion rate of the waste containers, the permeability of the geotechnical barriers as well as of the geologic barrier, the assumption of a primarily existent vertically or horizontally directed hydraulic gradient, the assumption of undiscovered disturbance zones in the rock mass, and the thickness of the host rock (geologic barrier). In order to improve the understanding of the system, the fluid dynamics processes taking place in the repository system have been visualised for different points of time. The calculated time-dependent development of the mechanical, thermal and hydraulic state variables in the near-field of the disposal facility may in principle also be used as comparison values for the monitoring of the repository.

  7. The long path to a disposal for high radioactive waste. Pt. 1. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hochradioaktive Waerme entwickelnde Abfaelle. T. 1. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponiertechnik und Geomechanik

    2017-03-15

    A new conceptual-configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long-term monitoring are presented and discussed. With regard to the final repository development, a retrievability of the heat-generating high-radioactive waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post-closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

  8. The long path to a disposal for high radioactive waste. Pt. 2. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hoch radioaktive Waerme entwickelnde Weg Abfaelle. T. 2. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponietechnik und Geomechanik

    2017-04-15

    A new conceptual-configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long term monitoring are presented and discussed. With regard to the final repository development, a retrieveability of the heat generating high radio active waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

  9. Environmental monitoring data review of a uranium ore processing facility in Argentina

    International Nuclear Information System (INIS)

    Bonetto, J.

    2014-01-01

    An uranium ore processing facility in the province of Mendoza (Argentina) that has produced uranium concentrate from 1954 to 1986 is currently undergoing the last steps of environmental restoration. The operator has been performing post-closure environmental monitoring since 1986, while the Nuclear Regulatory Authority (ARN) has been carrying out its own independent radiological environmental monitoring for verification purposes since its creation, in 1995. A detailed revision of ARN´s monitoring plan for uranium mining and milling facilities has been undergoing since 2013, starting with this particular site. Results obtained from long-time sampling locations (some of them currently unused) have been analyzed and potentially new sampling points have been studied and proposed. In this paper, some statistical analysis and comparison of sampling-points’ datasets are presented (specifically uranium and radium concentration in groundwater, surface water and sediments) with conclusions pertaining to their keeping or discarding as sampling points in future monitoring plans. (author)

  10. Approach to geologic repository post closure system performance assessment

    International Nuclear Information System (INIS)

    Pahwa, S.B.; Felton, W.; Duguid, J.O.

    1992-01-01

    An essential part of the license application for a geologic repository will be the demonstration of compliance with the standards set by the Environmental Protection Agency. The performance assessments that produce the demonstration must rely on models of various levels of detail. The most detailed of these models are needed for understanding thoroughly the complex physical and chemical processes affecting the behavior of the system. For studying the behavior of major components of the system, less detailed models are often useful. For predicting the behavior of the total system, models of a third kind may be needed. These models must cover all the important processes that contribute to the behavior of the system, because they must estimate the behavior under all significant conditions for 10,000 years. In addition, however, computer codes that embody these models must calculate very rapidly because of the EPA standard's requirement for probabilistic estimates, which will be produced by sampling thousands of times from probability distributions of parameters. For this reason, the total-system models must be less complex than the detailed-process and subsystem models. The total-system performance is evaluated through modeling of the following components: Radionuclide release from the engineered-barrier system. Fluid flow in the geologic units. Radionuclide transport to the accessible environment. Radionuclide release to the accessible environment and dose to man

  11. Threats and opportunities for post-closure development in dolomitic ...

    African Journals Online (AJOL)

    AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search ... slimes dams include the establishment of a large game reserve on donated land as well as ... capitalise on existing infrastructure and former expertise and benefit from the ...

  12. Review of SKB's report, SR 97 - Post-closure safety

    International Nuclear Information System (INIS)

    Holmlund, P.

    2000-01-01

    The climate and glaciation scenarios are described in detail and largely adequately supported by data. The deficiencies that I have chosen to point out are serious from the point of view of principle. I have not attempted to assess the significance of these deficiencies for a future repository. The climate predictions used in the reports are internationally generally accepted models, which can be said to be uncontroversial. However, they have been overutilized in that too much confidence has been placed in the results. The uncontroversial part of the climate scenario is the predicted development, that is, that there will be alternating cold and warm periods over the next hundred thousand year period, like we have experienced during the last glacial cycle. However, time and temperature data are naturally highly uncertain. As a reviewer, it is difficult for me to understand why priority has not been given to reconstructing events that have occurred at the possible repository sites studied in the report instead of performing general calculations based on the highly inaccurate future scenarios. High resolution data are available from the last glacial cycle. Geological evidence is also available which provides information on temperature conditions within and beneath the ice and, thereby, also provides information on the hydrology of the ice and beneath the ice. We know a great deal about these conditions, but nothing about the future. The modelling of extent of the ice sheet is not significantly different from other model experiments, which means that it largely reflects what most researchers consider to have occurred and likely to occur. However, the modelling results relating to the temperature distribution are highly controversial. These results are not supported by other modelling data, which on the contrary clearly indicate temperature patterns in and beneath the ice, which deviate from SR 97. The classification into ice divide zones and melting zones lacks a physical basis for the meanings given to these concepts in the report. Although these are only qualitative descriptions of the model designers' assumptions, the results are used quantitatively. Furthermore, the coupling to hydrology includes irrelevant descriptions of how the subglacial drainage in temperate glaciers has a seasonal variation, due to a hydraulic coupling between the surface and the base of the ice. The ice sheets that have covered and will cover Scandinavia are of a cold polar type, which lacks this hydrological coupling between the ice surface and the base, apart from possibly in frontal zones. The report clearly describes the ice as temperate, which must be considered to be an error that has a considerable impact on predictions concerning the subglacial water flow. GCM models have not been applied. The climate is complex and changes in the topography in the form of a growing North American continental ice sheet, change the circulation pattern and, thereby, the distribution of precipitation. Knowledge is available in this area, but this knowledge is not applied in the report. Furthermore, the fact that no sensitivity tests have been conducted of the climate and glacial scenario is surprising

  13. Threats and opportunities for post-closure development in dolomitic ...

    African Journals Online (AJOL)

    2009-12-09

    Dec 9, 2009 ... This uncertainty is exacerbated by the long time periods required for pro-active ... The loss of 'institutional memory' and local expertise has been identified as .... being lost, Potchefstroom may suffer from extended water short-.

  14. Threats and opportunities for post-closure development in dolomitic ...

    African Journals Online (AJOL)

    Mining-related impacts such as large-scale land degradation associated with dewatering of karstic aquifers and widespread pollution of surface water and groundwater systems are discussed. Based on this, potential threats and opportunities for post-mining scenarios are identified in a series of 3 papers. Part 1 of this series ...

  15. Threats and opportunities for post-closure development in dolomitic ...

    African Journals Online (AJOL)

    Owing to the pivotal role of water in the semi-arid area and the fact that some of the most important groundwater resources of South Africa were impacted on by deep-level mining, this paper in 3 parts adopted a largely hydraulic perspective. The loss of 'institutional memory' and local expertise has been identified as the ...

  16. 40 CFR 264.119 - Post-closure notices.

    Science.gov (United States)

    2010-07-01

    ...) STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Closure... closure of each hazardous waste disposal unit, the owner or operator must submit to the local zoning... disposal unit of the facility. For hazardous wastes disposed of before January 12, 1981, the owner or...

  17. Threats and opportunities for post-closure development in dolomitic ...

    African Journals Online (AJOL)

    Large-scale environmental degradation in the form of sinkholes and widespread radioactive pollution exacerbate such fears. ... Possibilities for using waste land such as sinkhole areas and slimes dams include the establishment of a large game reserve on donated land as well as using tailings for biofuel production and ...

  18. NNSS Soils Monitoring: Plutonium Valley (CAU 366) FY2016

    Energy Technology Data Exchange (ETDEWEB)

    Nikolich, George [Desert Research Inst. (DRI), Las Vegas, NV (United States); Mizell, Steve [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Campbell, Scott [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J. [Desert Research Inst. (DRI), Las Vegas, NV (United States)

    2017-10-01

    Desert Research Institute (DRI) is conducting a field assessment of the potential for contaminated soil transport from the Plutonium Valley Contamination Area (CA) as a result of wind transport and storm runoff in support of National Nuclear Security Administration (NNSA) efforts to complete regulatory closure of the contamination areas. The DRI work is intended to confirm the likely mechanism(s) of transport and determine the meteorological conditions that might cause movement of contaminated soils. The emphasis of the work is on collecting sediment transported by channelized storm runoff at the Plutonium Valley investigation sites. These data will inform closure plans that are being developed, which will facilitate the appropriate closure design and post-closure monitoring.

  19. Thematic Network on The role of Monitoring in a Phased Approach to Disposal - EUR 21025, 2004. Conclusions of the EC Thematic Network on The role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    Barlow, Stephen

    2005-01-01

    The EC thematic network on the role of monitoring in a phased approach to the geological disposal of radioactive waste brought together expertise from twelve organisations from ten countries. It was started in 2001 following on from an earlier EC study of retrievability and reversibility (EUR 19145 EN), and completed in 2004 with publication of the final report (EUR 21025 EN). The project mainly aimed to: - Understand the approaches to monitoring in each national programme and their dependency on concepts and approaches. - Distil consensus views and recognise alternative approaches to monitoring. - Share technical knowledge and experience. - Communicate views and experiences. Participants from the projects looked at various definitions of monitoring in relation to a phased approach to disposal, and achieved a consensus on the following: 'Continuous or periodic observations and measurements of engineering, environmental, radiological or other parameters and indicators/characteristics, to help evaluate the behaviour of components of the repository system, or the impacts of the repository and its operation on the environment, and to help in making decisions on the implementation of successive phases of the disposal concept'. That definition is mainly based on an IAEA definition with a few modifications and, in particular, by adding the fact that monitoring has a role in making decisions. Various alternative approaches to make decisions and achieve goals were analysed and the need was stressed for a flexible schedule with a degree of concept flexibility. The project achieved a consensus on the following principles: (i) monitoring has a role in underpinning and verification of operational safety (compliance monitoring); (ii) long-term (post-closure) safety must be assured by design - it cannot rely on monitoring, although monitoring may be implemented for other reasons - monitoring must not be detrimental to long-term (post-closure) safety (iii) monitoring

  20. VAMOS: The verification and monitoring options study: Current research options for in-situ monitoring and verification of contaminant remediation and containment within the vadose zone

    International Nuclear Information System (INIS)

    Betsill, J.D.; Gruebel, R.D.

    1995-09-01

    The Verification and Monitoring Options Study Project (VAMOS) was established to identify high-priority options for future vadose-zone environmental research in the areas of in-situ remediation monitoring, post-closure monitoring, and containment emplacement and verification monitoring. VAMOS examined projected needs not currently being met with applied technology in order to develop viable monitoring and verification research options. The study emphasized a compatible systems approach to reinforce the need for utilizing compatible components to provide user friendly site monitoring systems. To identify the needs and research options related to vadose-zone environmental monitoring and verification, a literature search and expert panel forums were conducted. The search included present drivers for environmental monitoring technology, technology applications, and research efforts. The forums included scientific, academic, industry, and regulatory environmental professionals as well as end users of environmental technology. The experts evaluated current and future monitoring and verification needs, methods for meeting these needs, and viable research options and directions. A variety of high-priority technology development, user facility, and technology guidance research options were developed and presented as an outcome of the literature search and expert panel forums

  1. Liquid effluent retention facility final-status groundwater monitoring plan

    International Nuclear Information System (INIS)

    Sweeney, M.D.; Chou, C.J.; Bjornstad, B.N.

    1997-09-01

    The following sections describe the groundwater-monitoring program for the Liquid Effluent Retention Facility (LERF). The LERF is regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The LERF is included in the open-quotes Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, Permit WA890008967close quotes, (referred to herein as the Permit) (Ecology 1994) and is subject to final-status requirements for groundwater monitoring (WAC 173-303-645). This document describes a RCRA/WAC groundwater detection-monitoring program for groundwater in the uppermost aquifer system at the LERF. This plan describes the LERF monitoring network, constituent list, sampling schedule, statistical methods, and sampling and analysis protocols that will be employed for the LERF. This plan will be used to meet the groundwater monitoring requirements from the time the LERF becomes part of the Permit and through the post-closure care period, until certification of final closure

  2. Monitoring during the stepwise implementation of the Swedish deep repository for spent fuel

    International Nuclear Information System (INIS)

    Baeckblom, Goeran; Almen, Karl-Erik

    2004-03-01

    terminate, quality control and reporting results from monitoring, decision on trigger levels for actions, decisions on what actions should be pursued in case trigger levels are exceeded). The site investigations in progress in Sweden essentially capture these elements in the investigation programme, but due to reasons of transparency it is however helpful that the present monitoring programme is further elaborated to clarify duration, frequency and criteria for terminating monitoring points. The current situation is reasonable due to the early stage of investigations and it is foreseen that the monitoring programme successively will be developed to meet the needs of the subsequent construction phase. There are of course still many open questions to address with respect to monitoring, not the least concerning monitoring of the open repository to collect data to verify barrier performance before closing the repository. Repository performance and safety cannot be directly monitored, but it would be of great significance that key indicators are determined to constitute a basis for tracking the performance of the repository during the repository implementation. Repository closure is a stepwise process from consecutively closing a deposition tunnel to closing one or several deposition areas before the whole repository is closed. It is possible that rationales for monitoring of the post-closure phase, such as verification of safeguard requirements, may develop. The extent of the post-closure monitoring programme will essentially be given by the decisions made at closure and it is appropriate that any decisions on post-closure monitoring are taken by the generation that is the decision-maker at the time of closure. While the responsibility for the repository is transferred to the State after closure it is then also needed to clarify the responsibility for execution of the post-closure monitoring

  3. Annual report of 1991 groundwater monitoring data for the Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin at the Y-12 Plant: Reporting and statistical evaluation of the subsequent year (sixth) data

    International Nuclear Information System (INIS)

    McMahon, L.W.; Mercier, T.M.

    1992-02-01

    This annual report has historically been prepared to meet the annual reporting requirements of the Tennessee Department of and Environment and Conservation (TDEC), Hazardous Waste Management Regulation 1200-1-11-.05 (6)(e), for detection monitoring data collected on Resource Conservation and Recovery Act (RCRA) wells in place around facilities which are accorded interim status. The regulatory authority for these units at the Y-12 Plant is currently in transition. A Federal Facility Agreement (FFA) with an effective date of January 1, 1992, has been negotiated with the Department of Energy (DOE) for the Oak Ridge Reservation. This agreement provides a framework for remediation of the Oak Ridge Reservation so that both RCRA and CERCLA requirements are integrated into the remediation process and provides for State, EPA, and DOE to proceed with CERCLA as the lead regulatory requirement and RCRA as an applicable or relevant and appropriate requirement. This report is presented for the RCRA certified wells for two interim status units at the Y-12 Plant. These units are Kerr Hollow Quarry and Chestnut Ridge Sediment Disposal Basin. Kerr Hollow is currently undergoing clean closure under RCRA. The Chestnut Ridge Sediment Disposal Basin (CRSDB) was closed in 1989 under a TDEC approved RCRA closure plan. The relevance of a RCRA Post-Closure Permit to either of these units is a matter of contention between DOE and TDEC since the FFA does not contemplate post-closure permits

  4. NNSS Soils Monitoring: Plutonium Valley (CAU 366) FY2015

    Energy Technology Data Exchange (ETDEWEB)

    Nikolich, George [Desert Research Inst. (DRI), Las Vegas, NV (United States); Mizell, Steve [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Reno, NV (United States); Campbell, Scott [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J. [Desert Research Inst. (DRI), Las Vegas, NV (United States)

    2017-02-01

    Desert Research Institute (DRI) is conducting a field assessment of the potential for contaminated soil transport from the Plutonium Valley Contamination Area (CA) as a result of wind transport and storm runoff in support of National Nuclear Security Administration (NNSA) efforts to complete regulatory closure of the contamination areas. The DRI work is intended to confirm the likely mechanism(s) of transport and determine the meteorological conditions that might cause movement of contaminated soils. The emphasis of the work is on collecting sediment transported by channelized storm runoff at the Plutonium Valley investigation sites. These data will inform closure plans that are being developed, which will facilitate the appropriate closure design and post-closure monitoring. In 2011, DRI installed two meteorological monitoring stations south (station #1) and north (station #2) of the Plutonium Valley CA and a runoff sediment sampling station within the CA. Temperature, wind speed, wind direction, relative humidity, precipitation, solar radiation, barometric pressure, soil temperature, and airborne particulate concentration are collected at both meteorological stations. The maximum, minimum, and average or total (as appropriate) for each of these parameters are recorded for each 10-minute interval. The sediment sampling station includes an automatically activated ISCO sampling pump with collection bottles for suspended sediment, which is activated when sufficient flow is present in the channel, and passive traps for bedload material that is transported down the channel during runoff events. This report presents data collected from these stations during fiscal year (FY) 2015.

  5. The long path to a disposal for high radioactive waste. Pt. 3. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hochradioaktive, Waerme entwickelnde Abfaelle. T. 3. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponiertechnik und Geomechanik

    2017-05-15

    A new conceptual@configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long-term monitoring are presented and discussed. With regard to the final repository development, a retrieveability of the heat-generating high-radio-active waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post-closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

  6. Monitoring water content in Opalinus Clay within the FE-Experiment: Test application of dielectric water content sensors

    Science.gov (United States)

    Sakaki, T.; Vogt, T.; Komatsu, M.; Müller, H. R.

    2013-12-01

    The spatiotemporal variation of water content in the near field rock around repository tunnels for radioactive waste in clay formations is one of the essential quantities to be monitored for safety assessment in many waste disposal programs. Reliable measurements of water content are important not only for the understanding and prediction of coupled hydraulic-mechanic processes that occur during tunnel construction and ventilation phase, but also for the understanding of coupled thermal-hydraulic-mechanical (THM) processes that take place in the host rock during the post closure phase of a repository tunnel for spent fuel and high level radioactive waste (SF/HLW). The host rock of the Swiss disposal concept for SF/HLW is the Opalinus Clay formation (age of approx. 175 Million years). To better understand the THM effects in a full-scale heater-engineered barrier-rock system in Opalinus Clay, a full-scale heater test, namely the Full-Scale Emplacement (FE) experiment, was initiated in 2010 at the Mont Terri underground rock laboratory in north-western Switzerland. The experiment is designed to simulate the THM evolution of a SF/HLW repository tunnel based on the Swiss disposal concept in a realistic manner during the construction, emplacement, backfilling, and post-closure phases. The entire experiment implementation (in a 50 m long gallery with approx. 3 m diameter) as well as the post-closure THM evolution will be monitored using a network of several hundred sensors. The sensors will be distributed in the host rock, the tunnel lining, the engineered barrier, which consists of bentonite pellets and blocks, and on the heaters. The excavation is completed and the tunnel is currently being ventilated. Measuring water content in partially saturated clay-rich high-salinity rock with a deformable grain skeleton is challenging. Therefore, we use the ventilation phase (before backfilling and heating) to examine the applicability of commercial water content sensors and to

  7. Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds

    International Nuclear Information System (INIS)

    2006-01-01

    The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been restricted to lined trenches and the Navy reactor-compartment trench only. Hence, as of July 2004, only the two lined trenches in burial ground 218-W-5 (trenches 31 and 34, see Appendix A) and the Navy reactor-compartment trench in burial ground 218 E 12B (trench 94) are allowed to receive waste. When the two lined trenches are filled, the LLBG will cease to operate except for reactor compartment disposal at trench 94. Remaining operational lifetime of the LLBG is dependent on waste volume disposal rates. Existing programs for air sampling and analyses and subsidence monitoring are currently adequate for performance assessment at the LLBG. The waste disposal authorization for the Hanford Site is based (in part) on the post-closure performance assessments for the LLBG. In order to maintain a useful link between operational monitoring (e.g., Resource Conservation and Recovery Act [RCRA], Comprehensive Environmental Response, Compensation, and Liability Act, and State Waste Discharge Permits), constituents, monitoring frequencies, and boundaries require

  8. Topical session proceedings of the 6. IGSC Meeting. The role of monitoring in a safety case

    International Nuclear Information System (INIS)

    2005-01-01

    This report summarises the outcomes of a topical session focused on the role of monitoring in a safety case. It was held as part of the 6. plenary meeting of the IGSC. It was attended by 39 participants, representing waste management organisations and regulatory authorities from 15 NEA member countries, the IAEA and the European Commission. The main purpose of this topical session was to create a platform for exchanging views on the key monitoring issues of interest to build confidence in a safety case e.g. relationship with the post-closure phase, functions, requirements, and to determine to what extent the main actions are to be addressed by the IGSC on its ongoing activities on defining the elements of a safety case. The topical session was indeed mainly aimed at exchanging information on: - National strategies or programmes in NEA members' countries. Member countries have organisations planning their own strategy, but some are already, to some extend engaged in implementing monitoring activities, e.g. Posiva Oy, US-DOE-YM, Andra. - Feedback from international projects, e.g. the EC Thematic Network on 'The role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste', and the IAEA programme of work. - The expectations of regulators, e.g. SKI. Part A of this document summarises the material orally presented and provides the main lessons drawn from the presentations and the discussions that followed them. The overheads presented are compiled without any further elaboration by the NEA Secretariat as Part B of the document. Part C gives the list of participants. The document as a whole provides a synthesis of current issues in monitoring of a deep geological disposal facility

  9. Review. Deep repository for spent nuclear fuel SR 97 - Post-closure safety

    International Nuclear Information System (INIS)

    Stephansson, Ove

    2000-01-01

    SKB states that the chosen scenarios provide good coverage of future evolutionary pathways for the deep repository. This is not the case. SKB has not made full use of the established interaction matrices and the new method of THMC diagrams to generate the relevant and important scenarios and to construct the important pathways of variables and processes, either in the established interaction matrices and the presented THMC diagrams. Hence, SKB is demonstrating in SR 97 that they lack a well thought through, sound and solid method to select and evaluate scenarios for the purpose of demonstrating the safety of a deep repository for spent nuclear fuel. The evolution of the system is presented for the components of the repository system (fuel, canister, buffer/backfill, geosphere) and the effects of four different scenarios, but time only enters into the system for discrete events or processes, e.g. description of the relative radiotoxicity and heat decay of the fuel, temperature distribution, iron exchange process, pH in buffer, redox capacity and radionuclear release at the three sites. There is a lack of method and way of describing the evolution of the complete repository system, including the major scenarios, as a function of time. It is essential that SKB is able to: - consider the full range of potential scenarios, - grade the scenarios according to their significance for repository design and performance and safety assessment, - consider whether simple engineering actions could be taken to inhibit the development of adverse scenarios. This cannot be done with the system presented in SR 97, and so SKB do not have a full predictive capability - which is required for the engineering design of such an important and costly structure as a repository. Geoscientific investigation material for three selected sites are presented by SKB in the technical report dealing with waste, repository design and sites. Here a general overview is missing of the geological and rock mechanical development of the respective areas and their place in space and time during the geological evolution of the Baltic Shield. This makes it difficult to rank the suggested sites based on their past, present and future geological evolution. The problem of large discrepancies in data needs to be resolved before stress measurements are performed at future sites. For stress measurements in general and the demand of good quality data at the future sites, there is a need for integrated stress analysis where data from different stress measurements methods (overcoring, hydrofracturing, hydraulic testing of pre-existing fractures and focal mechanism studies) are combined in an integrated stress analysis. Results from orientation of horizontal components from the stress measurements at the three sites clearly demonstrate the relatively large variation in orientation both at each site and between different sites. The relationship between the state of stress and the location and orientation of the major fracture zones is of outmost importance in a future location of a final repository. Preliminary repository layout was constructed by SKB for each selected repository site to accommodate approximately 4,000 canisters. From rock stability point of view the deposition tunnels should be oriented parallel with the orientation of the maximum horizontal principal stress. This is one of the fundamental principles in rock engineering. However, SKB prefer to orient the tunnel axes perpendicular to the maximum stress because the fracture zones and their respect distance, the orientation of water-bearing fracture zones and the area for repository location does not allow a proper tunnel orientation with respect to the orientation of the horizontal rock stresses. The orientation of the tunnels as suggested might lead to spalling or other types of failure of the tunnels and deposition hole. There has been a number of international studies about this problem and SKB has to give this problem additional studies to form a strategy for the future orientation of tunnels and deposition holes. In chapter 5 of the report on Waste, repository design and sites, SKB presents site-specific adaptation of the repository. In the section about repository design, there is a lack of information about the design method that will be applied for the repository. There are no references to standard literature about rock engineering design and design methods for underground constructions. There is a need for SKB to determine the design methods as this information is independent of the selection of a finale site for a repository. SKB advocates 'Design as you go' as an active approach during the process leading up to a finished repository and claims this as being important for safety. This method of constructing underground space can be applied for structures were safety demands are not particular important. However, the method is far from being applicable for construction of a final repository of radioactive waste. The public opinion will hardly accept such a strategy. This approach is also difficult to manage for the authorities as revised plans, safety documents and control systems have to be checked and revised continuously. To some extent this approach has been demonstrated during the present construction of the extension of the CLAB facilities of SKB and has not been functioning well. The design method 'design as you go' cannot be accepted for a repository for radioactive waste. The design issues need to be sorted out beforehand. Only minor variations can be allowed at the time of excavation, e.g. the precise position of the canister holes

  10. Deep repository for spent nuclear fuel. SR 97 - Post-closure safety. Main Report. Summary

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere and biosphere are analyzed in the canister defect scenario. Releases from the geosphere are converted to doses in different ecosystems. The variation in flow-related data in the geosphere has the greatest impact on the result, followed by data uncertainties for the biosphere. Other conclusions are that our understanding of fuel dissolution needs to be improved, and that the probability and size of initial canister defects that escape quality-control inspection is difficult to estimate. Risk analyses in the form of simplified probabilistic calculations are also performed. The risk analyses show that all sites lie well below the acceptance criterion. The maximum risk for release to a well is never more than 0.5 percent of the acceptance criterion, even when the calculations are extended a million years into the future. The same applies to releases to peat land for times up to 100,000 years, while the maximum risk here grows to about one-tenth of the acceptance criterion at the least favourable site at times after 100,000 years. The consequences of future climate change are explored in the climate scenario. A conceivable sequence of events, including severe glaciation, on each of the three sites is sketched for the coming 150,000 years. In the climate scenario as well, the overall conclusion is that the isolating capacity of the copper canister is not threatened by either mechanical or chemical stresses. As far as the retarding capacity of the repository is concerned, for example in the event of initial canister damage, the most important changes take place in the biosphere. The repository sites are expected to be covered by ice sheets or sea during long periods, and the aggregate effect of climate change will therefore be a reduction of the dose consequences compared with a situation where the present-day climate persists. In the earthquake scenario, the consequences of earthquakes are analyzed by means of model studies where site-specific data are used for the structure of the geosphere and for earthquake statistics. The analysis method is new and includes several highly pessimistic simplifications. The analyses show that the probability of canister damage is comparable with the probability assumed for initial damage in the canister defect scenario. In the evaluation of the analysis method, it is shown how less pessimistic assumptions should lead to no canister damage at all in the model studies. The method will be refined. The scenario that deals with future inadvertent human actions that could conceivably affect the repository is surrounded by great uncertainties, chiefly because the evolution of human society is unpredictable. SR 97 discusses how conceivable societal evolutions and future human actions that affect the repository can nevertheless be categorized to some extent. In an illustrative example, a situation is analyzed where a canister in the repository is inadvertently penetrated by rock drillers. (abstract truncated)

  11. Data Management to Support a Post-closure Safety Case for Higher Activity Wastes

    International Nuclear Information System (INIS)

    Carter, Alexander; Bailey, Lucy

    2016-01-01

    Lessons Learned: • Make sure data and modelling responsibilities and accountabilities are clearly defined and in the hands of suitable qualified and experienced staff. • Make clear what types of data are, and are not, within the scope of the data management system. • Consider data quality from the outset and record this with the data where possible (ideally during acquisition). • Don’t underestimate the time taken to manage data and quality check models – needs senior management support with business prioritisation to work most effectively. • Store data in an electronic format which can be retrieved and used/reused – consider automatic export into modelling software, data reports etc. (well received by reviewers). • Take care with data precision. • Make sure you understand where models exist in your organisation and how significant they are to your business. • Make sure uncertainties in model outputs are understood and communicated with the results

  12. Post-closure biosphere assessment modelling: comparison of complex and more stylised approaches

    Energy Technology Data Exchange (ETDEWEB)

    Walke, Russell C. [Quintessa Limited, The Hub, 14 Station Road, Henley-on-Thames (United Kingdom); Kirchner, Gerald [University of Hamburg, ZNF, Beim Schlump 83, 20144 Hamburg (Germany); Xu, Shulan; Dverstorp, Bjoern [Swedish Radiation Safety Authority, SE-171 16 Stockholm (Sweden)

    2014-07-01

    Geological facilities are the preferred option for disposal of high-level radioactive waste, due to their potential to provide isolation from the surface environment (biosphere) on very long time scales. Safety cases developed in support of geological disposal include assessment of potential impacts on humans and wildlife in order to demonstrate compliance with regulatory criteria. As disposal programmes move from site-independent/generic assessments through site selection to applications for construction/operation and closure, the degree of understanding of the present-day site increases, together with increased site-specific information. Assessments need to strike a balance between simple models and more complex approaches that draw more extensively on this site-specific information. This paper explores the relative merits of complex versus more stylised biosphere models in the context of a site-specific assessment. The complex biosphere model was developed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for the Formark candidate site for a spent nuclear fuel repository in Sweden. SKB's model is built on a landscape evolution model, whereby radionuclide releases to distinct hydrological basins/sub-catchments (termed 'objects') are represented as they evolve through land rise and climate change. The site is located on the Baltic coast with a terrestrial landscape including lakes, mires, forest and agriculture. The land at the site is projected to continue to rise due to post-glacial uplift leading to ecosystem transitions in excess of ten thousand years. The simple biosphere models developed for this study include the most plausible transport processes and represent various types of ecosystem. The complex biosphere models adopt a relatively coarse representation of the near-surface strata, which is shown to be conservative, but also to under-estimate the time scale required for potential doses to reach equilibrium with radionuclide fluxes to the biosphere. Some radionuclides do not reach equilibrium within the time frame that the biosphere evolves at the Forsmark site, making associated dose factors sensitive to time scales assumed for biosphere evolution. Comparison of the results generated by both types of model demonstrates that, for areas that evolve from marine, through lakes and mires to terrestrial systems with organic soils, the approach adopted in SKB's model is conservative. However, higher dose factors are possible when potential for long-term irrigation with shallow groundwater is considered. Surveys of groundwater wells in the Forsmark area today show that some shallow groundwater is used to water plants, which demonstrates that small scale irrigation from such sources cannot be ruled out for present-day or warmer climate states. Complex models use more of the available site-specific information and contribute to an understanding of complex process interactions and effects of system heterogeneity. The study shows, however, that simple 'reference' biosphere models enable processes that control potential radionuclide impacts to be identified, taking into account climate variability. They help to build understanding and confidence in more complex modelling approaches, quantify the conservatisms involved and remain a valuable tool for nuclear waste disposal licensing procedures. (authors)

  13. Preliminary Post-Closure Safety Assessment and Preoperational Radiomonitoring of Anarak Near Surface Repository

    International Nuclear Information System (INIS)

    Bagheri, A.

    2016-01-01

    Conclusion: • The results of design scenario demonstrate that the effect of surface water erosion scenario is acceptable. The results suggest that doses would still be well below the typical acceptance criteria, even with cautious assumptions likely to result in over-estimates of dose in surface water erosion scenario. • (Assuming the representative person who is living near the repository, 1100 years after closure and in case of water erosion scenario the maximum total dose is less than 0.2 mSv y -1 . Furthermore, the maximum dose is caused by 241 Am that is equal to 0.15 mSv y -1 ). The activity concentration levels of the natural and artificial radionuclides were determined in the all samples collected from Anarak site and surrounding area using active and passive device. All results showed the background level of the natural and artificial radionuclides before any operation in Anarak Near Surface Disposal Facility.

  14. Deep repository for spent nuclear fuel. SR 97 - Post-closure safety. Main Report. Summary

    International Nuclear Information System (INIS)

    Hedin, A.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10 -6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere and biosphere are analyzed in the canister defect scenario. Releases from the geosphere are converted to doses in different ecosystems. The variation in flow-related data in the geosphere has the greatest impact on the result, followed by data uncertainties for the biosphere. Other conclusions are that our understanding of fuel dissolution needs to be improved, and that the probability and size of initial canister defects that escape quality-control inspection is difficult to estimate. Risk analyses in the form of simplified probabilistic calculations are also performed. The risk analyses show that all sites lie well below the acceptance criterion. The maximum risk for release to a well is never more than 0.5 percent of the acceptance criterion, even when the calculations are extended a million years into the future. The same applies to releases to peat land for times up to 100,000 years, while the maximum risk here grows to about one-tenth of the acceptance criterion at the least favourable site at times after 100,000 years. The consequences of future climate change are explored in the climate scenario. A conceivable sequence of events, including severe glaciation, on each of the three sites is sketched for the coming 150,000 years. In the climate scenario as well, the overall conclusion is that the isolating capacity of the copper canister is not threatened by either mechanical or chemical stresses. As far as the retarding capacity of the repository is concerned, for example in the event of initial canister damage, the most important changes take place in the biosphere. The repository sites are expected to be covered by ice sheets or sea during long periods, and the aggregate effect of climate change will therefore be a reduction of the dose consequences compared with a situation where the present-day climate persists. In the earthquake scenario, the consequences of earthquakes are analyzed by means of model studies where site-specific data are used for the structure of the geosphere and for earthquake statistics. The analysis method is new and includes several highly pessimistic simplifications. The analyses show that the probability of canister damage is comparable with the probability assumed for initial damage in the canister defect scenario. In the evaluation of the analysis method, it is shown how less pessimistic assumptions should lead to no canister damage at all in the model studies. The method will be refined. The scenario that deals with future inadvertent human actions that could conceivably affect the repository is surrounded by great uncertainties, chiefly because the evolution of human society is unpredictable. SR 97 discusses how conceivable societal evolutions and future human actions that affect the repository can nevertheless be categorized to some extent. In an illustrative example, a situation is analyzed where a canister in the repository is inadvertently penetrated by rock drillers. Dose and risk are calculated for the drilling personnel and for a family that settles on the site at a later time. The principal conclusion of the SR 97 safety assessment is that the prospects of building a safety deep repository for spent nuclear fuel in Swedish granitic bedrock are very good. The results of the assessment also serve as a basis for formulating requirements and preferences regarding the bedrock in site investigations, for designing a programme for site investigations, for formulating functional requirements on the repository's barriers, and for prioritization of research. The next stage in the siting of a deep repository entails investigation of the bedrock at a number of candidate sites in Sweden. It is SKBs judgement that the scope of the safety assessment and confidence in its results satisfy the requirements that should be made in preparation for such a stage

  15. 40 CFR 264.145 - Financial assurance for post-closure care.

    Science.gov (United States)

    2010-07-01

    ... days before the date on which hazardous waste is first received for disposal. The trustee must be an... made before the initial receipt of hazardous waste for disposal. A receipt from the trustee for this... least 60 days before the date on which hazardous waste is first received for disposal. The bond must be...

  16. Review. Deep repository for spent nuclear fuel SR 97 - Post-closure safety

    Energy Technology Data Exchange (ETDEWEB)

    Stephansson, Ove [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Civil and Environmental Engineering

    2000-12-01

    SKB states that the chosen scenarios provide good coverage of future evolutionary pathways for the deep repository. This is not the case. SKB has not made full use of the established interaction matrices and the new method of THMC diagrams to generate the relevant and important scenarios and to construct the important pathways of variables and processes, either in the established interaction matrices and the presented THMC diagrams. Hence, SKB is demonstrating in SR 97 that they lack a well thought through, sound and solid method to select and evaluate scenarios for the purpose of demonstrating the safety of a deep repository for spent nuclear fuel. The evolution of the system is presented for the components of the repository system (fuel, canister, buffer/backfill, geosphere) and the effects of four different scenarios, but time only enters into the system for discrete events or processes, e.g. description of the relative radiotoxicity and heat decay of the fuel, temperature distribution, iron exchange process, pH in buffer, redox capacity and radionuclear release at the three sites. There is a lack of method and way of describing the evolution of the complete repository system, including the major scenarios, as a function of time. It is essential that SKB is able to: - consider the full range of potential scenarios, - grade the scenarios according to their significance for repository design and performance and safety assessment, - consider whether simple engineering actions could be taken to inhibit the development of adverse scenarios. This cannot be done with the system presented in SR 97, and so SKB do not have a full predictive capability - which is required for the engineering design of such an important and costly structure as a repository. Geoscientific investigation material for three selected sites are presented by SKB in the technical report dealing with waste, repository design and sites. Here a general overview is missing of the geological and rock mechanical development of the respective areas and their place in space and time during the geological evolution of the Baltic Shield. This makes it difficult to rank the suggested sites based on their past, present and future geological evolution. The problem of large discrepancies in data needs to be resolved before stress measurements are performed at future sites. For stress measurements in general and the demand of good quality data at the future sites, there is a need for integrated stress analysis where data from different stress measurements methods (overcoring, hydrofracturing, hydraulic testing of pre-existing fractures and focal mechanism studies) are combined in an integrated stress analysis. Results from orientation of horizontal components from the stress measurements at the three sites clearly demonstrate the relatively large variation in orientation both at each site and between different sites. The relationship between the state of stress and the location and orientation of the major fracture zones is of outmost importance in a future location of a final repository. Preliminary repository layout was constructed by SKB for each selected repository site to accommodate approximately 4,000 canisters. From rock stability point of view the deposition tunnels should be oriented parallel with the orientation of the maximum horizontal principal stress. This is one of the fundamental principles in rock engineering. However, SKB prefer to orient the tunnel axes perpendicular to the maximum stress because the fracture zones and their respect distance, the orientation of water-bearing fracture zones and the area for repository location does not allow a proper tunnel orientation with respect to the orientation of the horizontal rock stresses. The orientation of the tunnels as suggested might lead to spalling or other types of failure of the tunnels and deposition hole. There has been a number of international studies about this problem and SKB has to give this problem additional studies to form a strategy for the future orientation of tunnels and deposition holes. In chapter 5 of the report on Waste, repository design and sites, SKB presents site-specific adaptation of the repository. In the section about repository design, there is a lack of information about the design method that will be applied for the repository. There are no references to standard literature about rock engineering design and design methods for underground constructions. There is a need for SKB to determine the design methods as this information is independent of the selection of a finale site for a repository. SKB advocates 'Design as you go' as an active approach during the process leading up to a finished repository and claims this as being important for safety. This method of constructing underground space can be applied for structures were safety demands are not particular important. (abstract truncated)

  17. 40 CFR 146.73 - Financial responsibility for post-closure care.

    Science.gov (United States)

    2010-07-01

    ...-closure by using a trust fund, surety bond, letter of credit, financial test, insurance or corporate... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Financial responsibility for post... Standards Applicable to Class I Hazardous Waste Injection Wells § 146.73 Financial responsibility for post...

  18. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2010

    International Nuclear Information System (INIS)

    2011-01-01

    This report summarizes the annual inspection, sampling, measurement, and maintenance activities performed at the Salmon, Mississippi, Site in calendar year 2010. The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County Mississippi (DOE 2007) specifies the submittal of an annual report of site activities with the results of sample analyses. The Salmon, MS, Site is a federally owned site located in Lamar County, MS, approximately 12 miles west of Purvis, MS, and about 21 miles southwest of Hattiesburg, MS (Figure 1). The U.S. Department of Energy (DOE), a successor agency to the U.S. Atomic Energy Commission (AEC), is responsible for the long-term surveillance and maintenance of the 1,470-acre site. DOE's Office of Legacy Management (LM) is the operating agent for the surface and subsurface real estate.

  19. Corrective Action Management Unit Report of Post-Closure Care Activities Calendar Year 2016.

    Energy Technology Data Exchange (ETDEWEB)

    Ziock, Robert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Little, Bonnie Colleen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-02-01

    The Corrective Action Management Unit (CAMU) at Sandia National Laboratories, New Mexico (SNL/NM) consisted of a containment cell, two treatment systems, four associated waste staging and storage areas, and support areas; all were used for management of remediation wastes between 1997 and 2003.

  20. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    None

    2012-03-01

    This report summarizes the 2011 annual inspection, sampling, measurement, and maintenance activities performed at the Salmon, Mississippi, Site (Salmon site1). The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities with the results of sample analyses. The Salmon site consists of 1,470 acres. The site is located in Lamar County, Mississippi, approximately 10 miles west of Purvis, Mississippi, and about 21 miles southwest of Hattiesburg, Mississippi.

  1. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    None

    2010-10-01

    This report summarizes the annual inspection, sampling, and maintenance activities performed on and near the Salmon, Mississippi, Site in calendar year 2009. The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities and the results of sample analyses. This report complies with the annual report requirement. The Salmon, MS, Site is located in Lamar County, MS, approximately 12 miles west of Purvis, MS, and about 21 miles southwest of Hattiesburg, MS The site encompasses 1,470 acres and is not open to the general public. The U.S. Department of Energy (DOE), a successor agency to the U.S. Atomic Energy Commission (AEC), is responsible for the long-term surveillance and maintenance of the site. The DOE Office of Legacy Management (LM) was assigned responsibility for the site effective October 1, 2006

  2. Post-Closure Inspection, Sampling, and Maintenance Report for the Salmon, Mississippi, Site Calendar Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-03-01

    This report summarizes the annual inspection, sampling, measurement, and maintenance activities performed at the Salmon, Mississippi, Site in calendar year 2010. The draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County Mississippi (DOE 2007) specifies the submittal of an annual report of site activities with the results of sample analyses. The Salmon, MS, Site is a federally owned site located in Lamar County, MS, approximately 12 miles west of Purvis, MS, and about 21 miles southwest of Hattiesburg, MS (Figure 1). The U.S. Department of Energy (DOE), a successor agency to the U.S. Atomic Energy Commission (AEC), is responsible for the long-term surveillance and maintenance of the 1,470-acre site. DOE's Office of Legacy Management (LM) is the operating agent for the surface and subsurface real estate.

  3. A Post Closure Safety Assessment for Radioactive Wastes from Advanced nuclear fuel Cycle

    International Nuclear Information System (INIS)

    Kang, Chul Hyung; Hwang, Yong Soo

    2010-01-01

    KAERI has developed the KIEP-21 (Korean, Innovative, Environmentally Friendly, and Proliferation Resistant System for the 21st Century). It is an advanced nuclear fuel cycle option with a pyro-process and a GEN-IV SFR. A pyro-process consists of two distinctive processes, an electrolytic reduction process and an electro-refining and winning process. When the pyro-process is applied, it generates five streams of wastes. To compare pyro-process advantage over the direct disposal of Spent Nuclear Fuel (SNF), the PWR SNF of the 45,000 MWD burn-up has been assumed. A safety assessment model for pyro-process wastes and representative results are presented in this report

  4. 40 CFR 265.145 - Financial assurance for post-closure care.

    Science.gov (United States)

    2010-07-01

    ... care. 265.145 Section 265.145 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... made, multiplied by an amount equivalent to 85 percent of the most recent investment rate or of the...; and (B) In connection with that procedure, no matters came to his attention which caused him to...

  5. Post-closure biosphere assessment modelling: comparison of complex and more stylised approaches.

    Science.gov (United States)

    Walke, Russell C; Kirchner, Gerald; Xu, Shulan; Dverstorp, Björn

    2015-10-01

    Geological disposal facilities are the preferred option for high-level radioactive waste, due to their potential to provide isolation from the surface environment (biosphere) on very long timescales. Assessments need to strike a balance between stylised models and more complex approaches that draw more extensively on site-specific information. This paper explores the relative merits of complex versus more stylised biosphere models in the context of a site-specific assessment. The more complex biosphere modelling approach was developed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for the Formark candidate site for a spent nuclear fuel repository in Sweden. SKB's approach is built on a landscape development model, whereby radionuclide releases to distinct hydrological basins/sub-catchments (termed 'objects') are represented as they evolve through land rise and climate change. Each of seventeen of these objects is represented with more than 80 site specific parameters, with about 22 that are time-dependent and result in over 5000 input values per object. The more stylised biosphere models developed for this study represent releases to individual ecosystems without environmental change and include the most plausible transport processes. In the context of regulatory review of the landscape modelling approach adopted in the SR-Site assessment in Sweden, the more stylised representation has helped to build understanding in the more complex modelling approaches by providing bounding results, checking the reasonableness of the more complex modelling, highlighting uncertainties introduced through conceptual assumptions and helping to quantify the conservatisms involved. The more stylised biosphere models are also shown capable of reproducing the results of more complex approaches. A major recommendation is that biosphere assessments need to justify the degree of complexity in modelling approaches as well as simplifying and conservative assumptions. In light of the uncertainties concerning the biosphere on very long timescales, stylised biosphere models are shown to provide a useful point of reference in themselves and remain a valuable tool for nuclear waste disposal licencing procedures. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. Review comments on the SR 97 post-closure safety assessment

    International Nuclear Information System (INIS)

    Geier, J.

    2000-01-01

    These review comments concern an assessment of the long-term safety of a deep repository for spent nuclear fuel, titled Safety Report 97 (SR 97), which was prepared by the Swedish Nuclear Fuel Waste Management Company (SKB). The primary focus of this review is on hydrogeologic issues relating to groundwater flow, hydrologic uncertainty, and the potential for radionuclide transport from leaking canisters. The main hydrological model that was used in SR 97 is based on a continuum conceptual model of groundwater flow in fractured bedrock. Major problems with this model include the following: The validity of the continuum model is arguable for the type of rock that is present at these sites. The suitability of the model for the intended purpose of predicting streamlines and travel times for groundwater flow through the rock mass has not been adequately demonstrated. The comparison with alternative, discrete models yielded more divergent results than has been recognized in the SR 97 reports. The comparison with alternative models did not consider significant, realistic sources of uncertainty in the alternative models, evaluation of which would have likely led to greater divergence. The SR 97 model of radionuclide transport is based on a 1-D streamtube formulation, within which the predicted release of radionuclides to the biosphere is dominated by a parameter called the F ratio. A key factor in this parameter is the flow wetted surface. All of the hydrologic models used in SR 97 relied upon essentially the same set of geometric assumptions to estimate flow wetted surface from conductive fracture frequency in boreholes. Hence the predictions of the alternative models are not independent. Alternative methods of estimating flow wetted surface are needed to obtain a realistic evaluation of the uncertainty regarding radionuclide release. The alternative 3-D hydrologic models were used only to predict streamtube parameters, not for actual transport simulations. Hence the comparison between the main hydrologic conceptual model and alternative models does not include a full assessment of the effects of flow field complexity on radionuclide transport. As this is one of the major distinctions between the continuum model and the alternative models, the comparison must be regarded as incomplete. Besides these major hydrological issues, miscellaneous comments are offered on aspects of the repository system design and site descriptions that relate to hydrology

  7. On the estimation of bias in post-closure performance assessment of underground radioactive waste disposal

    International Nuclear Information System (INIS)

    Thompson, B.G.J.; Gralewski, Z.A.; Grindrod, P.

    1995-01-01

    This paper proposes a systematic method for recording and evaluating bias in performance assessments for underground radioactive waste disposal facilities. The bias estimation approach comprises three principal components: (1) creation of a relational database containing historical assumptions and decisions made during the assessment, (2) investigation of the impact of some identified sources of internal bias through alternative assessment calculations, and (3) investigation of the impact of some identified sources of external bias by estimating degrees of belief probability. Bias corrections may help avoid unnecessary concerns by explaining and scoping the impacts of principal differences without the need to undertake additional site investigation, research, and performance analysis

  8. Radiation monitoring

    International Nuclear Information System (INIS)

    Larsson, L.Eh.; B'yuli, D.K.; Karmikel, Dzh.Kh.E.

    1985-01-01

    Recommendations on radiation monitoring of personnel, used medical ionizing radiation source, are given. The necessity to carry out radiation monitoring of situation at medical personnel's positions and personnel dosimetry is marked. It is convenient to subdivide radiation monitoring into 3 types: usual, surgical and special. Usual monitoring is connected with current work; surgical monitoring is carried out to receive information during a concrete operation; special monitoring is used to detect possible deviation from standard conditions of work or when suspecting them

  9. Resource Conservation and Recovery Act closure report: Area 2, Bitcutter and Postshot Containment Shops

    International Nuclear Information System (INIS)

    Petrello, Jaclyn

    1996-01-01

    Post-closure monitoring requirements for CASs 02-20-01 (Bitcutter/Ps Inj.) and Wells (3) (RCRA) and CAS 02-20-03 (Wastewater Pit) are managed through the RCRA permit, which is renewed every 5 years. Post-closure monitoring requirements are described in that permit.

  10. Resource Conservation and Recovery Act closure report: Area 2, Bitcutter and Postshot Containment Shops

    Energy Technology Data Exchange (ETDEWEB)

    Petrello, Jaclyn [Nevada Field Office, Las Vegas, NV (United States)

    1996-12-01

    Post-closure monitoring requirements for CASs 02-20-01 (Bitcutter/Ps Inj.) and Wells (3) (RCRA) and CAS 02-20-03 (Wastewater Pit) are managed through the RCRA permit, which is renewed every 5 years. Post-closure monitoring requirements are described in that permit.

  11. Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels: FY2017

    Energy Technology Data Exchange (ETDEWEB)

    Mizell, Steve A. [Desert Research Inst. (DRI), Las Vegas, NV (United States); Campbell, Scott A. [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J. [Desert Research Inst. (DRI), Las Vegas, NV (United States)

    2018-04-01

    The Desert Research Institute (DRI) is conducting a field assessment of the potential for contaminated soil to be transported from the Smoky Site Contamination Area (CA) as a result of storm runoff. This activity supports U.S. Department of Energy (DOE) Environmental Management Nevada Program (EM-NV) efforts to establish post-closure monitoring plans for the Smoky Site Soils Corrective Action Unit (CAU) 550. The work is intended to confirm the likely mechanism of transport and determine the meteorological conditions that might cause the movement of contaminated soils, as well as determine the particle size fraction that is most closely associated with transported radionuclide-contaminated soils. These data will facilitate the design of the appropriate post-closure monitoring program. In 2011, DRI installed a meteorological monitoring station on the west side of the Smoky Site CA and a hydrologic (runoff) monitoring station within the CA, near the east side. Air temperature, wind speed, wind direction, relative humidity, precipitation, solar radiation, barometric pressure, soil temperature, and soil water content are collected at the meteorological station. The maximum, minimum, and average or total values (as appropriate) for each of these parameters are recorded for each 10-minute interval. The maximum, minimum, and average water depth in the flume installed at the hydrology station are also recorded for every 10-minute interval. This report presents data collected from these stations during fiscal year (FY) 2017. During the FY2017 reporting period, the warmest months were June, July, and August and the coldest were December and January. Solar radiation showed the same seasonal trend, although the months with the most solar radiation were May and June. Monthly mean wind speeds were highest in the spring (April and May). Winds were generally from the southwest during the summer and from the northwest throughout the remainder of the year. The monthly average

  12. Groundwater monitoring for remedial investigation in the Oriskany-Whitestown Sand Plain, Oneida County, New York

    International Nuclear Information System (INIS)

    Kewer, R.P.; Birckhead, E.F.

    1992-01-01

    The 50-acre Whitestown Landfill is listed by NYSDEC as a Class 2 inactive hazardous waste disposal site. During Remedial Investigations, a 23-well groundwater monitoring system was installed, exploring Wisconsin age glaciofluvial deposits of the Oriskany-Whitestown sand plain. These were described in the late 19th century as deltaic sediments deposited in a proglacial lake. However, no recent studies and only limited subsurface data were available, prompting a two-phase installation program. The landfill is located above steep bluffs 70 feet above the Mohawk River and Oriskany Creek valleys. Beneath the landfill, Phase I identified a gradational sequence of coarse to fine deltaic sediments with glacial till. This sequence was partly eroded and overlain by alluvium and colluvium in the valleys. The landfill was constructed on surficial deposits of coarse fluviodeltaic gravel. These were underlain by deltaic deposits grading from sand to silt with depth, the lower silts comprising the uppermost aquifer. The silts made identification of the water table difficult during drilling and caused problems in meeting a stringent development criterion for turbidity. Phase I found that the saturated zone, up to 50 feet thick, is perched on glaciolacustrine clays and, locally, tills, which were the lower boundary of the system investigated. Partly influenced by the clays, groundwater and contaminant movement was to the adjoining valley, causing off-site impacts in the shallow alluvial/colluvial aquifer. Therefore, Phase 11 focused on characterizing flow and groundwater quality in the discharge area, particularly with respect to an adjacent residence and wetlands. Contamination was found to extend northward only as far as the Old Erie Canal, which parallels the base of the bluff. Only limited off-site involvement was documented which will be monitored in the post-closure period using the installed well system

  13. F-Area Seepage Basins groundwater monitoring report -- third and fourth quarters 1993

    International Nuclear Information System (INIS)

    Butler, C.T.

    1994-03-01

    During the second half of 1993, the groundwater at the F-Area Seepage Basins (FASB) was monitored in compliance with Module 3, Section C, of South Carolina Hazardous Waste Permit SC1-890-008-989, effective November 2, 1992. The monitoring well network is composed of 87 FSB wells screened in the three hydrostratigraphic units that make up the uppermost aquifer beneath the FASB. A detailed description of the uppermost aquifer is included in the Resource Conservation and Recovery Act Part B post-closure care permit application for the F-Area Hazardous Waste Management Facility submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in December 1990. Beginning in the first quarter of 1993, the standard for comparison became the SCDHEC Groundwater Protection Standard (GWPS) specified in the approved F-Area Seepage Basins Part B permit. Currently and historically, gross alpha, nitrate, nonvolatile beta, and tritium are among the primary constituents to exceed standards. Numerous other radionuclides and hazardous constituents also exceeded the GWPS in the groundwater at the FASB during the second half of 1993, notably aluminum, iodine-129, and zinc. The elevated constituents are found primarily in Aquifer Zone 2B 2 and Aquifer Zone 2B 1 wells. However, several Aquifer Unit 2A wells also contain elevated levels of constituents. Isoconcentration/isoactivity maps included in this report indicate both the concentration/activity and extent of the primary contaminants in each of the three hydrostratigraphic units. Water-level maps indicate that the groundwater flow rates and directions at the FASB have remained relatively constant since the basins ceased to be active in 1988

  14. Personnel monitoring

    International Nuclear Information System (INIS)

    1965-01-01

    This film stresses the need for personnel monitoring in work areas where there is a hazard of exposure to radiation. It illustrates the use of personnel monitoring devices (specially the film dosimeter), the assessment of exposure to radiation and the detailed recording of the results on personnel filing cards

  15. Mobility Monitor

    DEFF Research Database (Denmark)

    Schæbel, Anne-Lise; Dybbro, Karina Løvendahl; Andersen, Lisbeth Støvring

    2015-01-01

    Undersøgelse af digital monitorering af plejehjemsbeboeres vendinger under søvn på Fremtidens Plejehjem, Nørresundby......Undersøgelse af digital monitorering af plejehjemsbeboeres vendinger under søvn på Fremtidens Plejehjem, Nørresundby...

  16. Personnel monitoring

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-12-31

    This film stresses the need for personnel monitoring in work areas where there is a hazard of exposure to radiation. It illustrates the use of personnel monitoring devices (specially the film dosimeter), the assessment of exposure to radiation and the detailed recording of the results on personnel filing cards

  17. Process monitoring

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Many of the measurements and observations made in a nuclear processing facility to monitor processes and product quality can also be used to monitor the location and movements of nuclear materials. In this session information is presented on how to use process monitoring data to enhance nuclear material control and accounting (MC and A). It will be seen that SNM losses can generally be detected with greater sensitivity and timeliness and point of loss localized more closely than by conventional MC and A systems if process monitoring data are applied. The purpose of this session is to enable the participants to: (1) identify process unit operations that could improve control units for monitoring SNM losses; (2) choose key measurement points and formulate a loss indicator for each control unit; and (3) describe how the sensitivities and timeliness of loss detection could be determined for each loss indicator

  18. H-Area Seepage Basins groundwater monitoring report -- third and fourth quarters 1993. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Butler, C.T.

    1994-03-01

    During the second half of 1993, the groundwater at the H-Area Seepage Basins (HASB) was monitored in compliance with the September 30, 1992, modification of South Carolina Hazardous Waste Permit SC1-890-008-989. A detailed description of the uppermost aquifer is included in the Resource Conservation and Recovery Act Part B post-closure care permit application for the H-Area Hazardous Waste Management Facility submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in December 1990. Beginning first quarter 1993, the HASB`s Groundwater Protection Standard (GWPS), established in Appendix 3D-A of the cited permit, became the standard for comparison. Historically as well as currently, nitrate, nonvolatile beta, and tritium have been among the primary constituents to exceed standards. Other radionuclides and hazardous constitutents also exceeded the GWPS in the groundwater at the HASB (notably aluminum, iodine-129, strontium-90, technetium-99, and zinc) during the second half of 1993. Elevated constituents were found primarily in Aquifer Zone 2B{sub 2} and in the upper portion of Aquifer Zone 2B{sub 1}. However, constituents exceeding standards also occurred in several wells screened in the lower portion of Aquifer Zone 2B{sub 1} and Aquifer Unit 2A. Isoconcentration/isoactivity maps include in this report indicate both the concentration/activity and extent of the primary contaminants in each of the three hydrostratigraphic units during the second half of 1993. Water-level maps indicate that the groundwater flow rates and directions at the HASB have remained relatively constant since the basins ceased to be active in 1988.

  19. H-Area Seepage Basins groundwater monitoring report -- third and fourth quarters 1993

    International Nuclear Information System (INIS)

    Butler, C.T.

    1994-03-01

    During the second half of 1993, the groundwater at the H-Area Seepage Basins (HASB) was monitored in compliance with the September 30, 1992, modification of South Carolina Hazardous Waste Permit SC1-890-008-989. A detailed description of the uppermost aquifer is included in the Resource Conservation and Recovery Act Part B post-closure care permit application for the H-Area Hazardous Waste Management Facility submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in December 1990. Beginning first quarter 1993, the HASB's Groundwater Protection Standard (GWPS), established in Appendix 3D-A of the cited permit, became the standard for comparison. Historically as well as currently, nitrate, nonvolatile beta, and tritium have been among the primary constituents to exceed standards. Other radionuclides and hazardous constitutents also exceeded the GWPS in the groundwater at the HASB (notably aluminum, iodine-129, strontium-90, technetium-99, and zinc) during the second half of 1993. Elevated constituents were found primarily in Aquifer Zone 2B 2 and in the upper portion of Aquifer Zone 2B 1 . However, constituents exceeding standards also occurred in several wells screened in the lower portion of Aquifer Zone 2B 1 and Aquifer Unit 2A. Isoconcentration/isoactivity maps include in this report indicate both the concentration/activity and extent of the primary contaminants in each of the three hydrostratigraphic units during the second half of 1993. Water-level maps indicate that the groundwater flow rates and directions at the HASB have remained relatively constant since the basins ceased to be active in 1988

  20. Monitoring Hadoop

    CERN Document Server

    Singh, Gurmukh

    2015-01-01

    This book is useful for Hadoop administrators who need to learn how to monitor and diagnose their clusters. Also, the book will prove useful for new users of the technology, as the language used is simple and easy to grasp.

  1. Treaty Monitoring

    DEFF Research Database (Denmark)

    Canty, M.; Jasani, B.; Lingenfelder, I.

    2009-01-01

    of remote sensing technologies. The book therefore comprises management aspects (issues and priorities of security research, crisis response), applied methodologies and process chains (treaty monitoring, estimation of population densities and characteristics, border permeability models, damage assessment...... companies, national research institutions and international organizations, all of whom were brought together under the aegis of the European research project GMOSS (Global Monitoring for Security and Stability). This book is tailored for the scientific community that deals with the application of EO data...... of civil security. Written for: Scientists, researchers in spatial sciences as well as practitioners, politicians, decision makers at NGO's in the field of security, crisis management, risk assessment and vulnerability....

  2. Monitoring apparatus

    International Nuclear Information System (INIS)

    Keats, A.B.

    1981-01-01

    An improved monitoring apparatus for use with process plants, such as nuclear reactors, is described. System failure in the acquisition of data from the plant, owing to stuck signals, is avoided by arranging input signals from transducers in the plant in a test pattern. (U.K.)

  3. Monitor 1979

    International Nuclear Information System (INIS)

    Grisham, D.L.; Ekberg, E.L.; Lambert, J.E.; Meyer, R.E.; Stroik, P.J.; Wickham, M.D.

    1979-01-01

    The status, improvements, and accomplishments of the Monitor remote-handling system previously reported are updated. It also outlines the goals for the future to improve the efficiency and speed of remote-maintenance operations at the Clinton P. Anderson Meson Physics Facility

  4. Monitoring programme

    International Nuclear Information System (INIS)

    1994-06-01

    Her Majesty's Inspectorate of Pollution's 1992 report on its programme of monitoring radioactive substances is presented. Site operators' returns are verified and the report provides independent data on the environmental impact of authorized disposal of radioactive wastes. Radiation doses which may have been received by members of the public, fall well below the International Commission for Radiological Protection's (ICRP) recommended annual doses. (UK)

  5. Energy Monitoring

    DEFF Research Database (Denmark)

    Hansen, Claus T.; Madsen, Dines; Christiensen, Thomas

    Energy measurement has become an important aspect of our daily lives since we have learned that energy consumption, is one of the main source of global warming. Measuring instruments varies from a simple watt-meter to more sophisticated microprocessor control devices. The negative effects...... that fossil fuels induce on our environment has forced us to research renewable energy such as sunlight, wind etc. This new environmental awareness has also helped us to realize the importance of monitoring and controlling our energy use. The main purpose in this research is to introduce a more sophisticated...... but affordable way to monitor energy consumption of individuals or groups of home appliances. By knowing their consumption the utilization can be regulated for more efficient use. A prototype system has been constructed to demonstrate our idea....

  6. Personal monitoring

    International Nuclear Information System (INIS)

    1995-01-01

    Sources of ionizing radiation have innumerable applications in the workplace. The potential exposures of the individual workers involved may need to be routinely monitored and records kept of their cumulative radiation doses. There are also occasions when it is necessary to retrospectively determine a dose which may have been received by a worker. This Module explains the basic terminology associated with personal monitoring and describes the principal types of dosimeters and other related techniques and their application in the workplace. The Manual will be of most benefit if it forms part of more comprehensive training or is supplemented by the advice of a qualified expert in radiation protection. Most of the dosimeters and techniques described in this Module can only be provided by qualified experts

  7. Sewage Monitors

    Science.gov (United States)

    1987-01-01

    Every U.S. municipality must determine how much waste water it is processing and more importantly, how much is going unprocessed into lakes and streams either because of leaks in the sewer system or because the city's sewage facilities were getting more sewer flow than they were designed to handle. ADS Environmental Services, Inc.'s development of the Quadrascan Flow Monitoring System met the need for an accurate method of data collection. The system consists of a series of monitoring sensors and microcomputers that continually measure water depth at particular sewer locations and report their findings to a central computer. This provides precise information to city managers on overall flow, flow in any section of the city, location and severity of leaks and warnings of potential overload. The core technology has been expanded upon in terms of both technical improvements, and functionality for new applications, including event alarming and control for critical collection system management problems.

  8. Material monitoring

    International Nuclear Information System (INIS)

    Kotter, W.; Zirker, L.; Hancock, J.A.

    1995-01-01

    Waste Reduction Operations Complex (WROC) facilities are located at the Idaho National Engineering Laboratory (INEL). The overall goal for the Pollution Prevention/Waste Minimization Unit is to identify and establish the correct amount of waste generated so that it can be reduced. Quarterly, the INEL Pollution Prevention (P2) Unit compares the projected amount of waste generated per process with the actual amount generated. Examples of waste streams that would be addresses for our facility would include be are not limited to: Maintenance, Upgrades, Office and Scrap Metal. There are three potential sources of this variance: inaccurate identification of those who generate the waste; inaccurate identification of the process that generates the waste; and inaccurate measurement of the actual amount generated. The Materials Monitoring Program was proposed to identify the sources of variance and reduce the variance to an acceptable level. Prior to the implementation of the Material Monitoring Program, all information that was gathered and recorded was done so through an informal estimation of waste generated by various personnel concerned with each processes. Due to the inaccuracy of the prior information gathering system, the Material Monitoring Program was established. The heart of this program consists of two main parts. In the first part potential waste generators provide information on projected waste generation process. In the second part, Maintenance, Office, Scrap Metal and Facility Upgrade wastes from given processes is disposed within the appropriate bin dedicated to that process. The Material Monitoring Program allows for the more accurate gathering of information on the various waste types that are being generated quarterly

  9. Individual monitoring

    International Nuclear Information System (INIS)

    2004-01-01

    This Practical Radiation Technical Manual is one of a series which has been designed to provide guidance on radiological protection for employers, Radiation Protection Officers, managers and other technically competent persons who have a responsibility to ensure the safety of employees working with ionizing radiation. The Manual may be used together with the appropriate IAEA Practical Radiation Safety Manual to provide adequate training, instruction or information on individual monitoring for all employees engaged in work with ionizing radiations. Sources of ionizing radiation have a large number of applications in the workplace. The exposures of the individual workers involved may need to be routinely monitored and records kept of their cumulative radiation doses. There are also occasions when it is necessary to retrospectively determine a dose which may have been received by a worker. This Manual explains the basic terminology associated with individual monitoring and describes the principal types of dosimeters and other related techniques and their application in the workplace. The Manual will be of most benefit if it forms part of more comprehensive training or is supplemented by the advice of a qualified expert in radiation protection. Most of the dosimeters and techniques described in this Manual can only be provided by qualified experts

  10. Review of computer models used for post closure safety assessment of nuclear waste repositories in the FRG

    International Nuclear Information System (INIS)

    Bogorinski, P.; Baltes, B.; Martens, K.H.

    1987-01-01

    In the FRG, disposal of nuclear wastes takes place in deep geologic formations. For longterm safety assessment of such a repository, groundwater transport provides a release scenario for the radionuclides to the biosphere. GRs reviewed a methodology that was implemented by the research group of PSE to simulate migration of radionuclides in the geosphere. The examination included the applicability of theoretical models, numerical experiments, comparison to results of diverse computer codes as well as experience from international intercomparison studies. The review concluded that the hydrological model may be applied to full extent unless density effects have to be considered whereas there are some restrictions in the use of the nuclide transport model

  11. Feasibility of the use of optimisation techniques to calibrate the models used in a post-closure radiological assessment

    International Nuclear Information System (INIS)

    Laundy, R.S.

    1991-01-01

    This report addresses the feasibility of the use of optimisation techniques to calibrate the models developed for the impact assessment of a radioactive waste repository. The maximum likelihood method for improving parameter estimates is considered in detail, and non-linear optimisation techniques for finding solutions are reviewed. Applications are described for the calibration of groundwater flow, radionuclide transport and biosphere models. (author)

  12. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere and biosphere are analyzed in the canister defect scenario. Releases from the geosphere are converted to doses in different ecosystems. The variation in flow-related data in the geosphere has the greatest impact on the result, followed by data uncertainties for the biosphere. Other conclusions are that our understanding of fuel dissolution needs to be improved, and that the probability and size of initial canister defects that escape quality-control inspection is difficult to estimate. Risk analyses in the form of simplified probabilistic calculations are also performed. The risk analyses show that all sites lie well below the acceptance criterion. The maximum risk for release to a well is never more than 0.5 percent of the acceptance criterion, even when the calculations are extended a million years into the future. The same applies to releases to peat land for times up to 100,000 years, while the maximum risk here grows to about one-tenth of the acceptance criterion at the least favourable site at times after 100,000 years. The consequences of future climate change are explored in the climate scenario. A conceivable sequence of events, including severe glaciation, on each of the three sites is sketched for the coming 150,000 years. In the climate scenario as well, the overall conclusion is that the isolating capacity of the copper canister is not threatened by either mechanical or chemical stresses. As far as the retarding capacity of the repository is concerned, for example in the event of initial canister damage, the most important changes take place in the biosphere. The repository sites are expected to be covered by ice sheets or sea during long periods, and the aggregate effect of climate change will therefore be a reduction of the dose consequences compared with a situation where the present-day climate persists. In the earthquake scenario, the consequences of earthquakes are analyzed by means of model studies where site-specific data are used for the structure of the geosphere and for earthquake statistics. The analysis method is new and includes several highly pessimistic simplifications. The analyses show that the probability of canister damage is comparable with the probability assumed for initial damage in the canister defect scenario. In the evaluation of the analysis method, it is shown how less pessimistic assumptions should lead to no canister damage at all in the model studies. The method will be refined. The scenario that deals with future inadvertent human actions that could conceivably affect the repository is surrounded by great uncertainties, chiefly because the evolution of human society is unpredictable. SR 97 discusses how conceivable societal evolutions and future human actions that affect the repository can nevertheless be categorized to some extent.

  13. Validation of the vault computer model 'VERMIN' for post-closure behaviour of repositories in geological formations

    International Nuclear Information System (INIS)

    Laurens, J.-M.

    1987-10-01

    A validation methodology is proposed and applied to the computer model VERMIN, which is used to simulate radionuclide release from repositories for solid radioactive wastes. The processes included in the validation exercise are leaching from the waste matrix, diffusive transport and advective transport combined with sorption. Suggestions are made for new experimental studies relevant to VERMIN validation. In addition, VERMIN was used to simulate the behaviour of a repository in a clay formation and thus provide input for the geosphere model being used in the PACOMA study. Results from these simulations are reported. (author)

  14. Foundations, trusts and funds in near mine closure and post-closure environments: a case from Bolivia

    DEFF Research Database (Denmark)

    Pacheco Cueva, Vladimir

    2012-01-01

    and when management of the FTF requires considerable input from the community it was meant to serve. This paper provides baseline results from research undertaken on the Inti Raymi Foundation in Bolivia. It analyses the community engagement practices and the programs used by both the foundation and its...

  15. Assessment of post closure radioactive safety for the Korean reference disposal system: development of scenarios and quantitative assessment

    International Nuclear Information System (INIS)

    Kang, C. H.; Hwang, Y. S.; Lee, Y. M.

    2005-01-01

    The total system performance assessment (TSPA) on the Korean reference disposal system has been performed for different types of scenarios. Firstly two reference scenarios, the natural discharge and well ones are developed assessed. The natural discharge scenario assumes that a radionuclide is released from a waste container with an average lifetime of 1,000 years by intruding groundwater to a biosphere through a bentonite buffer and a natural barrier composed of a fractured porous rock and a major water conducting feature (MWCF). The well scenario describes that a radionuclide passing through a buffer enters a fractured rock which is intersected with a drinking well. Two scenarios are named as R1 and R2 respectively. The third scenario is for the initial waste container failure case. A waste container is apt to have initial defects during manufacturing and transportation to a deposition hole. The probability function of the ratio of waste container failure is assumed based on the engineering sense. The rest of waste containers are assumed to have full function of isolation of hazardous nuclides during the lifetime. This initial container failure scenario (ICF) has two different variations: one with a lifetime of 1,000 years ana the other with 10,000 years. Two variations are assessed for two different biosphere, natural discharge and well. The forth one is to assess the impact of excavation disturbed zones. Deposition tunnels are excavated by tunnel boring machine (TBM) or controlled blast (CB). The disturbed zone in assumed to be 30 cm and 1 meter for TBN and CB respectively. Six cases are developed for the EDZ scenarios considering all possible combination of changes in permeability a fracture aperture, and a porosity of a fractured rock. The fifth scenario stipulates the change of long term climate (LTC). The ice age assumed to be prevailed again after a few tens of thousand years. The advent of the ice age alters groundwater composition, pathways, and most importantly the nature of human life. Two cases are developed for the ice age scenario. The first one is the case that the groundwater pathway is shortened. This is feasible when a new shorter pathway is evolved between a repository and surface. Also it is possible when a future resident drills a deeper borehole to extract drinking water into a fractured rock adjacent to a repository. Even though groundwater is released into a ground surface, the pattern in usage of water will be significantly changed. To accommodate it, the dose conversion factors in the current boreal climate are used to assess the annual individual dose. The next scenario is still under development. It aims to deal with the case with a fault reactivation (FR) near a repository. Reactivation is assumed to reactivate and eventually widen an existing joint and its properties so that the groundwater flow speed and/or pathways will be altered. The TSPA 2006 by KAERI is to assess these two reference and four alternative scenarios with many sub-cases and parameter uncertainties for given Korean geological data set

  16. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere and biosphere are analyzed in the canister defect scenario. Releases from the geosphere are converted to doses in different ecosystems. The variation in flow-related data in the geosphere has the greatest impact on the result, followed by data uncertainties for the biosphere. Other conclusions are that our understanding of fuel dissolution needs to be improved, and that the probability and size of initial canister defects that escape quality-control inspection is difficult to estimate. Risk analyses in the form of simplified probabilistic calculations are also performed. The risk analyses show that all sites lie well below the acceptance criterion. The maximum risk for release to a well is never more than 0.5 percent of the acceptance criterion, even when the calculations are extended a million years into the future. The same applies to releases to peat land for times up to 100,000 years, while the maximum risk here grows to about one-tenth of the acceptance criterion at the least favourable site at times after 100,000 years. The consequences of future climate change are explored in the climate scenario. A conceivable sequence of events, including severe glaciation, on each of the three sites is sketched for the coming 150,000 years. In the climate scenario as well, the overall conclusion is that the isolating capacity of the copper canister is not threatened by either mechanical or chemical stresses. As far as the retarding capacity of the repository is concerned, for example in the event of initial canister damage, the most important changes take place in the biosphere. The repository sites are expected to be covered by ice sheets or sea during long periods, and the aggregate effect of climate change will therefore be a reduction of the dose consequences compared with a situation where the present-day climate persists. In the earthquake scenario, the consequences of earthquakes are analyzed by means of model studies where site-specific data are used for the structure of the geosphere and for earthquake statistics. The analysis method is new and includes several highly pessimistic simplifications. The analyses show that the probability of canister damage is comparable with the probability assumed for initial damage in the canister defect scenario. In the evaluation of the analysis method, it is shown how less pessimistic assumptions should lead to no canister damage at all in the model studies. The method will be refined. The scenario that deals with future inadvertent human actions that could conceivably affect the repository is surrounded by great uncertainties, chiefly because the evolution of human society is unpredictable. SR 97 discusses how conceivable societal evolutions and future human actions that affect the repository can nevertheless be categorized to some extent.

  17. Generic Post-closure Safety Assessment for Disposal of Disused Sealed Radioactive Sources in Narrow Diameter Boreholes

    International Nuclear Information System (INIS)

    2017-10-01

    This publication, prepared in light of the IAEA Action Plan on Nuclear Safety developed after the accident at the Fukushima Daiichi nuclear power plant, addresses the management of large volumes of radioactive waste arising in a nuclear or radiological emergency, as part of overall emergency preparedness. The management of large volumes of waste will be one of many efforts to be dealt with to allow recovery of affected areas, to support return of evacuated or relocated populations and preparations for normal social and economic activities, and/or to mitigate additional environmental impacts. The publication is intended to be of use to national planners and policy makers, facility and programme managers, and other professionals responsible for developing and implementing national plans and strategies to manage radioactive waste arising from nuclear or radiological emergencies.

  18. 40 CFR 264.146 - Use of a mechanism for financial assurance of both closure and post-closure care.

    Science.gov (United States)

    2010-07-01

    ... facilities by using a trust fund, surety bond, letter of credit, insurance, financial test, or corporate... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Use of a mechanism for financial... HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Financial Requirements § 264.146 Use of a...

  19. Natural analogue of redox front formation in near-field environment at post-closure phase of HLW geological disposal

    International Nuclear Information System (INIS)

    Yoshida, Hidekazu; Yamamoto, Koushi; Amano, Yuki

    2005-01-01

    Redox fronts are created in the near field of rocks, in a range of oxidation environments, by microbial activity in rock groundwater. Such fronts, and the associated oxide formation, are usually unavoidable around high level radioactive waste (HLW) repositories, whatever their design. The long term behaviour of these oxides after repositories have been closed is however little known. Here we introduce an analogue of redox front formation, such as 'iron oxide' deposits, known as takashikozo forming cylindrical nodules, and the long term behaviour of secondarily formed iron oxyhydroxide in subsequent geological environments. (author)

  20. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    International Nuclear Information System (INIS)

    Hedin, A.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10 -6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere and biosphere are analyzed in the canister defect scenario. Releases from the geosphere are converted to doses in different ecosystems. The variation in flow-related data in the geosphere has the greatest impact on the result, followed by data uncertainties for the biosphere. Other conclusions are that our understanding of fuel dissolution needs to be improved, and that the probability and size of initial canister defects that escape quality-control inspection is difficult to estimate. Risk analyses in the form of simplified probabilistic calculations are also performed. The risk analyses show that all sites lie well below the acceptance criterion. The maximum risk for release to a well is never more than 0.5 percent of the acceptance criterion, even when the calculations are extended a million years into the future. The same applies to releases to peat land for times up to 100,000 years, while the maximum risk here grows to about one-tenth of the acceptance criterion at the least favourable site at times after 100,000 years. The consequences of future climate change are explored in the climate scenario. A conceivable sequence of events, including severe glaciation, on each of the three sites is sketched for the coming 150,000 years. In the climate scenario as well, the overall conclusion is that the isolating capacity of the copper canister is not threatened by either mechanical or chemical stresses. As far as the retarding capacity of the repository is concerned, for example in the event of initial canister damage, the most important changes take place in the biosphere. The repository sites are expected to be covered by ice sheets or sea during long periods, and the aggregate effect of climate change will therefore be a reduction of the dose consequences compared with a situation where the present-day climate persists. In the earthquake scenario, the consequences of earthquakes are analyzed by means of model studies where site-specific data are used for the structure of the geosphere and for earthquake statistics. The analysis method is new and includes several highly pessimistic simplifications. The analyses show that the probability of canister damage is comparable with the probability assumed for initial damage in the canister defect scenario. In the evaluation of the analysis method, it is shown how less pessimistic assumptions should lead to no canister damage at all in the model studies. The method will be refined. The scenario that deals with future inadvertent human actions that could conceivably affect the repository is surrounded by great uncertainties, chiefly because the evolution of human society is unpredictable. SR 97 discusses how conceivable societal evolutions and future human actions that affect the repository can nevertheless be categorized to some extent. In an illustrative example, a situation is analyzed where a canister in the repository is inadvertently penetrated by rock drillers. Dose and risk are calculated for the drilling personnel and for a family that settles on the site at a later time. The principal conclusion of the SR 97 safety assessment is that the prospects of building a safety deep repository for spent nuclear fuel in Swedish granitic bedrock are very good. The results of the assessment also serve as a basis for formulating requirements and preferences regarding the bedrock in site investigations, for designing a programme for site investigations, for formulating functional requirements on the repository's barriers, and for prioritization of research. The next stage in the siting of a deep repository entails investigation of the bedrock at a number of candidate sites in Sweden. It is SKBs judgement that the scope of the safety assessment and confidence in its results satisfy the requirements that should be made in preparation for such a stage

  1. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

  2. Demonstrating compliance with protection objectives for non-human biota within post-closure safety cases for radioactive waste repositories.

    Science.gov (United States)

    Jackson, D; Smith, K; Wood, M D

    2014-07-01

    Over recent years, a number of approaches have been developed that enable the calculation of dose rates to animals and plants following the release of radioactivity to the environment. These approaches can be used to assess the potential impacts of activities that may release radioactivity to the environment, such as the operation of waste repositories. A number of national and international studies have identified screening criteria to indicate those assessment results below which further consideration is not generally required. However no internationally agreed criteria are currently available and consistency in criteria between countries has not been achieved. Furthermore, since screening criteria are not intended to be applied as limits, it is clear that they cannot always form a sufficient basis for assessing the adequacy of protection afforded. Typically, exceeding a screening value leads to a regulatory requirement to undertake a further, more detailed assessment. It does not, per se, imply that there is inadequate protection of the organism types at the specific site under assessment. Therefore, there is a need to develop a more structured approach to dealing with situations in which current screening criteria are exceeded. As a contribution to the developing international discussions, and as an interim measure for application where assessments are required currently, a two-tier, three zone framework is proposed here, relevant to the long term assessment of potential impacts from the deep disposal of radioactive wastes. The purpose of the proposed framework is to promote a proportionate and risk-based approach to the level of effort required in undertaking and interpreting an assessment. Copyright © 2013. Published by Elsevier Ltd.

  3. SR 97: Post-closure safety for a KBS 3 type deep repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Hedin, A.; Kautsky, U.

    2000-03-01

    Prior to coming site investigations for siting of a deep repository for spent nuclear fuel, SKB has carried out the long-term safety assessment SR 97, requested by the Swedish Government. The repository is of the KBS-3 type, where the fuel is placed in isolating copper canisters with a high-strength cast iron insert. The canisters are surrounded by bentonite clay in individual deposition holes at a depth of 500 m in granitic bedrock. The future evolution of the repository system is analysed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings, including climate, persist. The four other scenarios show the evolution if the repository contains a few initially defective canisters, in the event of climate change, in the event of earthquakes, and in the event of future inadvertent human intrusion. The principal conclusion of the assessment is that the prospects of building a safe deep repository for spent nuclear fuel in Swedish granitic bedrock are very good. (author)

  4. Technology monitoring; Technologie-Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Eicher, H.; Rigassi, R. [Eicher und Pauli AG, Liestal (Switzerland); Ott, W. [Econcept AG, Zuerich (Switzerland)

    2003-07-01

    This study made for the Swiss Federal Office of Energy (SFOE) examines ways of systematically monitoring energy technology development and the cost of such technologies in order to pave the way to a basis for judging the economic development of new energy technologies. Initial results of a survey of the past development of these technologies are presented and estimates are made of future developments in the areas of motor-based combined heat and power systems, fuel-cell heating units for single-family homes and apartment buildings, air/water heat pumps for new housing projects and high-performance thermal insulation. The methodology used for the monitoring and analysis of the various technologies is described. Tables and diagrams illustrate the present situation and development potential of various fields of technology.

  5. Ammonia Monitor

    Science.gov (United States)

    Sauer, Richard L. (Inventor); Akse, James R. (Inventor); Thompson, John O. (Inventor); Atwater, James E. (Inventor)

    1999-01-01

    Ammonia monitor and method of use are disclosed. A continuous, real-time determination of the concentration of ammonia in an aqueous process stream is possible over a wide dynamic range of concentrations. No reagents are required because pH is controlled by an in-line solid-phase base. Ammonia is selectively transported across a membrane from the process stream to an analytical stream to an analytical stream under pH control. The specific electrical conductance of the analytical stream is measured and used to determine the concentration of ammonia.

  6. Oscillator monitor

    International Nuclear Information System (INIS)

    McNeill, G.A.

    1981-01-01

    Present high-speed data acquisition systems in nuclear diagnostics use high-frequency oscillators to provide timing references for signals recorded on fast, traveling-wave oscilloscopes. An oscillator's sinusoidal wave shape is superimposed on the recorded signal with each cycle representing a fixed time increment. During data analysis the sinusoid is stripped from the signal, leaving a clean signal shape with known timing. Since all signal/time relationships are totally dependant upon working oscillators, these critical devices must have remote verification of proper operation. This manual presents the newly-developed oscillator monitor which will provide the required verification

  7. Luminosity monitor

    International Nuclear Information System (INIS)

    Underwood, D. G.

    1998-01-01

    Luminosity monitors are needed in each experiment doing spin physics at RHIC. They concentrate on the luminosity aspects here because, for example, with a 10 -3 raw asymmetry in an experiment, an error of 10 -4 in the luminosity is as significant as a 10% polarization error. Because luminosity is a property of how two beams overlap, the luminosity at an interaction region must be measured at that interaction region in order to be relevant to the experiment at that interaction region. The authors will have to do the physics and the luminosity measurements by using labels on the event sums according to the polarization labels on the colliding bunches. Most likely they will not have independent polarization measurement on each bunch, but only on all the filled bunches in a ring, or perhaps all the bunches that are actually used in an experiment. Most analyses can then be handled by using the nine combinations gotten from three kinds of bunches in each ring, +, - and empty bunches. The empty bunches are needed to measure beam-gas background, (and some, like six in a row, are needed for the beam abort). Much of the difficulty comes from the fact that they must use a physics process to represent the luminosity. This process must have kinematic and geometric cuts both to reduce systematics such as beam-gas backgrounds, and to make it representative of the part of the interaction diamond from which the physics events come

  8. Contamination monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Alamares, A L [Philippine Nuclear Research Inst., Diliman, Quezon City (Philippines)

    1997-06-01

    By virture of Republic Act 2067, as amended the Philippine Atomic Energy Commission (PAEC), now renamed Philippine Nuclear Research Institute (PNRI) is the government agency charged with the regulations and control of radioactive materials in the Philippines. The protection against the hazards of non-ionizing radiation is being monitored by the Radiological Health Service (RHS) of the Department of Health pursuant to the provision of Presidental Decree 480. The RHS issues licenses for possession, handling, and use of x-ray machines and equipment, both industrial and medical, and provide radiation protection training to x-ray technologists and technicians. As part of its regulatory function, the PNRI is charged with the responsibility of assuring that the radiation workers and the public are protected from the hazards associated with the possession, handling, production, manufacturing, and the use of radioactive materials and atomic energy facilities in the Philippines. The protection of radiation workers from the hazards of ionizing radiation has always been a primary concern of PNRI and by limiting the exposure of radiation workers, the risk to population is kept to within acceptable level. In this paper, the following items are described: radiation protection program, radiation protection services, radiation control, and problems encountered/recommendation. (G.K.)

  9. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  10. 78 FR 54674 - Notice of Intent To Prepare an Environmental Impact Statement for the Proposed Gold Rock Mine...

    Science.gov (United States)

    2013-09-05

    ..., reclamation, and post-closure monitoring periods would extend the project life for an additional estimated 38... and operation, including effects to night sky from nighttime operations. (h) Potential effects to...

  11. Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Hunter, S.W.; Gallegos, G.M.; Surano, K.A.; Lamson, K.C.; Tate, P.J.; Balke, B.K.; Biermann, A.H.; Hoppes, W.G.; Fields, B.C.; Gouveia, F.J.; Berger, R.L.; Miller, F.S.; Rueppel, D.W.; Sims, J.M.

    1992-04-01

    The primary tasks of the environmental monitoring section (EMS) Livermore National Laboratory (LLNL) are: effluent monitoring of air, sewer, and NPDES water. Surveillance monitoring of soil, vegetation and foodstuff, water, air particulate, and air tritium. Radiation monitoring, dose assessment, emergency response, quality assurance, and reporting. This report describes LLNL and the monitoring plan

  12. Wireless Transmission of Monitoring Data out of an Underground Repository: Results of Field Demonstrations Performed at the HADES Underground Laboratory - 13589

    International Nuclear Information System (INIS)

    Schroeder, T.J.; Rosca-Bocancea, E.; Hart, J.

    2013-01-01

    As part of the European 7. framework project MoDeRn, Nuclear Research and Consultancy Group (NRG) performed experiments in order to demonstrate the feasibility of wireless data transmission through the subsurface over large distances by low frequency magnetic fields in the framework of the geological disposal of radioactive waste. The main objective of NRG's contribution is to characterize and optimize the energy use of this technique within the specific context of post-closure monitoring of a repository. For that, measurements have been performed in the HADES Underground Research Laboratory (URL) located at Mol, Belgium, at 225 m depth. The experimental set-up utilizes a loop antenna for the transmitter that has been matched to the existing infrastructure of the HADES. Between 2010 and 2012 NRG carried out several experiments at the HADES URL in order to test the technical set-up and to characterize the propagation behavior of the geological medium and the local background noise pattern. Transmission channels have been identified and data transmission has been demonstrated at several frequencies, with data rates up to 10 bit/s and bit error rates <1%. A mathematical model description that includes the most relevant characteristics of the transmitter, transmission path, and receiver has been developed and applied to analyze possible options to optimize the set-up. With respect to the energy-efficiency, results so far have shown that data transmission over larger distances through the subsurface is a feasible option. To support the conclusions on the energy need per bit of transmitted data, additional experiments are foreseen. (authors)

  13. Development of web monitoring radiation area monitor

    International Nuclear Information System (INIS)

    Jung, Hoon Jin; Lee, Jun Hee; Namkoong, Phil; Lee, Dong Hoon; Lee, Su Hong; Lee, Gun Bae

    2005-01-01

    Recently the increasing number of radioisotope industry and nuclear facility have ever raised the possibility of radiation safety accident. As such a result, radioisotope companies and nuclear facility operators have become to be much interested in radiation area monitoring for efficient radiation protection. At present, almost of the radiation area monitors which are imported products are outdated in aspect of their functions. Diversification of the monitoring work is urgently demanding additional functions to be added. Thus we have developed new-type digital area monitor which enables remote web monitoring with image and radiation dose rate value at distant places through using internet, the latest IT technology, and radiation measurement technology

  14. Monitoring Knowledge Base (MKB)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Monitoring Knowledge Base (MKB) is a compilation of emissions measurement and monitoring techniques associated with air pollution control devices, industrial...

  15. Monitor resultaten geluid 2000

    NARCIS (Netherlands)

    Jabben J; Potma CJM; Swart WJR; LLO

    2001-01-01

    As part of an enhanced effort in monitoring the environmental quality in 1999, the RIVM set up a noise monitoring programme. This programme forms part of the project, "Development of a monitoring system for noise and disturbance", which aims at establishing a number of permanent sites for monitoring

  16. Radioactive surface contamination monitors

    International Nuclear Information System (INIS)

    Aoyama, Kei; Minagoshi, Atsushi; Hasegawa, Toru

    1994-01-01

    To reduce radiation exposure and prevent contamination from spreading, each nuclear power plant has established a radiation controlled area. People and articles out of the controlled area are checked for the surface contamination of radioactive materials with surface contamination monitors. Fuji Electric has repeatedly improved these monitors on the basis of user's needs. This paper outlines typical of a surface contamination monitor, a personal surface contamination monitor, an article surface contamination monitor and a laundry monitor, and the whole-body counter of an internal contamination monitor. (author)

  17. Monitoring of transport contamination

    International Nuclear Information System (INIS)

    Turkin, N.F.

    1980-01-01

    Organization of monitoring of transport contamination is considered. A particularly thorough monitoring is recommended to be carried out in loading-unloading operations. The monitoring is performed when leaving loading-unloading site and zone under control and prior to preventive examination, technical service or repair. The method of monitoring of auto transport contamination with high-energy β-emitters by means of a special stand permitting the automation of the monitoring process is described [ru

  18. Environmental γ radiation monitor

    International Nuclear Information System (INIS)

    Qu Xiaopeng

    1993-01-01

    The environmental γ radiation monitor is a kind of dose or dose rate measuring devices, which can be used for monitoring environmental γ radiation around a nuclear site when normal or even abnormal events occur. The monitor is controlled by a single-chip microcomputer so that it can acquire synchronously the data from four detectors and transfer the data to a central computer. The monitor has good temperature property due to the technique of temperature correction. The monitor has been used in the environment monitoring vehicle for Qinshan Nuclear Power Plant

  19. Modern Project: monitoring developments for safe repository operation and staged closure

    International Nuclear Information System (INIS)

    Mayer, S.; Ouchhi, S.; Verstricht, J.; Maurer, H.; Breen, B.

    2010-01-01

    Document available in extended abstract form only. In a first part, the overall objectives of the MoDeRn project (Monitoring Developments for safe Repository operation and stage closure project) are presented. MoDeRn is a four year (2009-2013) collaborative project co-funded under the 7. Framework Program for Nuclear Research and Training (EURATOM). It involves 17 organizations responsible for research into radioactive waste management in the European Union, United States, Japan and Switzerland, with partners with extensive experience in monitoring activities in underground research laboratories (URL); as well as research institutes and universities with substantial experience in research on socio-technical interactions and public and stakeholder engagement. An overview of the project work packages and of their interdependencies is given. The successful implementation of a repository program for radioactive waste relies on both the technical aspects of a sound safety strategy and scientific and engineering excellence as well as on social aspects such as stakeholder acceptance and confidence. Monitoring is considered key in serving both technical and social objectives. It is not only essential to underpin the technical safety strategy and quality of the engineering, but it can also be an important tool for public communication, contributing to public understanding of and confidence in the repository behaviour. By inclusion of specific national contexts of waste management programs in different countries, the MoDeRn project aims at providing a reference framework for development and implementation of monitoring activities. This will be achieved by stakeholder engagement during all identifiable phases of the radioactive waste disposal process. Thus, site characterisation, construction, operation and staged closure, as well as post-closure institutional control phases have to be addressed. MoDeRn considers different host rock types, such as salt, tuff, crystalline rock

  20. Monitoring natural phytoplankton communities

    DEFF Research Database (Denmark)

    Haraguchi, L.; Jakobsen, H. H.; Lundholm, Nina

    2017-01-01

    The phytoplankton community can vary within hours (physiology) to years (climatic and anthropogenic responses), and monitoring at different timescales is relevant for understanding community functioning and assessing changes. However, standard techniques used in monitoring programmes are time...

  1. Beam position monitoring

    International Nuclear Information System (INIS)

    Shafer, R.E.

    1990-01-01

    Beam monitoring in accelerators is reviewed, with emphasis on the engineering aspects of the problem. Guidelines for monitor design are given. Advantages and disadvantages of various electrode designs and signal processing methods are reviewed

  2. USAID Colombia - Clearinghouse Monitor

    Data.gov (United States)

    US Agency for International Development — The Monitoring and Evaluation (M&E) Clearinghouse-Monitor is a web-based Information System that provides the Mission with information about the status and...

  3. Inductive Monitoring System (IMS)

    Data.gov (United States)

    National Aeronautics and Space Administration — IMS: Inductive Monitoring System The Inductive Monitoring System (IMS) is a tool that uses a data mining technique called clustering to extract models of normal...

  4. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Thomas, P.

    1982-01-01

    The present paper deals with the following topics: - Radiological quantities and units - Principles of radiological protection - Limits of doses and activity uptake - Activity discharges and monitoring - Radiation exposure and its calculation - Environmental monitoring - Personnel dosimetry. (orig./RW)

  5. To monitor or not to monitor?: editorial

    International Nuclear Information System (INIS)

    Johns, T.F.

    1988-01-01

    After a brief discussion about results for occupational exposure in New Zealand and the UK, a short editorial raises a number of questions about personal dosimetry practice. These questions include whether the right people are being monitored and whether less attention should be paid to the monitoring of certain groups of workers who are occupationally exposed to external beta/gamma radiation, and more to the monitoring of workers or members of the general public who are exposed to higher doses from radon daughters, so as to focus attention on the areas where the largest savings in collective dose could be achieved. (U.K.)

  6. Inside the Monitor Model

    DEFF Research Database (Denmark)

    Carl, Michael; Dragsted, Barbara

    2012-01-01

    a “monitor model” according to which translators start with a literal default rendering procedure and where a monitor interrupts the default procedure when a problem occurs. This paper suggests an extension of the monitor model in which comprehension and production are processed in parallel by the default...

  7. Remote Monitoring Transparency Program

    International Nuclear Information System (INIS)

    Sukhoruchkin, V.K.; Shmelev, V.M.; Roumiantsev, A.N.

    1996-01-01

    The objective of the Remote Monitoring Transparency Program is to evaluate and demonstrate the use of remote monitoring technologies to advance nonproliferation and transparency efforts that are currently being developed by Russia and the United States without compromising the national security to the participating parties. Under a lab-to-lab transparency contract between Sandia National Laboratories (SNL) and the Kurchatov Institute (KI RRC), the Kurchatov Institute will analyze technical and procedural aspects of the application of remote monitoring as a transparency measure to monitor inventories of direct- use HEU and plutonium (e.g., material recovered from dismantled nuclear weapons). A goal of this program is to assist a broad range of political and technical experts in learning more about remote monitoring technologies that could be used to implement nonproliferation, arms control, and other security and confidence building measures. Specifically, this program will: (1) begin integrating Russian technologies into remote monitoring systems; (2) develop remote monitoring procedures that will assist in the application of remote monitoring techniques to monitor inventories of HEU and Pu from dismantled nuclear weapons; and (3) conduct a workshop to review remote monitoring fundamentals, demonstrate an integrated US/Russian remote monitoring system, and discuss the impacts that remote monitoring will have on the national security of participating countries

  8. BPA genetic monitoring - BPA Genetic Monitoring Project

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Initiated in 1989, this study monitors genetic changes associated with hatchery propagation in multiple Snake River sub-basins for Chinook salmon and steelhead. We...

  9. Deep Controlled Source Electro-Magnetic Sensing: A Cost Effective, Long-Term Tool for Sequestration Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    LaBrecque, Douglas [Multi-Phase Technologies, LLC, Sparks, NV (United States); Brigham, Russell D. [Multi-Phase Technologies, LLC, Sparks, NV (United States); Schmidt-Hattenburger, Conny [GFZ German Research Centre for Geoscience, Potsdam (Germany); Um, Evan [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Petrov, Peter [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Daley, Thomas [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-05-01

    The proposed system was designed to operate as a permanent, autonomous monitoring and data collection system that can provide much higher temporal data density than can be achieved economically with 3-Dimensional (3D) seismic surveys. It can operate over broad areas for long periods of time providing full 3D data sets on a monthly basis at a very low cost. By borrowing techniques commonly used in marine CSEM, structural information from background seismic surveys can be incorporated into the CSEM modeling to provide high resolution models of CO2 progression within reservoirs. The system uses borehole-based vertical-electric-dipole sources placed at reservoir depths in the formation. The electric and magnetic fields induced by this source are received on the surface using an array of stations. The project was conducted in three phases. Phase I demonstrated the feasibility of the system to collect static/reference data at the Ketzin CO2 storage pilot site in Germany. In Phase I, numerical modeling was used to determine the optimal configurations and requirements for sensor sensitivity and data accuracy. Based on the model results, existing hardware and software were modified. The CSEM system was then field tested at the Ketzin site. The data were imaged and the results were compared with independent studies of the reservoir and overburden geo-electrical characteristics. Phase II demonstrated the ability to provide sensitive, cost-effective measurement of changes in reservoir properties and changes in the overlying formations using a second round of measurements at the Ketzin site. A prototype autonomous recording system was developed and tested as a subset of the measurement points. Phase III of the project quantified the advantages (and disadvantages) of the fully autonomous data collection subsystems by comparing them with repeated measurements made with mobile stations. The Phase III also provided an additional time point in measuring post-closure

  10. Compact neutron flux monitor

    International Nuclear Information System (INIS)

    Madhavi, V.; Phatak, P.R.; Bahadur, C.; Bayala, A.K.; Jakati, R.K.; Sathian, V.

    2003-01-01

    Full text: A compact size neutron flux monitor has been developed incorporating standard boards developed for smart radiation monitors. The sensitivity of the monitors is 0.4cps/nV. It has been tested up to 2075 nV flux with standard neutron sources. It shows convincing results even in high flux areas like 6m away from the accelerator in RMC (Parel) for 106/107 nV. These monitors have a focal and remote display, alarm function with potential free contacts for centralized control and additional provision of connectivity via RS485/Ethernet. This paper describes the construction, working and results of the above flux monitor

  11. Nuclear reactor effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L.; Essig, T.H. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-12-31

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC`s program results.

  12. Nuclear reactor effluent monitoring

    International Nuclear Information System (INIS)

    Minns, J.L.; Essig, T.H.

    1993-01-01

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC's program results

  13. Movement monitoring device

    International Nuclear Information System (INIS)

    Ichikawa, Takashi; Yoneda, Yasuaki; Hanatsumi, Masaharu.

    1997-01-01

    The present invention provides a device suitable to accurate recognition for the moving state of reactor core fuels as an object to be monitored in a nuclear power plant. Namely, the device of the present invention prepares each of scheduled paths for the movement of the object to be monitored and executed moving paths along with the movement based on the information of the movement obtained from scheduled information for the movement of the reactor core fuels as a object to be monitored and the actual movement of the object to be monitored. The results of the preparation are outputted. As an output mode, (1) the results of preparation for each of the paths for movement and the results of the monitoring obtained by monitoring the state of the object to be monitored are jointed and outputted, (2) images showing each of the paths for the movement are formed, and the formed images are displayed on a screen, and (3) each of the moving paths is prepared as an image, and the image is displayed together with the image of the regions before and after the movement of the object to be monitored. In addition, obtained images of each of the paths for the movement and the monitored images obtained by monitoring the state of the object to be monitored are joined and displayed. (I.S.)

  14. Modular remote radiation monitor

    International Nuclear Information System (INIS)

    Lacerda, Fabio; Farias, Marcos S.; Aghina, Mauricio A.C.; Oliveira, Mauro V.

    2013-01-01

    The Modular Remote Radiation Monitor (MRRM) is a novel radiation monitor suitable for monitoring environmental exposure to ionizing radiation. It is a portable compact-size low-power microprocessor-based electronic device which provides its monitoring data to other electronic systems, physically distant from it, by means of an electronic communication channel, which can be wired or wireless according to the requirements of each application. Besides its low-power highly-integrated circuit design, the Modular Remote Radiation Monitor is presented in a modular architecture, which promotes full compliance to the technical requirements of different applications while minimizing cost, size and power consumption. Its communication capability also supports the implementation of a network of multiple radiation monitors connected to a supervisory system, capable of remotely controlling each monitor independently as well as visualizing the radiation levels from all monitors. A prototype of the MRRM, functionally equivalent to the MRA-7027 radiation monitor, was implemented and connected to a wired MODBUS network of MRA-7027 monitors, responsible for monitoring ionizing radiation inside Argonauta reactor room at Instituto de Engenharia Nuclear. Based on the highly positive experimental results obtained, further design is currently underway in order to produce a consumer version of the MRRM. (author)

  15. Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Holland, R.C. [Science Applications International Corp., San Diego, CA (United States)

    1993-07-01

    This Environmental Monitoring Plan was written to fulfill the requirements of Department of Energy (DOE) Order 5400.1 and DOE Environmental Regulatory Guide DOE/EH 0173T. This Plan documents the background, organizational structure, and methods used for effluent monitoring and environmental surveillance at Sandia National Laboratories/California. The design, rationale, and historical results of the environmental monitoring system are discussed in detail. Throughout the Plan, recommendations for improvements to the monitoring system are made. This revision to the Environmental Monitoring Plan was written to document the changes made to the Monitoring Program during 1992. Some of the data (most notably the statistical analyses of past monitoring data) has not been changed.

  16. Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Holland, R.C.

    1993-07-01

    This Environmental Monitoring Plan was written to fulfill the requirements of Department of Energy (DOE) Order 5400.1 and DOE Environmental Regulatory Guide DOE/EH 0173T. This Plan documents the background, organizational structure, and methods used for effluent monitoring and environmental surveillance at Sandia National Laboratories/California. The design, rationale, and historical results of the environmental monitoring system are discussed in detail. Throughout the Plan, recommendations for improvements to the monitoring system are made. This revision to the Environmental Monitoring Plan was written to document the changes made to the Monitoring Program during 1992. Some of the data (most notably the statistical analyses of past monitoring data) has not been changed

  17. Monitoring your baby before labor

    Science.gov (United States)

    ... stress test - monitoring; CST- monitoring; Biophysical profile - monitoring; BPP - monitoring ... A biophysical profile (BPP) is a NST with an ultrasound. If the NST results are not reactive, a BPP may be done. The ...

  18. Power consumption monitoring using additional monitoring device

    Energy Technology Data Exchange (ETDEWEB)

    Truşcă, M. R. C., E-mail: radu.trusca@itim-cj.ro; Albert, Ş., E-mail: radu.trusca@itim-cj.ro; Tudoran, C., E-mail: radu.trusca@itim-cj.ro; Soran, M. L., E-mail: radu.trusca@itim-cj.ro; Fărcaş, F., E-mail: radu.trusca@itim-cj.ro [National Institute for Research and Development of Isotopic and Molecular Technologies, 65-103 Donath, 400293 Cluj-Napoca (Romania); Abrudean, M. [Technical University of Cluj-Napoca, Cluj-Napoca (Romania)

    2013-11-13

    Today, emphasis is placed on reducing power consumption. Computers are large consumers; therefore it is important to know the total consumption of computing systems. Since their optimal functioning requires quite strict environmental conditions, without much variation in temperature and humidity, reducing energy consumption cannot be made without monitoring environmental parameters. Thus, the present work uses a multifunctional electric meter UPT 210 for power consumption monitoring. Two applications were developed: software which carries meter readings provided by electronic and programming facilitates remote device and a device for temperature monitoring and control. Following temperature variations that occur both in the cooling system, as well as the ambient, can reduce energy consumption. For this purpose, some air conditioning units or some computers are stopped in different time slots. These intervals were set so that the economy is high, but the work's Datacenter is not disturbed.

  19. Monitor inspection device

    International Nuclear Information System (INIS)

    Ueshima, Yoshinobu.

    1995-01-01

    The device of the present invention reliably conducts monitoring by radiation monitors in a nuclear power plant thereby contributing to save the number of radiation operators and reduction of radiation exposure. Namely, radiation monitors continuously measure a plurality of γ-ray levels. A branched simultaneously counting circuit receives these signals. The output of the branched simultaneously counting circuit is inputted to a differentiation means. The differentiation means calculates a variation coefficient for each of the radiation monitoring values, namely, equivalent dose rates, and records and monitors change with time of the equivalent dose rates. With such procedures, the results of the monitoring of γ-ray levels can be judged objectively corresponding to the increase of the equivalent dose rates. As a result, the number of radiation operators can be saves and radiation exposure of the radiation operators can be reduced. (I.S.)

  20. Occupational monitoring program

    International Nuclear Information System (INIS)

    Sordi, G.-M.A.A.

    1988-10-01

    After to give the principal aim of a monitoring program it gives the philosophy in force in our country and the new one, international. It shows the different monitoring types and the classification related to their functions. The functions are deal with, separately, for workplace and individual monitoring. It shows, also, that the individual monitoring can be used to assess the workplace conditions. It discusses the models that can be introduced to assess the quantities used in the results interpretation from the quantities used in the measurements. It gives an example. Finally it discusses the supplementary functions of monitoring as such reassessment of monitoring programs, selection of the controlled areas and the extent form of medical supervision. (author) [pt

  1. [Blood glucose self monitoring].

    Science.gov (United States)

    Wascher, Thomas C; Stechemesser, Lars

    2016-04-01

    Self monitoring of blood glucose contributes to the integrated management of diabetes mellitus. It, thus, should be available for all patients with diabetes mellitus type-1 and type-2. Self monitoring of blood glucose improves patients safety, quality of life and glucose control. The current article represents the recommendations of the Austrian Diabetes Association for the use of blood glucose self monitoring according to current scientific evidence.

  2. Radiation contamination monitors

    International Nuclear Information System (INIS)

    Kato, Tsutomu; Iba, Hiroshi; Sato, Hiroshi

    1999-01-01

    To make sure of no contamination on people, used articles and working uniforms coming out of the radiation controlled area, nuclear power plants are equipped with radioactive contamination monitors. This paper outlines the basic specifications and advantages of our personnel surface contamination monitors to inspect whole-body surface contamination of people coming out, article surface contamination monitors to inspect the surface and inside contamination of used articles brought out, laundry monitors to inspect surface contamination of working uniforms used in the area before and after a wash, and whole-body counters to inspect and measure the internal contamination of a person out of the area. (author)

  3. Monitoring of radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service.

  4. Monitoring of radiation exposure

    International Nuclear Information System (INIS)

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service

  5. Remote Maintenance Monitoring System -

    Data.gov (United States)

    Department of Transportation — The Remote Maintenance and Monitoring System (RMMS) is a collection of subsystems that includes telecommunication components, hardware, and software, which serve to...

  6. Environmental monitoring plan

    International Nuclear Information System (INIS)

    Holland, R.C.

    1997-02-01

    This Environmental Monitoring Plan was written to fulfill the requirements of Department of Energy (DOE) Order 5400.1 and DOE Environmental Regulatory Guide DOE/EH 0173T. This Plan documents the background, organizational structure, and methods used for effluent monitoring and environmental surveillance at Sandia National Laboratories/California. The design, rationale, and historical results of the environmental monitoring system are discussed in detail. Throughout the Plan, recommendations for improvements to the monitoring system are made. 52 refs., 10 figs., 12 tabs

  7. Facility effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

  8. Personnel Monitoring Department - DEMIN

    International Nuclear Information System (INIS)

    1989-01-01

    The activities and purposes of the Personnel Monitoring Dept. of the Institute of Radioprotection and Dosimetry of the Brazilian CNEN are presented. A summary of the personnel monitoring service is given, such as dosemeters supply, laboratorial inspections, and so on. The programs of working, publishing, courses and personnel interchange are also presented. (J.A.M.M.)

  9. Liquid metal monitor

    International Nuclear Information System (INIS)

    Caldwell-Nichols, C.J.; Roach, P.F.

    1982-01-01

    A liquid metal monitor of the by-pass plugging meter kind described in British Patent 1,308,466, is further provided with a pump arranged to oppose flow through a by-pass thereby to provide a constant pressure difference across an orifice and improve the sensitivity of the instrument. The monitor estimates the impurity content in a liquid metal stream. (author)

  10. Simple beam profile monitor

    Energy Technology Data Exchange (ETDEWEB)

    Gelbart, W.; Johnson, R. R.; Abeysekera, B. [ASD Inc. Garden Bay, BC (Canada); Best Theratronics Ltd Ottawa Ontario (Canada); PharmaSpect Ltd., Burnaby BC (Canada)

    2012-12-19

    An inexpensive beam profile monitor is based on the well proven rotating wire method. The monitor can display beam position and shape in real time for particle beams of most energies and beam currents up to 200{mu}A. Beam shape, position cross-section and other parameters are displayed on a computer screen.

  11. Improved Marine Waters Monitoring

    Science.gov (United States)

    Palazov, Atanas; Yakushev, Evgeniy; Milkova, Tanya; Slabakova, Violeta; Hristova, Ognyana

    2017-04-01

    IMAMO - Improved Marine Waters Monitoring is a project under the Programme BG02: Improved monitoring of marine waters, managed by Bulgarian Ministry of environment and waters and co-financed by the Financial Mechanism of the European Economic Area (EEA FM) 2009 - 2014. Project Beneficiary is the Institute of oceanology - Bulgarian Academy of Sciences with two partners: Norwegian Institute for Water Research and Bulgarian Black Sea Basin Directorate. The Project aims to improve the monitoring capacity and expertise of the organizations responsible for marine waters monitoring in Bulgaria to meet the requirements of EU and national legislation. The main outcomes are to fill the gaps in information from the Initial assessment of the marine environment and to collect data to assess the current ecological status of marine waters including information as a base for revision of ecological targets established by the monitoring programme prepared in 2014 under Art. 11 of MSFD. Project activities are targeted to ensure data for Descriptors 5, 8 and 9. IMAMO aims to increase the institutional capacity of the Bulgarian partners related to the monitoring and assessment of the Black Sea environment. The main outputs are: establishment of real time monitoring and set up of accredited laboratory facilities for marine waters and sediments chemical analysis to ensure the ability of Bulgarian partners to monitor progress of subsequent measures undertaken.

  12. Digital radiation monitor system

    International Nuclear Information System (INIS)

    Quan Jinhu; Zhai Yongchun; Guan Junfeng; Ren Dangpei; Ma Zhiyuan

    2003-01-01

    The article introduced digital radiation monitor system. The contents include: how to use advanced computer net technology to establish equipment net for nuclear facility, how to control and manage measuring instruments on field equipment net by local area net, how to manage and issue radiation monitoring data by internet

  13. Environmental radiation monitoring

    International Nuclear Information System (INIS)

    Watanabe, Isao

    2011-01-01

    The samples, pretreatment method, and measurement methods of 'Environmental radioactivity level by prefecture' of Ministry of Education, Culture, Sports, Science and Education (MEXT) is explained. It consists of 1), 'Environmental radioactivity level by prefecture' in normal period, 2) 'Strengthening of Monitoring of Environmental Radioactivity Level by Prefecture' of MEXT at emergency 3) strengthening of monitoring by Fukushima Daiichi nuclear accident, 4) radiation monitoring around the nuclear facility, 5) strengthening of monitoring by MEXT, and 6) quality of monitoring. The survey item and samples etc., of 'Environmental radioactivity level by prefecture', monitoring post, NaI (Tl) scintillation survey meter, sampling and pretreatment methods for radionuclide analysis in normal period, an example of germanium semiconductor detector, gamma ray spectrum of spaghetti from Italy by germanium semiconductor detector, flow chart of radionuclide analysis of fallout in normal period and emergency by germanium semiconductor detector, example of analytical method of radioactive strontium ( ion exchange method), outline of plutonium analytical method for emergency, sampling and pretreatment methods of radionuclides for strengthening, monitoring result around Fukushima Daiichi nuclear plant from June 23 to 24, 2011, change of air dose rate of monitoring post in Mito city from March 14 to 26, 2011, concentration of I-131 and Cs-137 in fallout in Hitachinaka city from March 19 to April 30, 2011, and change of concentration of I-131, Cs-134 and Cs-137 in tap water of Iitate village from March 20 to April 30, 2011, are illustrated. (S.Y.)

  14. Water Quality Monitoring Manual.

    Science.gov (United States)

    Mason, Fred J.; Houdart, Joseph F.

    This manual is designed for students involved in environmental education programs dealing with water pollution problems. By establishing a network of Environmental Monitoring Stations within the educational system, four steps toward the prevention, control, and abatement of water pollution are proposed. (1) Train students to recognize, monitor,…

  15. Monitoring Cray Cooling Systems

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, Don E [ORNL; Ezell, Matthew A [ORNL; Becklehimer, Jeff [Cray, Inc.; Donovan, Matthew J [ORNL; Layton, Christopher C [ORNL

    2014-01-01

    While sites generally have systems in place to monitor the health of Cray computers themselves, often the cooling systems are ignored until a computer failure requires investigation into the source of the failure. The Liebert XDP units used to cool the Cray XE/XK models as well as the Cray proprietary cooling system used for the Cray XC30 models provide data useful for health monitoring. Unfortunately, this valuable information is often available only to custom solutions not accessible by a center-wide monitoring system or is simply ignored entirely. In this paper, methods and tools used to harvest the monitoring data available are discussed, and the implementation needed to integrate the data into a center-wide monitoring system at the Oak Ridge National Laboratory is provided.

  16. Monitoring Evolution at CERN

    CERN Document Server

    Andrade, P; Murphy, S; Pigueiras, L; Santos, M

    2015-01-01

    Over the past two years, the operation of the CERN Data Centres went through significant changes with the introduction of new mechanisms for hardware procurement, new services for cloud provisioning and configuration management, among other improvements. These changes resulted in an increase of resources being operated in a more dynamic environment. Today, the CERN Data Centres provide over 11000 multi-core processor servers, 130 PB disk servers, 100 PB tape robots, and 150 high performance tape drives. To cope with these developments, an evolution of the data centre monitoring tools was also required. This modernisation was based on a number of guiding rules: sustain the increase of resources, adapt to the new dynamic nature of the data centres, make monitoring data easier to share, give more flexibility to Service Managers on how they publish and consume monitoring metrics and logs, establish a common repository of monitoring data, optimise the handling of monitoring notifications, and replace the previous ...

  17. Monitoring production target thickness

    International Nuclear Information System (INIS)

    Oothoudt, M.A.

    1993-01-01

    Pion and muon production targets at the Clinton P. Anderson Meson Physics Facility consist of rotating graphite wheels. The previous target thickness monitoring Procedure scanned the target across a reduced intensity beam to determine beam center. The fractional loss in current across the centered target gave a measure of target thickness. This procedure, however, required interruption of beam delivery to experiments and frequently indicated a different fractional loss than at normal beam currents. The new monitoring Procedure compares integrated ups and downs toroid current monitor readings. The current monitors are read once per minute and the integral of readings are logged once per eight-hour shift. Changes in the upstream to downstream fractional difference provide a nonintrusive continuous measurement of target thickness under nominal operational conditions. Target scans are now done only when new targets are installed or when unexplained changes in the current monitor data are observed

  18. Space weather monitoring with neutron monitor measurements

    Energy Technology Data Exchange (ETDEWEB)

    Steigies, Christian [Christian-Albrechts-Universitaet zu Kiel (Germany)

    2013-07-01

    Space Weather affects many areas of the modern society, advance knowledge about space weather events is important to protect personnel and infrastructure. Cosmic Rays (CR) measurements by ground-based Neutron Monitors are influenced by Coronal Mass Ejections (CME), the intensity of the ever present Cosmic Rays is reduced in a Forbush decrease (Fd). In the case of very energetic CMEs, the measured intensity can be significantly increased in a Ground Level Enhancement (GLE). By detecting the anisotropy of the CR environment, a CME can be detected hours before it arrives at Earth. During a GLE the high-energy particles from the Sun can be detected before the more abundant lower energy particles arrive at Earth, thus allowing to take protective measures. Since the beginning of the Neutron Monitor Database (NMDB) project, which has been started in 2008 with funding from the European Commission, real-time data from Neutron Monitors around the world has been made available through one web-portal. We have more than doubled the number of stations providing data since the start of the project to now over 30 stations. The effectiveness of the ALERT applications which are based on NMDB data has been shown by the recent GLE71. We present different applications through which the measurements and different data products are accessible.

  19. CEMs turn monitoring giant

    International Nuclear Information System (INIS)

    White, J.R.

    1993-01-01

    Crucial to complying with environmental regulations is selecting appropriate pollution control equipment to capture or destroy regulated pollutants. But just as important is selecting a continuous emissions monitoring system (CEM). CEMs play a dual role in an overall compliance strategy. On one hand, they identify the type and quantity of emissions at a source as a first step for determining which regulatory requirements and control technologies are applicable. They also provide ongoing emissions data to demonstrate compliance with air and other environmental regulations. Facilities are required to monitor their processes with CEMs, or a comparable technology, under several titles of the Clean Air Act Amendments of 1990. CEMs meet regulatory requirements if they include a SO 2 concentration monitor, nitrogen oxides (NO x ) concentration monitor, volumetric flow monitor, opacity monitor, diluent gas monitor and data acquisition and handling system. The entire system and each subsystem has to be installed and certified before it can be used for compliance. A written quality assurance/quality control (QA/QC) plan for the CEMs must accompany the permit application. The acid rain rules also impose performance standards and frequent calibration checks to ensure the integrity of CEMs data

  20. Safety system status monitoring

    International Nuclear Information System (INIS)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

  1. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  2. Agile infrastructure monitoring

    International Nuclear Information System (INIS)

    Andrade, P; Ascenso, J; Fedorko, I; Fiorini, B; Paladin, M; Pigueiras, L; Santos, M

    2014-01-01

    At the present time, data centres are facing a massive rise in virtualisation and cloud computing. The Agile Infrastructure (AI) project is working to deliver new solutions to ease the management of CERN data centres. Part of the solution consists in a new 'shared monitoring architecture' which collects and manages monitoring data from all data centre resources. In this article, we present the building blocks of this new monitoring architecture, the different open source technologies selected for each architecture layer, and how we are building a community around this common effort.

  3. Radioactive Plumes Monitoring Simulator

    International Nuclear Information System (INIS)

    Kapelushnik, I.; Sheinfeld, M.; Avida, R.; Kadmon, Y.; Ellenbogen, M.; Tirosh, D.

    1999-01-01

    The Airborne Radiation Monitoring System (ARMS) monitors air or ground radioactive contamination. The contamination source can be a radioactive plume or an area contaminated with radionuclides. The system is based on two major parts, an airborne unit carried by a helicopter and a ground station carried by a truck. The system enables real time measurement and analysis of radioactive plumes as well as post flight processing. The Radioactive Plumes Monitoring Simulator purpose is to create a virtual space where the trained operators experience full radiation field conditions, without real radiation hazard. The ARMS is based on a flying platform and hence the simulator allows a significant reduction of flight time costs

  4. Java online monitoring framework

    International Nuclear Information System (INIS)

    Ronan, M.; Kirkby, D.; Johnson, A.S.; Groot, D. de

    1997-10-01

    An online monitoring framework has been written in the Java Language Environment to develop applications for monitoring special purpose detectors during commissioning of the PEP-II Interaction Region. PEP-II machine parameters and signals from several of the commissioning detectors are logged through VxWorks/EPICS and displayed by Java display applications. Remote clients are able to monitor the machine and detector performance using graphical displays and analysis histogram packages. In this paper, the design and implementation of the object-oriented Java framework is described. Illustrations of data acquisition, display and histograming applications are also given

  5. Plant monitoring system

    International Nuclear Information System (INIS)

    Tamaoki, Tetsuo.

    1994-01-01

    The memory means of the present invention memorize conditions for analyzing a sampling period for inputting process signals and time sequential data of the process signals. The process signals are analyzed following after sampling period and the analysis conditions stored in the memory means preceding to monitoring. A monitoring condition setting means controls and subsequently updates the sampling period and the analysis conditions in the memory means based on the analysis data, to finally set monitoring conditions. With such procedures, analysis conditions such as optimum analysis frequency range, signal sampling period and correlational characteristics between process noise signals are automatically selected. (I.S.)

  6. MCO Monitoring activity description

    International Nuclear Information System (INIS)

    SEXTON, R.A.

    1998-01-01

    Spent Nuclear Fuel remaining from Hanford's N-Reactor operations in the 1970s has been stored under water in the K-Reactor Basins. This fuel will be repackaged, dried and stored in a new facility in the 200E Area. The safety basis for this process of retrieval, drying, and interim storage of the spent fuel has been established. The monitoring of MCOS in dry storage is a currently identified issue in the SNF Project. This plan outlines the key elements of the proposed monitoring activity. Other fuel stored in the K-Reactor Basins, including SPR fuel, will have other monitoring considerations and is not addressed by this activity description

  7. Source Monitoring in Alzheimer's Disease

    Science.gov (United States)

    El Haj, Mohamad; Fasotti, Luciano; Allain, Philippe

    2012-01-01

    Source monitoring is the process of making judgments about the origin of memories. There are three categories of source monitoring: reality monitoring (discrimination between self- versus other-generated sources), external monitoring (discrimination between several external sources), and internal monitoring (discrimination between two types of…

  8. Monitoring Forsmark. Bird monitoring in Forsmark 2010

    Energy Technology Data Exchange (ETDEWEB)

    Green, Martin (Dept. of Animal Ecology, Lund Univ. (Sweden))

    2010-12-15

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds Directive) breeding birds in Forsmark 2002-2010. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2010 in the same way as in earlier years. The results from the monitoring in 2010 differed somewhat from results gathered in earlier years. Most monitored species have increased in local numbers during the study years, and from most years continued increases have been reported. Between 2009 and 2010 most species (seven, 64% of the monitored ones) instead decreased in numbers. Only one species (honey buzzard) increased in numbers between the years and in this case this was probably more a result of small moves by certain pairs so that they this year had parts reaching into the regional model area, while in 2009 their territories were outside of this. No dramatic changes in bird numbers were however recorded and all the studied species show stable or increasing local populations over the study period. Number of Black-throated diver pairs was normal and breeding success was good this year. The breeding success of divers has improved considerably over the studied period and the patterns recorded in Forsmark closely follow recorded patterns at the national level. Honey buzzards and ospreys occurred in good numbers, above the average for the whole period, and breeding success was better than in 2009. Even if breeding success of honey buzzards is not monitored in any detail, there were still signs of at least a few successful breedings in the area this year. Breeding success of ospreys was below average, but still within the normal variation for most years. The local white-tailed eagles had a poor breeding season and no young at all were produced within the study area. All three grouse species (black grouse, capercaillie and hazelhen) decreased in numbers between 2009 and 2010. Note however that the large amounts of snow

  9. Monitoring Forsmark. Bird monitoring in Forsmark 2010

    International Nuclear Information System (INIS)

    Green, Martin

    2010-12-01

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds Directive) breeding birds in Forsmark 2002-2010. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2010 in the same way as in earlier years. The results from the monitoring in 2010 differed somewhat from results gathered in earlier years. Most monitored species have increased in local numbers during the study years, and from most years continued increases have been reported. Between 2009 and 2010 most species (seven, 64% of the monitored ones) instead decreased in numbers. Only one species (honey buzzard) increased in numbers between the years and in this case this was probably more a result of small moves by certain pairs so that they this year had parts reaching into the regional model area, while in 2009 their territories were outside of this. No dramatic changes in bird numbers were however recorded and all the studied species show stable or increasing local populations over the study period. Number of Black-throated diver pairs was normal and breeding success was good this year. The breeding success of divers has improved considerably over the studied period and the patterns recorded in Forsmark closely follow recorded patterns at the national level. Honey buzzards and ospreys occurred in good numbers, above the average for the whole period, and breeding success was better than in 2009. Even if breeding success of honey buzzards is not monitored in any detail, there were still signs of at least a few successful breedings in the area this year. Breeding success of ospreys was below average, but still within the normal variation for most years. The local white-tailed eagles had a poor breeding season and no young at all were produced within the study area. All three grouse species (black grouse, capercaillie and hazelhen) decreased in numbers between 2009 and 2010. Note however that the large amounts of snow

  10. Post-Closure Challenges of U.S. Department of Energy Sites in Desert Environments of the Southwestern United States - 12095

    Energy Technology Data Exchange (ETDEWEB)

    Gil, April; Steckley, Deborah [U.S. Department of Energy Office of Legacy Management (United States); Gauthier, Cassie; Miller, David [S.M. Stoller Company, Contractor to the U.S. Department of Energy (United States)

    2012-07-01

    U.S. Department of Energy (DOE) sites located in harsh desert environments of the Four Corners region of the southwestern United States require diligence and continual maintenance to ensure the remediation systems function as designed to protect human health and the environment. The geology and climate of this area create issues that are unique to these sites. Geologic formations contain naturally occurring constituents that are often the same as the residual contaminants remaining from historical milling activities at the sites. Although annual precipitation is low, when precipitation events occur they can be of extreme intensity, resulting in erosion and flooding that can quickly destroy infrastructure and rapidly change site conditions. Winds can cause sand storms and sand mounding that effect site features. These challenging environmental conditions, along with the remote locations of the sites, require active management beyond what was originally envisioned for uranium disposal sites to address concerns in a safe and cost-effective manner. The unique environment of the Four Corners region creates many challenges to the LTSM of LM sites in southwestern United States. The remediation efforts and approaches to infrastructure have to be specifically structured to work in this environment. Often, the systems and structures have to be modified based on lessons learned on how to best adapt to these difficult conditions and remote locations. These sites require continual maintenance and additional efforts compared to many other LM sites. (authors)

  11. An investigation into local socio-environmental characteristics in relation to post-closure arrangements with the uranium mine at the Ningyo-Toge Environmental Engineering Center

    International Nuclear Information System (INIS)

    Matsumoto, Satoshi; Horikoshi, Hidehiko; Goto, Daisuke; Sono, Miharu; Kumetani, Hiromitsu

    2004-03-01

    This research aims to gain an understanding of local socio-environmental characteristics surrounding the Ningyo-Toge Environmental Engineering Center, from the viewpoint of bidirectional information sharing. In order to clarify the relevant issues, we analyzed publicly available information over the past 20 years. We also conducted an internet survey to assess risk perceptions etc. and feelings toward local enterprises, of residents in the surrounding localities and the general public. Expectations for economic benefits of the facilities began to fade in mid 1980s while negative aspects drew increasing attention. Local assemblies disputed over reliability, not technical safety. In Okayama prefecture there found a strong sense of avoidance toward radioactive waste disposal, the background of their refusal of carrying-in of waste rock from Togo-cho Shimane prefecture. A majority of local residents see nuclear facilities as highly dangerous. National newspapers, NHK, professional researchers were identified as reliable sources of information regarding atomic energy and radioactively, indicating the effectiveness of information dissemination through them. Though residents in the surrounding localities are aware of economic benefits of nuclear facilities, a majority of them would refuse the siting of a new one. Meanwhile, revitalization of local communities was found to be in need, in which local enterprises were expected to participate. (author)

  12. Evolution Of Chemical Conditions And Estimated Plutonium Solubility In The Residual Waste Layer During Post-Closure Aging Of Tank 18

    International Nuclear Information System (INIS)

    Denham, M.

    2012-01-01

    This document updates the Eh-pH transitions from grout aging simulations and the plutonium waste release model of Denham (2007, Rev. 1) based on new data. New thermodynamic data for cementitious minerals are used for the grout simulations. Newer thermodynamic data, recommended by plutonium experts (Plutonium Solubility Peer Review Report, LA-UR-12-00079), are used to estimate solubilities of plutonium at various pore water compositions expected during grout aging. In addition, a new grout formula is used in the grout aging simulations and apparent solubilities of coprecipitated plutonium are estimated using data from analysis of Tank 18 residual waste. The conceptual model of waste release and the grout aging simulations are done in a manner similar to that of Denham (2007, Rev. 1). It is assumed that the pore fluid composition passing from the tank grout into the residual waste layer controls the solubility, and hence the waste release concentration of plutonium. Pore volumes of infiltrating fluid of an assumed composition are reacted with a hypothetical grout block using The Geochemist's Workbench(reg s ign) and changes in pore fluid chemistry correspond to the number of pore fluid volumes reacted. As in the earlier document, this results in three states of grout pore fluid composition throughout the simulation period that are termed Reduced Region II, Oxidized Region II, and Oxidized Region III. The one major difference from the earlier document is that pyrite is used to account for reducing capacity of the tank grout rather than pyrrhotite. This poises Eh at -0.47 volts during Reduced Region II. The major transitions in pore fluid composition are shown. Plutonium solubilities are estimated for discrete PuO2(am,hyd) particles and for plutonium coprecipitated with iron phases in the residual waste. Thermodynamic data for plutonium from the Nuclear Energy Agency are used to estimate the solubilities of the discrete particles for the three stages of pore fluid evolution. In Denham (2007, Rev. 1), the solubilities in the oxidized regions were estimated at Eh values in equilibrium with dissolved oxygen. Here, these are considered to be maximum possible solubilities because Eh values are unlikely to be in equilibrium with dissolved oxygen. More realistic Eh values are estimated here and plutonium solubilities calculated at these are considered more realistic. Apparent solubilities of plutonium that coprecipitated with iron phases are estimated from Pu:Fe ratios in Tank 18 residual waste and the solubilities of the host iron phases. The estimated plutonium solubilities are shown. Uncertainties in the grout simulations and plutonium solubility estimates are discussed. The primary uncertainty in the grout simulations is that little is known about the physical state of the grout as it ages. The simulations done here are pertinent to a porous medium, which may or may not be applicable to fractured grout, depending on the degree and nature of the fractures. Other uncertainties that are considered are the assumptions about the reducing capacity imparted by blast furnace slag, the effects of varying dissolved carbon dioxide and oxygen concentrations, and the treatment of silica in the simulations. The primary uncertainty in the estimates of plutonium solubility is that little is known about the exact form of plutonium in the residual waste. Other uncertainties include those inherent in the thermodynamic data, pH variations from those estimated in the grout simulations, the effects of the treatment of silica in the grout simulations, and the effect of varying total dissolved carbonate concentrations. The objective of this document is to update the model for solubility controls on release of plutonium from residual waste in closed F-Area waste tanks. The update is based on new information including a new proposed grout formulation, chemical analysis of Tank 18 samples and more current thermodynamic data for plutonium and grout minerals. In addition, minor changes to the modeling of the grout chemical evolution have been made. It should be noted that the intent is to provide bounding solubilities for plutonium to be used in Performance Assessment modeling rather than trying to identify an exact concentration of plutonium in pore fluids released from a tank at any given time. This document also considers suggestions and opportunities for improvement regarding the plutonium modeling assumptions from the Plutonium Solubility Peer Review Report, LA-UR-12-00079.

  13. Tracking natural and anthropogenic origins of dissolved arsenic during surface and groundwater interaction in a post-closure mining context: Isotopic constraints.

    Science.gov (United States)

    Khaska, Mahmoud; Le Gal La Salle, Corinne; Verdoux, Patrick; Boutin, René

    2015-01-01

    Arsenic contamination of stream waters and groundwater is a real issue in Au-As mine environments. At the Salsigne Au-As mine, southern France, arsenic contamination persists after closure and remediation of the site. In this study, natural and anthropogenic arsenic inputs in surface water and groundwater are identified based on (87)Sr/(86)Sr, and δ(18)O and δ(2)H isotopic composition of water. In the wet season, downstream of the remediated zone, the arsenic contents in stream water and alluvial aquifer groundwater are high, with values in the order of 36 μg/L and 40 μg/L respectively, while upstream natural background average concentrations are around 4 μg/L. Locally down-gradient of the reclaimed area, arsenic concentrations in stream water showed 2 peaks, one during an important rainy event (101 mm) in the wet season in May, and a longer one over the dry period, reaching 120 and 110 μg/L respectively. The temporal variations in arsenic content in stream water can be explained i) during the dry season, by release of arsenic stored in the alluvial sediments through increased contribution from base flow and decreased stream flow and ii) during major rainy events, by mobilization of arsenic associated with important surface runoff. The (87)Sr/(86)Sr ratios associated with increasing arsenic content in stream waters downstream of the reclaimed area are significantly lower than that of the natural Sr inherited from Variscan formations. These low (87)Sr/(86)Sr ratios are likely to be associated with the decontaminating water treatment processes, used in the past and still at present, where CaO, produced from marine limestone and therefore showing a low (87)Sr/(86)Sr ratios, is used to precipitate Ca3(AsO4)2. The low Sr isotope signatures will then impact on the Sr isotope ratio of (1) the Ca-arsenate stored in tailing dams, (2) effluent currently produced by water treatment process and (3) groundwater draining from the overall site. Furthermore, Δ(2)H shows that the low (87)Sr/(86)Sr ratio, arsenic rich water is characterized by an evaporated signature suggesting a potential influence of water impacted by evaporation during storage in decantation lagoons. This study shows the suitability of Sr and stable isotopes of water as tracers to differentiate natural and anthropogenic sources of arsenic release or other trace elements from mining context where CaO is used for water treatment. Copyright © 2015 Elsevier B.V. All rights reserved.

  14. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site. V.1

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

  15. Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities-IAEA ASAM coordinated research programme

    International Nuclear Information System (INIS)

    Gonzales, A.; Simeonov, G.; Bennett, D.G.; Nys, V.; Ben Belfadhel, M.

    2005-01-01

    Some years ago, the IAEA successfully concluded a Coordinated Research Program (CRP) called Islam, which focussed on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities. In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near-surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

  16. Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada: For Calendar Year 2016, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States)

    2017-03-01

    This report covers the reporting period calendar year 2016 and the fourth quarter of 2015 (October 2015 through December 2016). This change to the reporting periods (i.e., fiscal to calendar) is to gain efficiencies during report development and to better align with other environmental report schedules.

  17. Development of an Insight Model for Post-closure Radiological Risks from the Disposal of High-level Waste and Spent Fuel

    Science.gov (United States)

    Kelly, M.; Carter, A.; Bailey, L.; Wellstead, M.

    2012-04-01

    Geological disposal is the UK policy for the long-term management of higher activity radioactive wastes. The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal in the UK. The approach adopted for building confidence in long-term safety of the GDF is to use multiple barriers to isolate and contain the wastes. NDA-RWMD proposes to develop a safety case based on varied and different lines of reasoning, including both quantitative aspects and qualitative safety arguments. This paper describes the development of a simplified model for high-level waste (HLW) and spent fuel (SF). Assessments of HLW and SF disposals need to reflect a number of physical and chemical processes that govern the release and transport of the disposed wastes. Physical processes include container failure, release of radionuclides from the wasteform, diffusion through bentonite barriers and transport in fractured rock. Chemical processes include solubility limitation and sorption. HLW and SF assessments are generally based on numerical models of these processes, implemented in software tools such as GoldSim. The results of such assessments can be complex to understand, especially in situations where no single release or transport process is dominant. A simplified model of the release and transport of radionuclides for disposals of HLW and SF has been developed. The objectives of the model are to identify the key physical and chemical processes that govern radiological risk, and to enable numerical estimates of risk (and other intermediate quantities) to be made. The model is based on the notion that the properties of the time-dependent model outputs can be characterised in terms of "moments". The moments are easy to compute since they are related in a simple way to the Laplace transforms of the functions under consideration. The Laplace transform method is a standard technique for solving the governing equations for release and transport of radionuclides. A number of mathematical theorems enable the moments of outputs for coupled systems to be expressed in terms of the moments of individual subcomponents. Use of this model demonstrates that approximations to peak risk and other intermediate quantities can be derived that bring out clearly the relative importance of the underlying physical and chemical processes. In this way the key processes can be identified for each radionuclide, and hence the key governing parameters can be identified. This is achieved without the need to develop or execute detailed numerical models of radionuclide release and transport. The model has been implemented in a spreadsheet, and has been tested against the results of detailed assessments undertaken by NDA-RWMD for scenarios involving disposal of HLW and SF using the Swedish (KBS-3) concept. Although such a simplified model will not replace detailed numerical models as the main tools for assessing risk, the model provides ready insight to the key controlling features of the system which can be difficult to achieve using only detailed numerical models.

  18. A model for evaluating radiological impacts on organisms other than man for use in post-closure assessments of geological repositories for radioactive wastes.

    Science.gov (United States)

    Thorn, M C; Kelly, M; Rees, J H; Sánchez-Friera, P; Calvez, M

    2002-09-01

    Bioaccumulation and dosimetric models have been developed that allow the computation of dose rates to a wide variety of plants and animals in the context of the deep geological disposal of solid radioactive wastes. These dose rates can be compared with the threshold dose rates at which significant deleterious effects have been observed in field and laboratory observations. This provides a general indication of whether effects on ecosystems could be observable, but does not quantify the level of those effects. To address this latter issue, two indicator organisms were identified and exposure-response relationships were developed for endpoints of potential interest (mortality in conifers and the induction of skeletal malformations in rodents irradiated in utero). The bioaccumulation, dosimetry and exposure-response models were implemented and used to evaluate the potential significance of radionuclide releases from a proposed deep geological repository for radioactive wastes in France. This evaluation was undertaken in the context of a programme of assessment studies being performed by the Agence nationale pour la gestion des déchets radioactifs (ANDRA).

  19. Long-term gas and brine migration at the Waste Isolation Pilot Plant: Preliminary sensitivity analyses for post-closure 40 CFR 268 (RCRA), May 1992

    International Nuclear Information System (INIS)

    1992-12-01

    This report describes preliminary probabilistic sensitivity analyses of long term gas and brine migration at the Waste Isolation Pilot Plant (WIPP). Because gas and brine are potential transport media for organic compounds and heavy metals, understanding two-phase flow in the repository and the surrounding Salado Formation is essential to evaluating long-term compliance with 40 CFR 268.6, which is the portion of the Land Disposal Restrictions of the Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act that states the conditions for disposal of specified hazardous wastes. Calculations described here are designed to provide guidance to the WIPP Project by identifying important parameters and helping to recognize processes not yet modeled that may affect compliance. Based on these analyses, performance is sensitive to shaft-seal permeabilities, parameters affecting gas generation, and the conceptual model used for the disturbed rock zone surrounding the excavation. Brine migration is less likely to affect compliance with 40 CFR 268.6 than gas migration. However, results are preliminary, and additional iterations of uncertainty and sensitivity analyses will be required to provide the confidence needed for a defensible compliance evaluation. Specifically, subsequent analyses will explicitly include effects of salt creep and, when conceptual and computational models are available, pressure-dependent fracturing of anhydrite marker beds

  20. Dry run 1: an initial examination of a procedure for the post-closure radiological risk assessment of an underground disposal facility for radioactive waste

    International Nuclear Information System (INIS)

    Thompson, B.G.J.; Broyd, T.W.

    1986-02-01

    A probabilistic risk analysis is demonstrated for a single groundwater release scenario from a repository for intermediate level wastes at a depth of about 150 metres under Harwell. This is the first stage development of an overall methodology which will eventually treat combinations of risks due to multiple release scenarios with parameter values whose uncertainty varies with time. It is shown that upper bound estimates of risk are unlikely to be useful and that the approach to radiological risk assessment based upon 'best estimates' is difficult to justify. Consequently, a full probabilistic risk analysis is necessary although further development of statistical sampling and data acquisition techniques and also of methods for the generation and analysis of site evolution scenarios, is necessary. (author)

  1. Reconfigurable Sensor Monitoring System

    Science.gov (United States)

    Alhorn, Dean C. (Inventor); Dutton, Kenneth R. (Inventor); Howard, David E. (Inventor); Smith, Dennis A. (Inventor)

    2017-01-01

    A reconfigurable sensor monitoring system includes software tunable filters, each of which is programmable to condition one type of analog signal. A processor coupled to the software tunable filters receives each type of analog signal so-conditioned.

  2. Environmental radiation monitoring system

    International Nuclear Information System (INIS)

    Kato, Tsutomu; Shioiri, Masatoshi; Sakamaki, Tsuyoshi

    2007-01-01

    Environmental radiation monitoring systems are used to measure and monitoring gamma-rays at the observation boundaries of nuclear facilities and in the surrounding areas. In recent years, however, few new nuclear facilities have been constructed and the monitoring systems shift to renewal of existing systems. In addition, in order to increase public acceptance, the facilities are being equipped with communication lines to provide data to prefectural environmental centers. In this text, we introduce the latest technology incorporated in replacement of environmental radiation monitoring systems. We also introduce a replacement method that can shorten the duration during which environmental dose rate measurement is interrupted by enabling both the replacement system and the system being replaced to perform measurements in parallel immediately before and after the replacement. (author)

  3. Ocean Disposal Site Monitoring

    Science.gov (United States)

    EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

  4. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Kono, Shigehiro.

    1990-01-01

    Among a plurality of power monitoring programs in a reactor power monitoring device, rapid response is required for a scram judging program for the power judging processing of scram signals. Therefore, the scram judging program is stored independently from other power monitoring programs, applied with a priority order, and executed in parallel with other programs, to output scram signals when the detected data exceeds a predetermined value. As a result, the capacity required for the scram judging program is reduced and the processing can be conducted in a short period of time. In addition, since high priority is applied to the scram judging program which is divided into a small capacity, it is executed at higher frequency than other programs when they are executed in parallel. That is, since the entire processings for the power monitoring program are repeated in a short cycle, the response speed of the scram signals required for high responsivity can be increased. (N.H.)

  5. Incore monitoring device

    International Nuclear Information System (INIS)

    Tai, Ichiro; Shirayama, Shin-pei; Nozaki, Shin-ichi.

    1978-01-01

    Purpose: To provide an incore monitoring device wherein both radiation monitoring and acoustic monitoring are carried out simultaneously by one detector, whereby installation of the device and signal pick-up are facilitated. Incore conditions are accurately grasped. Constitution: When a neutron is irradiated in a state where a DC voltage is applied between the electrode and the vessel in the device, an ionization current is occured by (n.γ) reaction of the transformed substance as in an ionization chamber, Accordingly, a voltage drop occurs at both ends of the resistor of the radiation signal processing system, as a result of which a neutron flux can be detected. Further, when a sound is generated in the reactor, the monitoring device bottom wall which formed by a piezoelectric element detects the sound-waves. This output signal is picked up by the acoustic signal processing system to judge the generation of sound. (Aizawa, K.)

  6. Nocturnal continuous glucose monitoring

    DEFF Research Database (Denmark)

    Bay, Christiane; Kristensen, Peter Lommer; Pedersen-Bjergaard, Ulrik

    2013-01-01

    Abstract Background: A reliable method to detect biochemical nocturnal hypoglycemia is highly needed, especially in patients with recurrent severe hypoglycemia. We evaluated reliability of nocturnal continuous glucose monitoring (CGM) in patients with type 1 diabetes at high risk of severe...

  7. ATLAS fast physics monitoring

    Indian Academy of Sciences (India)

    2012-11-16

    Nov 16, 2012 ... laboration has set up a framework to automatically process the ... ing (FPM) is complementary to data quality monitoring as problems may ... the full power of the ATLAS software framework Athena [4] and the availability of the.

  8. Lunar Health Monitor (LHM)

    Science.gov (United States)

    Lisy, Frederick J.

    2015-01-01

    Orbital Research, Inc., has developed a low-profile, wearable sensor suite for monitoring astronaut health in both intravehicular and extravehicular activities. The Lunar Health Monitor measures respiration, body temperature, electrocardiogram (EKG) heart rate, and other cardiac functions. Orbital Research's dry recording electrode is central to the innovation and can be incorporated into garments, eliminating the need for conductive pastes, adhesives, or gels. The patented dry recording electrode has been approved by the U.S. Food and Drug Administration. The LHM is easily worn under flight gear or with civilian clothing, making the system completely versatile for applications where continuous physiological monitoring is needed. During Phase II, Orbital Research developed a second-generation LHM that allows sensor customization for specific monitoring applications and anatomical constraints. Evaluations included graded exercise tests, lunar mission task simulations, functional battery tests, and resting measures. The LHM represents the successful integration of sensors into a wearable platform to capture long-duration and ambulatory physiological markers.

  9. Maine River Temperature Monitoring

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — We collect seasonal and annual temperature measurements on an hourly or quarter hourly basis to monitor habitat suitability for ATS and other species. Temperature...

  10. Equal Rights Monitor 2002

    NARCIS (Netherlands)

    Wil Portegijs; Annemarie Boelens; Saskia Keuzenkamp

    2002-01-01

    Original title: Emancipatiemonitor 2002. The Emancipation Monitor 2002 (Emancipatiemonitor 2002) provides statistics on the progress of the emancipation process, collected and analysed jointly by Statistics Netherlands (CBS) and the Netherlands Institute for Social Research/SCP. Is the

  11. Monitoring Microbially Influenced Corrosion

    DEFF Research Database (Denmark)

    Hilbert, Lisbeth Rischel

    and diffusional effects and unreliable corrosion rates, when biofilm and ferrous sulphide corrosion products cover the steel surface. Corrosion rates can be overestimated by a factor of 10 to 100 by electrochemical techniques. Weight loss coupons and ER are recommended as necessary basic monitoring techniques......Abstract Microbially influenced corrosion (MIC) of carbon steel may occur in media with microbiological activity of especially sulphate-reducing bacteria (SRB). The applicability and reliability of a number of corrosion monitoring techniques for monitoring MIC has been evaluated in experiments....... EIS might be used for detection of MIC as the appearance of very large capacitances can be attributed to the combined ferrous sulphide and biofilm formation. Capacitance correlates directly with sulphide concentration in sterile sulphide media. Keywords: Corrosion monitoring, carbon steel, MIC, SRB...

  12. Phytoplankton Monitoring Network (PMN)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Phytoplankton Monitoring Network (PMN) is a part of the National Centers for Coastal Ocean Science (NCCOS). The PMN was created as an outreach program to connect...

  13. Use of remote monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Fournel, E; Gouilloux, C

    1977-01-01

    Paper traces the development of remote monitoring devices, since their first appearance for safety purposes. Discusses their uses in coal mines: working and safety (definitions); sources and channels of information (transmission of information by automatic or verbal means); mine control stations; duties and responsibilities of persons in charge. Examines the contribution made by remote monitoring to management in production sector. Gives examples of assistance given to production management showing a very advantageous result on balance, by their use. The use of computers in real time and in batched mode is compared. Discusses their use in monitoring mine atmosphere. Very favorable results have already been obtained in France and abroad. The broadening scope and future of remote monitoring is considered.

  14. The Drought Monitor.

    Science.gov (United States)

    Svoboda, Mark; Lecomte, Doug; Hayes, Mike; Heim, Richard; Gleason, Karin; Angel, Jim; Rippey, Brad; Tinker, Rich; Palecki, Mike; Stooksbury, David; Miskus, David; Stephens, Scott

    2002-08-01

    information about drought and to receive regional and local input that is in turn incorporated into the product. This paper describes the Drought Monitor and the interactive process through which it is created.

  15. Optimization of environmental monitoring

    International Nuclear Information System (INIS)

    Winter, M.

    1986-01-01

    The routine work and tasks related to prevention in environmental monitoring of nuclear facilities range from low level methodology to the necessity of being likewise prepared to perform environmental impact measurements after nuclear incidents and accidents are presented [pt

  16. Infrastructure monitoring data management.

    Science.gov (United States)

    2015-07-01

    The primary objective of this project is to advance the development of a structural health monitoring : system (SHMS) for the Cut River Bridge. The scope includes performing an analysis from the fiber : optic strain gauge readings and making recommen...

  17. New ICPP portal monitor

    International Nuclear Information System (INIS)

    Georgeson, M.A.; Nichols, C.E.

    1981-04-01

    A large area gas filled proportional-detector portal monitor mounted in a swinging door frame has been designed and developed at the Idaho Chemical Processing Plant (ICPP). This monitor extends the sensitivity and speed of personnel contamination detection to levels equal to or exceeding that obtained using hand-held portable survey techniques. The new monitor has state-of-the-art electronics which result in rapid response, and use statistical principles in the alarm logic to reduce or eliminate spurious alarms. In addition, the evaluation of this instrument indicates that it will detect small enough quantities of U-235 in shielded containers to meet current special nuclear materials (SNM) detection standards. Simultaneous detection of very low level contamination and small quantities of SNM results in a monitor particularly useful for nuclear installations

  18. Heart failure - home monitoring

    Science.gov (United States)

    ... this page: //medlineplus.gov/ency/patientinstructions/000113.htm Heart failure - home monitoring To use the sharing features on ... your high blood pressure Fast food tips Heart failure - discharge Heart failure - fluids and diuretics Heart failure - what to ...

  19. Regional Seismic Threshold Monitoring

    National Research Council Canada - National Science Library

    Kvaerna, Tormod

    2006-01-01

    ... model to be used for predicting the travel times of regional phases. We have applied these attenuation relations to develop and assess a regional threshold monitoring scheme for selected subregions of the European Arctic...

  20. Environmental monitoring plan - environmental monitoring section. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Wilt, G.C. [ed.; Tate, P.J.; Brigdon, S.L. [and others

    1994-11-01

    This report presents the environmental monitoring plan for the Lawrence Livermore National Laboratory. A site characterization is provided along with monitoring and measurement techniques and quality assurance measures.

  1. Environmental monitoring plan - environmental monitoring section. Revision 1

    International Nuclear Information System (INIS)

    Wilt, G.C.; Tate, P.J.; Brigdon, S.L.

    1994-11-01

    This report presents the environmental monitoring plan for the Lawrence Livermore National Laboratory. A site characterization is provided along with monitoring and measurement techniques and quality assurance measures

  2. Reusable radiation monitor

    International Nuclear Information System (INIS)

    Fanselow, D.L.; Ersfeld, D.A.

    1978-01-01

    An integrating, reusable device for monitoring exposure to actinic radiation is disclosed. The device comprises a substrate having deposited thereon at least one photochromic aziridine compound which is sealed in an oxygen barrier to stabilize the color developed by the aziridine compound in response to actinic radiation. The device includes a spectral response shaping filter to transmit only actinic radiation of the type being monitored. A color standard is also provided with which to compare the color developed by the aziridine compound

  3. Monitoring of lightning discharge

    International Nuclear Information System (INIS)

    Grigor'ev, V.A.

    2001-01-01

    The paper presents a brief description of a lightning discharge recording system developed at the NPO 'Monitoring Techniques' under the direction of V.M. Moskolenko (Moscow). The system provides information about dangerous environmental occurrences such as tornados and hurricanes, making the forecast of extreme situations possible, especially in the areas of dangerous industries and objects. The created automatic system can be useful in solving the tasks relating to nuclear test monitoring. (author)

  4. Structure function monitor

    Science.gov (United States)

    McGraw, John T [Placitas, NM; Zimmer, Peter C [Albuquerque, NM; Ackermann, Mark R [Albuquerque, NM

    2012-01-24

    Methods and apparatus for a structure function monitor provide for generation of parameters characterizing a refractive medium. In an embodiment, a structure function monitor acquires images of a pupil plane and an image plane and, from these images, retrieves the phase over an aperture, unwraps the retrieved phase, and analyzes the unwrapped retrieved phase. In an embodiment, analysis yields atmospheric parameters measured at spatial scales from zero to the diameter of a telescope used to collect light from a source.

  5. Biosemiotics and ecological monitoring

    DEFF Research Database (Denmark)

    Bruni, Luis Emilio

    2001-01-01

    of the qualitative and relational aspects that can only be grasped by considering the semiotic networks operative in complex ecological and cultural systems. In this paper, it is suggested that a biosemiotic approach to ecology may prove useful for the modelling process, which in turn will allow the construction...... of meaningful monitoring systems. It is also contended that a biosemiotic approach may also serve to better integrate our understanding and monitoring of ecosystems into the cultural process of searching for (human) sustainability....

  6. Meteorological Monitoring Program

    International Nuclear Information System (INIS)

    Hancock, H.A. Jr.; Parker, M.J.; Addis, R.P.

    1994-01-01

    The purpose of this technical report is to provide a comprehensive, detailed overview of the meteorological monitoring program at the Savannah River Site (SRS) near Aiken, South Carolina. The principle function of the program is to provide current, accurate meteorological data as input for calculating the transport and diffusion of any unplanned release of an atmospheric pollutant. The report is recommended for meteorologists, technicians, or any personnel who require an in-depth understanding of the meteorological monitoring program

  7. Radioisotope dust pollution monitor

    International Nuclear Information System (INIS)

    Szepke, R.; Harasimczuk, J.; Dobrowiecki, J.

    1990-01-01

    Measuring principles and specification of two dust monitors: station-type AMIZ and portable-type PIK-10 for ambient air pollution are presented. The first one, a fully automatic instrument is destined for permanent monitoring of air pollution in preset sampling time from .25 to 24 hours. The second one was developed as a portable working model. Both instruments display their results in digital form in dust concentration units. (author)

  8. Monitor Sustainable Netherlands 2011

    International Nuclear Information System (INIS)

    2011-09-01

    The Monitor provides an image of the sustainability of the Dutch society. It shows which areas are successful and what the 'concerns for tomorrow' are from the point of view of sustainability. An analysis is conducted of how the Netherlands are doing in the fields of climate change, biodiversity, health, knowledge, graying and social cohesion. These and many other topics are discussed in this monitor by means of a number of sustainability indicators and detail analyses [mk]. [nl

  9. Monitor Sustainable Netherlands 2009

    International Nuclear Information System (INIS)

    2009-02-01

    The Monitor provides an image of the sustainability of the Dutch society. It shows which areas are successful and what the 'concerns for tomorrow' are from the point of view of sustainability. An analysis is conducted of how the Netherlands are doing in the fields of climate change, biodiversity, health, knowledge, graying and social cohesion. These and many other topics are discussed in this monitor by means of a number of sustainability indicators and detail analyses [mk] [nl

  10. Advanced Environmental Monitoring Technologies

    Science.gov (United States)

    Jan, Darrell

    2004-01-01

    Viewgraphs on Advanced Environmental Monitoring Technologies are presented. The topics include: 1) Monitoring & Controlling the Environment; 2) Illustrative Example: Canary 3) Ground-based Commercial Technology; 4) High Capability & Low Mass/Power + Autonomy = Key to Future SpaceFlight; 5) Current Practice: in Flight; 6) Current Practice: Post Flight; 7) Miniature Mass Spectrometer for Planetary Exploration and Long Duration Human Flight; 8) Hardware and Data Acquisition System; 9) 16S rDNA Phylogenetic Tree; and 10) Preview of Porter.

  11. Robotic weed monitoring

    DEFF Research Database (Denmark)

    Bochtis, Dionysis; Sørensen, Claus Aage Grøn; Jørgensen, R N

    2011-01-01

    Abstract: In this paper, an integrated management system for the planning and activation of thefield monitoring task is presented. The architecture of the system is built around a mobile roboticunit. The internet based architecture of the system includes a station unit that works as a mobileon-fa...... of the weed monitoring operation.Key words: autonomous vehicles, farm management, mission planning, route planning,sampling....

  12. Meteorological Monitoring Program

    Energy Technology Data Exchange (ETDEWEB)

    Hancock, H.A. Jr. [ed.; Parker, M.J.; Addis, R.P.

    1994-09-01

    The purpose of this technical report is to provide a comprehensive, detailed overview of the meteorological monitoring program at the Savannah River Site (SRS) near Aiken, South Carolina. The principle function of the program is to provide current, accurate meteorological data as input for calculating the transport and diffusion of any unplanned release of an atmospheric pollutant. The report is recommended for meteorologists, technicians, or any personnel who require an in-depth understanding of the meteorological monitoring program.

  13. Monitoring of radioactive wastes

    International Nuclear Information System (INIS)

    Houriet, J.Ph.

    1982-08-01

    The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements

  14. Home apnea monitor use - infants

    Science.gov (United States)

    ... this page: //medlineplus.gov/ency/patientinstructions/000755.htm Home apnea monitor use - infants To use the sharing ... portable. Why is an Apnea Monitor Used at Home? A monitor may be needed when: Your baby ...

  15. Battery Monitoring and Charging System

    National Research Council Canada - National Science Library

    Thivierge, Daniel P

    2007-01-01

    A battery monitoring device for a battery having cells grouped in modules. The device includes a monitoring circuit for each module which monitors the voltage in each cell and the overall module voltage...

  16. Photochemical Assessment Monitoring Stations (PAMS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — Photochemical Assessment Monitoring Stations (PAMS). This file provides information on the numbers and distribution (latitude/longitude) of air monitoring sites...

  17. Monitoring Forsmark - Bird monitoring in Forsmark 2012

    Energy Technology Data Exchange (ETDEWEB)

    Green, Martin [Dept of Biology, Lund Univ., Lund (Sweden)

    2013-03-15

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds directive) breeding birds in Forsmark 2002 - 2012. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2012 in the same way as in earlier years. The results from 2012 generally follow patterns recorded in earlier years. 2012 was in general a better bird year compared to 2010 and 2011 and most species (82%) showed increasing or stable numbers from 2011 to 2012. Only two species (18%) decreased in numbers between the last two years. All in all, six species (55 %, black-throated diver, honey buzzard, black grouse, ural owl, wryneck and red-backed shrike) show no significant trends since the start of the bird monitoring (2002/2003/2004 depending on species). During this period three species (27 %, white-tailed eagle, osprey and lesser spotted woodpecker) have increased in numbers while just two (18 %, capercaillie and hazelhen) have decreased. A new pair of black-throated divers was discovered in 2012 and seven resident pairs were registered. Breeding success was very good, the second best during the study period. Population development follows the national pattern, but breeding success seems to be better in Forsmark than in the country as a whole. Honey buzzards and ospreys occurred in good numbers, and breeding success for ospreys was good. No signs of successful breedings of honey buzzards were recorded, but this may mean little as no detailed monitoring of breeding success is made for this species. The white-tailed eagles had their best breeding year since the start of the SKB bird monitoring, meaning that during the last two years local breeding success has been back at the level recorded before the site investigations started. The three grouse species (black grouse, capercaillie and hazelhen) again showed somewhat varying patterns between the last two years as well as in the long run. The black grouse increased

  18. VME system monitor board

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    Much of the machinery throughout the APS will be controlled by VME based computers. In order to increase the reliability of the system, it is necessary to be able to monitor the status of each VME crate. In order to do this, a VME System Monitor was created. In addition to being able to monitor and report the status (watchdog timer, temperature, CPU (Motorola MVME 167) state (status, run, fail), and the power supply), it includes provisions to remotely reset the CPU and VME crate, digital I/O, and parts of the transition module (serial port and ethernet connector) so that the Motorla MVME 712 is not needed. The standard VME interface was modified on the System Monitor so that in conjunction with the Motorola MVME 167 a message based VXI interrupt handler could is implemented. The System Monitor is a single VME card (6U). It utilizes both the front panel and the P2 connector for I/O. The front panel contains a temperature monitor, watchdog status LED, 4 general status LEDs, input for a TTL interrupt, 8 binary inputs (24 volt, 5 volt, and dry contact sense), 4 binary outputs (dry contact, TTL, and 100 mA), serial port (electrical RS-232 or fiber optic), ethernet transceiver (10 BASE-FO or AUI), and a status link to neighbor crates. The P2 connector is used to provide the serial port and ethernet to the processor. In order to abort and read the status of the CPU, a jumper cable must be connected between the CPU and the System Monitor.

  19. Monitoring: The missing piece

    Energy Technology Data Exchange (ETDEWEB)

    Bjorkland, Ronald, E-mail: r_bjorkland@hotmail.com

    2013-11-15

    The U.S. National Environmental Policy Act (NEPA) of 1969 heralded in an era of more robust attention to environmental impacts resulting from larger scale federal projects. The number of other countries that have adopted NEPA's framework is evidence of the appeal of this type of environmental legislation. Mandates to review environmental impacts, identify alternatives, and provide mitigation plans before commencement of the project are at the heart of NEPA. Such project reviews have resulted in the development of a vast number of reports and large volumes of project-specific data that potentially can be used to better understand the components and processes of the natural environment and provide guidance for improved and efficient environmental protection. However, the environmental assessment (EA) or the more robust and intensive environmental impact statement (EIS) that are required for most major projects more frequently than not are developed to satisfy the procedural aspects of the NEPA legislation while they fail to provide the needed guidance for improved decision-making. While NEPA legislation recommends monitoring of project activities, this activity is not mandated, and in those situations where it has been incorporated, the monitoring showed that the EIS was inaccurate in direction and/or magnitude of the impact. Many reviews of NEPA have suggested that monitoring all project phases, from the design through the decommissioning, should be incorporated. Information gathered though a well-developed monitoring program can be managed in databases and benefit not only the specific project but would provide guidance how to better design and implement future activities designed to protect and enhance the natural environment. -- Highlights: • NEPA statutes created profound environmental protection legislative framework. • Contrary to intent, NEPA does not provide for definitive project monitoring. • Robust project monitoring is essential for enhanced

  20. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 2, Radiation Monitoring and Sampling

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Aerial Measurement Systems

    2012-07-31

    The FRMAC Monitoring and Sampling Manual, Volume 2 provides standard operating procedures (SOPs) for field radiation monitoring and sample collection activities that are performed by the Monitoring group during a FRMAC response to a radiological emergency.

  1. Overview of food monitors

    International Nuclear Information System (INIS)

    Saito, I.

    2014-01-01

    May 11th 2011, nuclear accidents occurred by Tohoku Region Pacific Coast Earthquake made radioisotopes overflow in reactors and spread around the environments, and it caused risk of food contamination in these areas. And May 17th 2011, Ministry of Health, Labour and Welfare Japan announced provisional regulation values of radioactive materials in food in accordance with the food sanitation act. And they had notified the municipality to corresponding foods above the provisional regulation not had to be on sale. It causes massive needs for food monitoring in Japan. For reply to these massive needs, Hitachi Aloka Medical Ltd. commercialized food monitor: CAN-OSP-NAI in cooperation with CANBERRA Industries Inc. And after this, commercialized food screening system: FSS-101 for reply more expand food monitoring in Japan. This paper introduce Hitachi Aloka Medical Ltd. products which two types of food monitor product, provisional regulation values of radioactive materials in food in accordance with the food sanitation act and with comparing with past food monitoring, needs when accident happen. I wish this is going to be good report for help to radioactive and radiation detection in the future. (author)

  2. Radioactivity monitoring in Romania

    International Nuclear Information System (INIS)

    Alexandrescu, M.; Milu, C.

    1996-01-01

    Radioactivity monitoring in Romania is based on National Regulations for Radiation Protection enforced in 1976, on other environment protection laws enforced in the last years and on the recommendations of IAEA. Accordingly two systems of radioactive monitoring are to date operational in this field: the first one is the self-control of the radioactive emissions in the environment generated by the own nuclear activities (of nuclear units like the Cernavoda NPP, the Institute of Atomic Physics at Magurele-Bucharest, the Institute for Nuclear Research at Pitesti, the R Plant at Feldioara, Uranium mining units, etc.), while the other is based on two national agencies (the National Network of Environment Radiation Monitoring of the Ministry of Waters, Forests and Environment Protection and the Network of Radiation Hygiene Laboratories of the Health Ministry). The authors review and discuss the radiation protection legislation, the structure and the organizational operations of the national monitoring systems and the co-operation of the national monitoring systems with international authorities or programmes. 3 Figs., 1 tab., 11 refs

  3. Serial Network Flow Monitor

    Science.gov (United States)

    Robinson, Julie A.; Tate-Brown, Judy M.

    2009-01-01

    Using a commercial software CD and minimal up-mass, SNFM monitors the Payload local area network (LAN) to analyze and troubleshoot LAN data traffic. Validating LAN traffic models may allow for faster and more reliable computer networks to sustain systems and science on future space missions. Research Summary: This experiment studies the function of the computer network onboard the ISS. On-orbit packet statistics are captured and used to validate ground based medium rate data link models and enhance the way that the local area network (LAN) is monitored. This information will allow monitoring and improvement in the data transfer capabilities of on-orbit computer networks. The Serial Network Flow Monitor (SNFM) experiment attempts to characterize the network equivalent of traffic jams on board ISS. The SNFM team is able to specifically target historical problem areas including the SAMS (Space Acceleration Measurement System) communication issues, data transmissions from the ISS to the ground teams, and multiple users on the network at the same time. By looking at how various users interact with each other on the network, conflicts can be identified and work can begin on solutions. SNFM is comprised of a commercial off the shelf software package that monitors packet traffic through the payload Ethernet LANs (local area networks) on board ISS.

  4. Photon beam position monitor

    Science.gov (United States)

    Kuzay, Tuncer M.; Shu, Deming

    1995-01-01

    A photon beam position monitor for use in the front end of a beamline of a high heat flux and high energy photon source such as a synchrotron radiation storage ring detects and measures the position and, when a pair of such monitors are used in tandem, the slope of a photon beam emanating from an insertion device such as a wiggler or an undulator inserted in the straight sections of the ring. The photon beam position monitor includes a plurality of spaced blades for precisely locating the photon beam, with each blade comprised of chemical vapor deposition (CVD) diamond with an outer metal coating of a photon sensitive metal such as tungsten, molybdenum, etc., which combination emits electrons when a high energy photon beam is incident upon the blade. Two such monitors are contemplated for use in the front end of the beamline, with the two monitors having vertically and horizontally offset detector blades to avoid blade "shadowing". Provision is made for aligning the detector blades with the photon beam and limiting detector blade temperature during operation.

  5. Wide area monitoring study

    International Nuclear Information System (INIS)

    Wogman, N.A.; Holdren, G.R. Jr.

    1999-01-01

    Environmental sampling can be used to complement the safeguarding of nuclear material, especially in the detection of undeclared nuclear activities. Routine monitoring of nuclear installations has provided valuable information about the fate of key signature materials within different environmental settings. The approach collates information regarding the generation of individual radiochemical signatures within different nuclear processes, the potential for release of these signatures to the environment and, the chemical form and mobility of the signatures in environmental media along which the material could migrate. Meteorological, geological and hydrological information is used to determine where to sample, what to sample, and how often to sample to provide the greatest likelihood for detection. Multiple strategies can be used to implement wide area monitoring for safeguards purposes. The most complex, and expensive of these, involves establishing extensive networks of fixed location sampling sites. The sites would be operated continuously, and would be instrumented with automated sampling, analysis, and communication equipment to relay information regarding potential anomalies to control centers in near-real time. Alternative strategies can be used to supplement fixed location monitoring equipment, especially in regions that cannot support (financially or logistically) the fixed stations. Through combinations of these various strategies, using a variety of environmental media to monitor a region, we believe that a competent network, one with a quantifiable probability for detecting undeclared nuclear activities, can be designed. While this approach cannot and should not replace other inspection and monitoring activities, it can potentially contribute valuable information to an international safeguards system. (author)

  6. Radiation monitoring device

    International Nuclear Information System (INIS)

    Sato, Toshifumi.

    1993-01-01

    The device of the present invention concerns a reactor start-up region monitor of a nuclear power plant. In an existent start-up region monitor, bias voltage is limited, if the reactor moves to a power region, in order to prevent degradation of radiation detectors. Accordingly, since the power is lower than an actual reactor power, the reactor power can not be monitored. The device of the present invention comprises a memory means for previously storing a Plateau's characteristic of the radiation detectors and a correction processing means for obtaining a correction coefficient in accordance with the Plateau's characteristic to correct and calculate the reactor power when the bias voltage is limited. With such a constitution, when the reactor power exceeds a predetermined value and the bias voltage is limited, the correction coefficient can be obtained by the memory means and the correction processing means. Corrected reactor power can also be obtained from the start-up region monitor by the correction coefficient. As a result, monitoring of the reactor power can be continued while preventing degradation of the radiation detector even if the bias voltage is limited. (I.S.)

  7. Nonintercepting emittance monitor

    International Nuclear Information System (INIS)

    Miller, R.H.; Clendenin, J.E.; James, M.B.; Sheppard, J.C.

    1983-08-01

    A nonintercepting emittance monitor is a helpful device for measuring and improving particle beams in accelerators and storage rings as it allows continuous monitoring of the beam's distribution in phase space, and perhaps closed loop computer control of the distributions. Stripline position monitors are being investigated for use as nonintercepting emittance monitors for a beam focused by a FODO array in the first 100 meters of our linear accelerator. The technique described here uses the signal from the four stripline probes of a single position monitor to measure the quadrupole mode of the wall current in the beam pipe. This current is a function of the quadrupole moment of the beam, sigma 2 /sub x/ - sigma 2 /sub y/. In general, six independent measurements of the quadrupole moment are necessary to determine the beam emittance. This technique is dependent on the characteristically large variations of sigma 2 /sub x/ - sigma 2 /sub y/ in a FODO array. It will not work in a focusing system where the beam is round at each focusing element

  8. Automatic personnel contamination monitor

    International Nuclear Information System (INIS)

    Lattin, Kenneth R.

    1978-01-01

    United Nuclear Industries, Inc. (UNI) has developed an automatic personnel contamination monitor (APCM), which uniquely combines the design features of both portal and hand and shoe monitors. In addition, this prototype system also has a number of new features, including: micro computer control and readout, nineteen large area gas flow detectors, real-time background compensation, self-checking for system failures, and card reader identification and control. UNI's experience in operating the Hanford N Reactor, located in Richland, Washington, has shown the necessity of automatically monitoring plant personnel for contamination after they have passed through the procedurally controlled radiation zones. This final check ensures that each radiation zone worker has been properly checked before leaving company controlled boundaries. Investigation of the commercially available portal and hand and shoe monitors indicated that they did not have the sensitivity or sophistication required for UNI's application, therefore, a development program was initiated, resulting in the subject monitor. Field testing shows good sensitivity to personnel contamination with the majority of alarms showing contaminants on clothing, face and head areas. In general, the APCM has sensitivity comparable to portal survey instrumentation. The inherit stand-in, walk-on feature of the APCM not only makes it easy to use, but makes it difficult to bypass. (author)

  9. Environmental monitoring programme

    International Nuclear Information System (INIS)

    1991-08-01

    During 1989 there were about 1000 premises in England and Wales authorised to discharge radioactive wastes. The majority of these premises consisted of hospitals, universities and industrial, research or manufacturing centres. Discharges from these premises when made in accordance with the strict conditions specified in their authorisations will have been of little radiological significance. In the case of nuclear sites authorisations or approvals are issued jointly by the DoE and the Ministry of Agriculture, Fisheries and Food (MAFF) known collectively as the Authorising Departments. In Wales these functions are undertaken by the Welsh Office with the support of HMIP and MAFF. The Authorising Departments specify numerical limits on the amounts of radioactivity which operators may discharge to the environment. In addition operators are required to demonstrate that the best practicable means (BPM) to minimise discharges is undertaken. Operators are also required to carry out appropriate environmental monitoring to demonstrate the effectiveness of BPM. As part of their regulatory functions the Authorising Departments undertake their own environmental monitoring programmes to act as both a check on site operator's returns and to provide independent data on the exposure of the public. HM Inspectorate of Pollution has monitored levels of radioactivity in drinking water sources for many years and published results annually. MAFF undertakes two programmes to monitor radioactivity in the aquatic environment and in terrestrial foodstuffs and publishes annual reports. Environmental monitoring programmes undertaken by both nuclear site operators and government departments are summarised. (author)

  10. Augmented fish health monitoring

    International Nuclear Information System (INIS)

    Michak, P.; Rogers, R.; Amos, K.

    1991-05-01

    The Bonneville Power Administration (BPA) initiated the Augmented Fish Health Monitoring project in 1986. This project was a five year interagency project involving fish rearing agencies in the Columbia Basin. Historically, all agencies involved with fish health in the Columbia Basin were conducting various levels of fish health monitoring, pathogen screening and collection. The goals of this project were; to identify, develop and implement a standardized level of fish health methodologies, develop a common data collection and reporting format in the area of artificial production, evaluate and monitor water quality, improve communications between agencies and provide annual evaluation of fish health information for production of healthier smolts. This completion report will contain a project evaluation, review of the goals of the project, evaluation of the specific fish health analyses, an overview of highlights of the project and concluding remarks. 8 refs., 1 fig., 4 tabs

  11. CMS Space Monitoring

    Science.gov (United States)

    Ratnikova, N.; Huang, C.-H.; Sanchez-Hernandez, A.; Wildish, T.; Zhang, X.

    2014-06-01

    During the first LHC run, CMS stored about one hundred petabytes of data. Storage accounting and monitoring help to meet the challenges of storage management, such as efficient space utilization, fair share between users and groups and resource planning. We present a newly developed CMS space monitoring system based on the storage metadata dumps produced at the sites. The information extracted from the storage dumps is aggregated and uploaded to a central database. A web based data service is provided to retrieve the information for a given time interval and a range of sites, so it can be further aggregated and presented in the desired format. The system has been designed based on the analysis of CMS monitoring requirements and experiences of the other LHC experiments. In this paper, we demonstrate how the existing software components of the CMS data placement system, PhEDEx, have been re-used, dramatically reducing the development effort.

  12. Copilot: Monitoring Embedded Systems

    Science.gov (United States)

    Pike, Lee; Wegmann, Nis; Niller, Sebastian; Goodloe, Alwyn

    2012-01-01

    Runtime verification (RV) is a natural fit for ultra-critical systems, where correctness is imperative. In ultra-critical systems, even if the software is fault-free, because of the inherent unreliability of commodity hardware and the adversity of operational environments, processing units (and their hosted software) are replicated, and fault-tolerant algorithms are used to compare the outputs. We investigate both software monitoring in distributed fault-tolerant systems, as well as implementing fault-tolerance mechanisms using RV techniques. We describe the Copilot language and compiler, specifically designed for generating monitors for distributed, hard real-time systems. We also describe two case-studies in which we generated Copilot monitors in avionics systems.

  13. Neutron flux monitoring device

    International Nuclear Information System (INIS)

    Goto, Yasushi; Mitsubori, Minehisa; Ohashi, Kazunori.

    1997-01-01

    The present invention provides a neutron flux monitoring device for preventing occurrence of erroneous reactor scram caused by the elevation of the indication of a start region monitor (SRM) due to a factor different from actual increase of neutron fluxes. Namely, judgement based on measured values obtained by a pulse counting method and a judgment based on measured values obtained by a Cambel method are combined. A logic of switching neutron flux measuring method to be used for monitoring, namely, switching to an intermediate region when both of the judgements are valid is adopted. Then, even if the indication value is elevated based on the Cambel method with no increase of the counter rate in a neutron source region, the switching to the intermediate region is not conducted. As a result, erroneous reactor scram such as 'shorter reactor period' can be avoided. (I.S.)

  14. CMS Space Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Ratnikova, N. [Fermilab; Huang, C.-H. [Fermilab; Sanchez-Hernandez, A. [CINVESTAV, IPN; Wildish, T. [Princeton U.; Zhang, X. [Beijing, Inst. High Energy Phys.

    2014-01-01

    During the first LHC run, CMS stored about one hundred petabytes of data. Storage accounting and monitoring help to meet the challenges of storage management, such as efficient space utilization, fair share between users and groups and resource planning. We present a newly developed CMS space monitoring system based on the storage metadata dumps produced at the sites. The information extracted from the storage dumps is aggregated and uploaded to a central database. A web based data service is provided to retrieve the information for a given time interval and a range of sites, so it can be further aggregated and presented in the desired format. The system has been designed based on the analysis of CMS monitoring requirements and experiences of the other LHC experiments. In this paper, we demonstrate how the existing software components of the CMS data placement system, PhEDEx, have been re-used, dramatically reducing the development effort.

  15. Monitoring with Data Automata

    Science.gov (United States)

    Havelund, Klaus

    2014-01-01

    We present a form of automaton, referred to as data automata, suited for monitoring sequences of data-carrying events, for example emitted by an executing software system. This form of automata allows states to be parameterized with data, forming named records, which are stored in an efficiently indexed data structure, a form of database. This very explicit approach differs from other automaton-based monitoring approaches. Data automata are also characterized by allowing transition conditions to refer to other parameterized states, and by allowing transitions sequences. The presented automaton concept is inspired by rule-based systems, especially the Rete algorithm, which is one of the well-established algorithms for executing rule-based systems. We present an optimized external DSL for data automata, as well as a comparable unoptimized internal DSL (API) in the Scala programming language, in order to compare the two solutions. An evaluation compares these two solutions to several other monitoring systems.

  16. Part 6: Forest monitoring

    International Nuclear Information System (INIS)

    1997-01-01

    In this part the results of forest monitoring on Hungarian and Slovak territory are presented. The two countries examine the growth and the health conditions of trees in similar ways. The monitoring sites in the Slovak and Hungarian territories, included in the joint monitoring, are shown on figure. The Slovak Party has already evaluated the wood yield data for 1996, the weekly girth growth observations in 1996 were not performed yet. So far on the Hungarian side only the weekly girth growth data are available for the year 1996, the wood yield data for 1996 are being processed. In the evaluation of Hungarian side only the results obtained for the period from 1992 to 1995 were analysed. Moreover, on the Slovak side an evaluation of the health conditions of trees based on aerial was carried out. The Hungarian party did not carried out such a survey, therefore the evaluation is based only on field (on-the-spot) observations

  17. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  18. MCO Monitoring Plan

    International Nuclear Information System (INIS)

    SEXTON, R.A.

    2000-01-01

    The basis for development of the Multi-Canister Overpack (MCO) Monitoring Plan was established in HNF-3312, MCO Monitoring Activity Description (Sexton 1998), with the following specific objectives: The safety of Spent Nuclear Fuel (SNF) Project processes for retrieving, packaging, handling, conditioning, and storing the N Reactor spent nuclear fuel has been demonstrated by conservative analyses, as compiled in the project safety basis and licensing documentation. Appropriate quality assurance and independent checking of engineering, fabrication, and construction are being applied, and there will be in-process monitoring and verification of MCO loading and conditioning actions. Once the MCOs have been placed in storage, there is no safety requirement, regulatory requirement, or precedent to monitor them. Although not required, a monitoring program which would acquire data for use by Process Engineering is considered valuable for several reasons (Sexton 1998): Good engineering practice--Acquiring data at a reasonable cost that may be useful in developing a fuller understanding of the behavior of an engineered system is good engineering practice. Actual data on full scale MCOs is otherwise unavailable--Previous investigations have been limited to small fuel samples or simulant prototypes and have been relatively short in duration. MCO monitoring can provide data on large loads of actual fuel, in full-scale configuration, over longer time periods. Additional knowledge of the fuel type may prove valuable in future analyses or applications. On that basis, a program with two components was planned: The pressure/temperature/gas composition relationships will be observed in a limited number of MCOs during the first two years in storage. The remaining MCOs will incorporate a simple means to confirm at any time in the future, that internal pressure of the MCO is not high enough to threaten its structural integrity. The MCOs are likely to be stored for 40 years or longer

  19. Foodstuffs, radionuclides, monitoring

    International Nuclear Information System (INIS)

    Denisikov, A.I.

    2000-01-01

    Radionuclide contamination of water and food stuffs as a result of the Chernobyl accident and permissible contents of 90 Sr and 137 Cs are considered in brief. A method of radiation monitoring of food stuffs and water for the radionuclides mentioned is suggested. The method permits employment of the simplest and cheapest radiometric equipment for analysis, whole the high degree of radionuclide concentration using fiber sorbents permits using the instrumentation without expensive shields against external radiation. A description of ion-exchange unit for radiation monitoring of liquid samples of food stuffs or water, is provided [ru

  20. CLIC Luminosity Monitoring

    CERN Document Server

    Apyan, Armen; Gschwendtner, Edda; Lefevre, Thibault; Tygier, Sam; Appleby, Robert B

    2012-01-01

    The CLIC post-collision line is designed to transport the un-collided beams and the products of the collided beams with a total power of 14 MW to the main beam dump. Luminosity monitoring for CLIC is based on high energy muons produced by beamstrahlung photons in the main dump. Threshold Cherenkov counters are proposed for the detection of these muons. The expected rates and layout for these detectors is presented. Another method for luminosity monitoring is to directly detect the beamstrahlung photons in the post-collision line. Full Monte Carlo simulation has been performed to address its feasibility.

  1. Soil monitoring instrumentation

    International Nuclear Information System (INIS)

    Umbarger, C.J.

    1980-01-01

    The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities as well as wastes from old waste burial ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. Because of the topic of this workshop, only the assay instrumentation applied specifically to soil monitoring will be discussed here. Four types of soil monitors are described

  2. Monitors for TJII

    International Nuclear Information System (INIS)

    Tafalla, D.; Tabares, F.L.; Ortiz, P.; Lopez-Sanchez, A.; Martin Fresno, L.M.; Sanchez Sarabia, E.; Encabo, J.

    1998-06-01

    A set of monitors for the measurement of Hα radiation (656.3 nm) have been installed in TJ-II stellarator. The detectors are placed directly on the windows of the chamber and they are built using Si photodiodes and interference filters with a compact design that make easy their handling and maintenance. Here we describe the mechanical and electrical design of the monitors, their position in TJ-II and some examples of their working during the first discharges of the machine. (Author) 3 refs

  3. Intraoperative cranial nerve monitoring.

    Science.gov (United States)

    Harper, C Michel

    2004-03-01

    The purpose of intraoperative monitoring is to preserve function and prevent injury to the nervous system at a time when clinical examination is not possible. Cranial nerves are delicate structures and are susceptible to damage by mechanical trauma or ischemia during intracranial and extracranial surgery. A number of reliable electrodiagnostic techniques, including nerve conduction studies, electromyography, and the recording of evoked potentials have been adapted to the study of cranial nerve function during surgery. A growing body of evidence supports the utility of intraoperative monitoring of cranial nerve nerves during selected surgical procedures.

  4. Routine sanitary radiation monitoring

    International Nuclear Information System (INIS)

    Marej, A.N.

    1984-01-01

    Hygienic bases and organization principles of radiation monitoring realized in the process of operation of nuclear power engineering enterprises are considered. The monitoring is aimed at prevention from a negative effect of ionizing radiations on public heath. It is achieved by solution of the following tasks: realization of control over radioactive waste disposal into environment, control over the level of radioactive substance content in evironmental objects, control over external and internal irradiation of population assessment of environmental radiactivity of certain regions and of the territory of the country with the subsequent informing the corresponding organizations and population

  5. Car monitoring information systems

    Directory of Open Access Journals (Sweden)

    Alica KALAŠOVÁ

    2008-01-01

    Full Text Available The objective of this contribution is to characterize alternatives of information systems used for managing, processing and evaluation of information related to company vehicles. Especially we focus on logging, transferring and processing of on-road vehicle movement information in inland and international transportation. This segment of company information system has to monitor the car movement – actively or passively – according to demand of the company and after the processing it has to evaluate and give the complex monitoring of a situation of all the company vehicles to the controller.

  6. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Environmental monitoring of nuclear facilities is part of general monitoring for environmental radioactivity all over the territory of the Federal Republic of Germany. General principles of environmental monitoring were formulated by the ICRP in 1965. In 1974 guidelines for measures of monitoring the environment of NPP incorporating LWR were drafted, which helped to standardize environmental monitoring programs. Since 1958, data on environmental radioactivity from measurements by authorized laboratories have been published in reports. (DG)

  7. Radiation monitoring around accelerator facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Shinichi [High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki (Japan)

    2000-07-01

    The present status of a network of radiation monitors (NORM) working at KEK is described in detail. NORM consists of there parts; stand-alone radiation monitors (SARM), local-monitoring stations (STATION) and a central data-handling system (CENTER). NORM has developed to a large-scaled monitoring system in which more than 250 SARMs are under operation for monitoring the radiation fields and radioactivities around accelerators in KEK. (author)

  8. Monitor veiligheid en vertrouwen

    NARCIS (Netherlands)

    Degen, A.J.G.; Huveneers, S.G.; Kooij, R.E.

    2012-01-01

    Doelstelling: Om meer inzicht te krijgen in de risico’s bij het gebruik van ICT-diensten en de relatie met het vertrouwen van consumenten en bedrijven, is besloten te werken aan een monitor ‘Vertrouwen in ICT’. Dit onderzoek heeft als doel de eerste noodzakelijke stap te zetten: het bouwen van een

  9. Icinga Monitoring System Interface

    CERN Document Server

    Neculae, Alina Georgiana

    2014-01-01

    The aim of this project is to develop a web interface that would be used by the Icinga monitoring system to manage the CMS online cluster, in the experimental site. The interface would allow users to visualize the information in a compressed and intuitive way, as well as modify the information of each individual object and edit the relationships between classes.

  10. Intracranial Pressure Monitoring

    DEFF Research Database (Denmark)

    Raboel, P H; Bartek, J; Andresen, M

    2012-01-01

    Monitoring of intracranial pressure (ICP) has been used for decades in the fields of neurosurgery and neurology. There are multiple techniques: invasive as well as noninvasive. This paper aims to provide an overview of the advantages and disadvantages of the most common and well-known methods...

  11. Automated Vehicle Monitoring System

    OpenAIRE

    Wibowo, Agustinus Deddy Arief; Heriansyah, Rudi

    2014-01-01

    An automated vehicle monitoring system is proposed in this paper. The surveillance system is based on image processing techniques such as background subtraction, colour balancing, chain code based shape detection, and blob. The proposed system will detect any human's head as appeared at the side mirrors. The detected head will be tracked and recorded for further action.

  12. The ozone monitoring instrument

    NARCIS (Netherlands)

    Levelt, P.F.; Oord, G.H.J. van den; Dobber, M.R.; Mälkki, A.; Visser, H.; Vries, J. de; Stammes, P.; Lundell, J.O.V.; Saari, H.

    2006-01-01

    The Ozone Monitoring Instrument (OMI) flies on the National Aeronautics and Space Adminsitration's Earth Observing System Aura satellite launched in July 2004. OMI is a ultraviolet/visible (UV/VIS) nadir solar backscatter spectrometer, which provides nearly global coverage in one day with a spatial

  13. Ballast Water Self Monitoring

    Science.gov (United States)

    2011-11-01

    Hydrogen peroxide  Menadione /Vitamin K The efficacy of these processes varies by water conditions such as pH, temperature and, most significantly...Hydrocyclone power consumption, voltage and current Hydrocyclone power consumption, voltage and current Menadione /Vitamin K Menadione Chemical analysis...and treatment monitoring - Menadione /Vitamin K concentration at injection - Menadione /Vitamin K dosage and usage - Menadione /Vitamin K

  14. CODAS object monitoring service

    International Nuclear Information System (INIS)

    Wheatley, M.R.; Rainford, M.

    2001-01-01

    The primary Control and Data Acquisition System (CODAS) of JET is based on a TCP/IP network of more than 150 computers. The CODAS computers provide the JET machine control and data acquisition for over 70,000 digital and analog signals. The Object Monitoring Service (OMS) is used by applications for monitoring objects for presentation to the JET machine operators and for the operation of individual software components (such as valve state, access control, mimic definition changes and internal data distribution). Each server typically handles connections from around 60 clients monitoring upwards of 2000 objects. Some servers have over 150 clients and 5000 objects. Acquisition libraries are dynamically linked into a running server as required either to acquire data values for objects or to forward requests to other OMS servers. A mechanism involving dynamic linking allows new libraries to be integrated without stopping or changing running software. OMS provides a very reliable and highly successful 'data-type independent' means of monitoring many different objects. It allows applications to take advantage of new data sources, without the need to change existing code

  15. Personal radiation monitoring

    International Nuclear Information System (INIS)

    Julius, H.W.

    1976-01-01

    This report reviews the context of a primary university course in individual radiation monitoring. A brief account of the regulations and permissible doses is given. The principles and design of film dosemeters, thermoluminescent dosemeters and the whole-body counting technique are treated

  16. Pump monitoring and analysis

    International Nuclear Information System (INIS)

    Guy, K.R.

    1992-01-01

    The paper describes how to set up a periodic vibration monitoring program implemented with electronic data loggers. Acquired data will be analyzed and evaluated to determine pump condition. Periodic measuring frequency, reporting procedures, and conditions of mechanical components are discussed in detail based on the actual case study

  17. AIR RADIOACTIVITY MONITOR

    Science.gov (United States)

    Bradshaw, R.L.; Thomas, J.W.

    1961-04-11

    The monitor is designed to minimize undesirable background buildup. It consists of an elongated column containing peripheral electrodes in a central portion of the column, and conduits directing an axial flow of radioactively contaminated air through the center of the column and pure air through the annular portion of the column about the electrodes. (AEC)

  18. Ractor stability monitor

    International Nuclear Information System (INIS)

    Takeuchi, Yutaka.

    1991-01-01

    A stability monitor for a BWR type reactor determines the index of stability by statistic processing of signals from an average power region monitor or the like, but it takes much time and the reliability thereof is not always high. Then, parameters such as reactor core power are measured on every sampling periods as observation data and pretreatments such as normalization are applied successively, to obtain monitored amount and store them successively. Differentiation coefficient relative to time are calculated by using the observed amount at present and that one sample period before, to evaluate on a phasal plane using the amount of observation and the differentiation coefficient with time on the axes of coordinate. As a result, information relative to the stability can be represented accurately, thereby enabling to monitor the stability at a high accuracy. Further, judgement for the condition considering the amplitude is conducted upon oscillation, thereby enabling to conduct control operation certainly. The operation in a region where it has been limited under great caution can be conducted appropriately and safely, enabling to conduct controlled operation of excellent economical property. (N.H.)

  19. Community Radiation Monitoring Program

    International Nuclear Information System (INIS)

    Lucas, R.P. Jr.; Cooper, E.N.; McArthur, R.D.

    1990-05-01

    The Community Radiation Monitoring Program began its ninth year in the summer of 1989, continuing as an essential portion of the Environmental Protection Agency's long-standing off-site monitoring effort. It is a cooperative venture between the Department of Energy (DOE), the Environmental Protection Agency (EPA), the University of Utah (U of U), and the Desert Research Institute (DRI) of the University of Nevada System. The objectives of the program include enhancing and augmenting the collection of environmental radiation data at selected sites around the Nevada Test Site (NTS), increasing public awareness of that effort, and involving, in as many ways as possible, the residents of the off-site area in these and other areas related to testing nuclear weapons. This understanding and improved communication is fostered by hiring residents of the communities where the monitoring stations are located as program representatives, presenting public education forums in those and other communities, disseminating information on radiation monitoring and related subjects, and developing and maintaining contacts with local citizens and elected officials in the off-site areas. 8 refs., 4 figs., 4 tabs

  20. Bolt Stress Monitor

    Science.gov (United States)

    1978-01-01

    In photo, an engineer is using a new Ultrasonic Bolt Stress Monitor developed by NASA's Langley Research Center to determine whether a bolt is properly tightened. A highly accurate device, the monitor is an important tool in construction of such structures as pressure vessels, bridges and power plants, wherein precise measurement of the stress on a tightened bolt is critical. Overtightened or undertightened bolts can fail and cause serious industrial accidents or costly equipment break-downs. There are a number of methods for measuring bolt stress. Most widely used and least costly is the torque wrench, which is inherently inaccurate; it does not take into account the friction between nut and bolt, which has an influence on stress. At the other end of the spectrum, there are accurate stress-measuring systems, but they are expensive and not portable. The battery-powered Langley monitor fills a need; it is inexpensive, lightweight, portable and extremely accurate because it is not subject to friction error. Sound waves are transmitted to the bolt and a return signal is received. As the bolt is tightened, it undergoes changes in resonance due to stress, in the manner that a violin string changes tone when it is tightened. The monitor measures the changes in resonance and provides a reading of real stress on the bolt. The device, patented by NASA, has aroused wide interest and a number of firms have applied for licenses to produce it for the commercial market.

  1. Air Quality Monitoring Programme

    DEFF Research Database (Denmark)

    Kemp, K.; Palmgren, F.

    The Danish Air Quality Monitoring Programme (LMP IV) has been revised in accordance with the Framework Directive and the first three daughter directives of SO2, NOx/NO2, PM10, lead, benzene, CO and ozone. PM10 samplers are under installation and the installation will be completed during 2002...

  2. Environmental monitoring programme

    International Nuclear Information System (INIS)

    Schroeder, H.J.

    1981-01-01

    The tasks of the radiation protection department at a nuclear power plant are mentioned and described. Special attention is given to the environmental monitoring program. The consequences from regulations, the different items in the program and the results are described. (orig./RW)

  3. (Multiawesome) Multispectral Multiprobe Monitoring

    International Nuclear Information System (INIS)

    Scheibelhofer, Otto; Hohl, Roland; Sacher, Stefan; Menezes, Jose; Khinast, Johannes

    2012-01-01

    Full text: In the food and pharmaceutical industry, near-infrared spectroscopy is a more and more frequently used tool for process monitoring. This is motivated by its fast and non-invasive nature. Further on, no extensive sample preparation is needed, enabling the use as an online process analytical tool. However, this comes with the drawback of large amounts of correlated data, often influenced by many external factors. Therefore, a lot of effort has to be invested in the correct use of mathematical tools to extract the information of interest. Here we put to use a new prototype NIR spectrometer (by EVK, Raaba, Austria), based on an established chemical imaging system, to enable the reading of several attached probes at the same time. However, even when investigating the same sample, there are slight differences from one probe to another. On the one hand, this is caused by their different eld of view; on the other hand, these are to be avoided disturbances, on nominally similar probes. Therefore, it is necessary to identify these disturbances and consider them in the spectral interpretation. This should allow the monitoring of processes at different positions, as well as the simultaneous monitoring of different processes, with one measurement system. In this work, data from the prototype system are presented in use on a pharmaceutical process. It is shown how to overcome some of the appearing difficulties when dealing with a multiprobe system, in order to enable fast and robust process monitoring, and render process control. (author)

  4. Poverty monitor 2007

    NARCIS (Netherlands)

    Cok Vrooman; Stella Hoff; Ferdy Otten; Wim Bos

    2007-01-01

    Original title: Armoedemonitor 2007. The Poverty Monitor 2007 contains the most up-to-date figures on poverty in the Netherlands. The data were collected and analysed by the Netherlands Institute for Social Research/SCP in collaboration with Statistics Netherlands (CBS). The report describes

  5. Poverty Monitor 2003

    NARCIS (Netherlands)

    Cok Vrooman; Henk-Jan Dirven; Stella Hoff; Ger Linden

    2003-01-01

    Original title: Armoedemonitor 2003. The Poverty Monitor 2003 (Armoedemonitor 2003) contains the most up-to-date figures on poverty in the Netherlands. The data were collected and analysed by the Netherlands Institute for Social Research/SCP and Statistics Netherlands (CBS). The extent of and

  6. CERN GSM monitoring system

    CERN Multimedia

    Ghabrous Larrea, C

    2009-01-01

    As a result of the tremendous development of GSM services over the last years, the number of related services used by organizations has drastically increased. Therefore, monitoring GSM services is becoming a business critical issue in order to be able to react appropriately in case of incident. In order to provide with GSM coverage all the CERN underground facilities, more than 50 km of leaky feeder cable have been deployed. This infrastructure is also used to propagate VHF radio signals for the CERN’s fire brigade. Even though CERN’s mobile operator monitors the network, it cannot guarantee the availability of GSM services, and for sure not VHF services, where signals are carried by the leaky feeder cable. So, a global monitoring system has become critical to CERN. In addition, monitoring this infrastructure will allow to characterize its behaviour over time, especially with LHC operation. Given that commercial solutions were not yet mature, CERN developed a system based on GSM probes and an application...

  7. Poverty Monitor 1998

    NARCIS (Netherlands)

    1998-01-01

    Original title: Armoedemonitor 1998. The Poverty Monitor 1998 (Armoedemonitor 1998) presents a complete and up-to-date picture of poverty in the Netherlands. It is intended to provide a factual basis for the current debate on poverty. The Netherlands Institute for Social Research/SCP and

  8. Poverty Monitor 2001

    NARCIS (Netherlands)

    2001-01-01

    Original title: Armoedemonitor 2001. The Poverty Monitor 2001 (Armoedemonitor 2001) contains the most up-to-date figures on poverty in the Netherlands. The data were collected and analysed by the Netherlands Institute for Social Research/SCP and Statistics Netherlands (CBS). The extent of and

  9. Poverty Monitor 1999

    NARCIS (Netherlands)

    1999-01-01

    Original title: Armoedemonitor 1999. The Poverty Monitor 1999 (Armoedemonitor 1999) presents as complete and up-to-date a picture as possible of poverty in the Netherlands, and thus provides a factual basis for the debate on poverty. The Netherlands Institute for Social Research/SCP

  10. Poverty Monitor 2000

    NARCIS (Netherlands)

    2000-01-01

    Original title: Armoedemonitor 2000. The Poverty Monitor 2000 (Armoedemonitor 2000) contains the most up-to-date figures on poverty in the Netherlands. The data were collected and analysed by the Netherlands Institute for Social Research/SCP and Statistics Netherlands (CBS). The extent of

  11. Beam profile monitor

    International Nuclear Information System (INIS)

    Krausse, G.J.; Gram, P.A.M.

    1978-05-01

    A system used to monitor secondary beam profiles at the LAMPF Linac for channel tune-up and diagnostics is described. The multiwire proportional chamber design is discussed, and descriptions and drawings of the gate card, the amplifier/multiplexer card, the output amplifier card, and the overall system are given

  12. LGBT Monitor 2016

    NARCIS (Netherlands)

    Lisette Kuyper

    2016-01-01

    Original title: LHBT-monitor 2016 What is the public attitude today towards lesbian, homosexual, bisexual and transgender (LGBT) persons? What do large-scale population surveys enable us to say about their position in society? The Netherlands is one of the most positive countries in Europe in its

  13. Value activity monitoring

    NARCIS (Netherlands)

    de Alencar Silva, P.

    2013-01-01

    Current value modeling ontologies are grounded on the economic premise that profit sharing is a critical condition to be assessed during the configuration of a value constellation. Such a condition ought to be reinforced through a monitoring mechanism design, since a value model expresses only

  14. Plant monitoring device

    International Nuclear Information System (INIS)

    Moriyama, Kunio.

    1991-01-01

    The monitoring device of the present invention is most suitable to early detection for equipment abnormality, or monitoring of state upon transient conditions such as startup and shutdown of an electric power plant, a large-scaled thermonuclear device and an accelerator plant. That is, in existent moitoring devices, acquired data are stored and the present operation states are monitored in comparison. A plant operation aquisition data reproduction section is disposed to the device. From the past operation conditions stored in the plant operation data aquisition reproducing section, the number of operation cycles that agrees with the present plant operation conditions is sought, to determine the agreed aquired data. Since these aquired data are time sequential data measured based on the standard time determined by the operation sequence, aquired data can be reproduced successively on every sample pitches. With such a constitution, aquired data under the same operation conditions as the present conditions are displayed together with the measured data. Accordingly, accurate monitoring can be conducted from the start-up to the shutdown of the plant. (I.S.)

  15. Monitoring selected arthropods

    Science.gov (United States)

    R. Chris Stanton; David J. Horn; Foster F. Purrington; John W. Peacock; Eric H. Metzler

    2003-01-01

    Arthropod populations were sampled in four study areas in southern Ohio in 1995 to document patterns of arthropod diversity and establish a baseline dataset for long-term monitoring in mixed-oak forests. Pitfall, Malaise, and blacklight traps were operated in 12 treatment units from May through September. Several insect groups were selected for detailed study due to...

  16. Luminosity monitor at PEP

    International Nuclear Information System (INIS)

    Fox, J.D.; Franklin, M.E.B.

    1981-02-01

    The luminosity monitor system utilized by the MKII Detector and by the PEP operators is described. This system processes information from 56 photomultipliers and calculates independent luminosities for each of the 3 colliding bunches in PEP. Design considerations, measurement techniques, and sources of error in the luminosity measurement are discussed

  17. Nuclear reactor monitoring device

    International Nuclear Information System (INIS)

    Mihashi, Ishi; Honma, Hitoshi.

    1993-01-01

    The monitoring device of the present invention comprises a reactor core/reactor system data measuring and controlling device, a radioactivity concentration calculation device for activated coolants for calculating a radioactivity concentration of activated coolants in a main steam and reactor water by using an appropriate physical model, a radioactivity concentration correlation and comparison device for activated coolants for comparing correlationship with a radiation dose and an abnormality alarm device. Since radioactivity of activated primary coolants is monitored at each of positions in the reactor system and occurrence of leakage and the amount thereof from a primary circuit to a secondary circuit is monitored if the reactor has secondary circuit, integrity of the reactor system can be ensured and an abnormality can be detected rapidly. Further, radioactivity concentration of activated primary circuit coolants, represented by 16 N or 15 C, is always monitored at each of positions of PWR primary circuits. When a heat transfer pipe is ruptured in a steam generator, leakage of primary circuit coolants is detected rapidly, as well as the amount of the leakage can be informed. (N.H.)

  18. EMon: Embodied Monitorization

    Science.gov (United States)

    Carneiro, Davide; Novais, Paulo; Costa, Ricardo; Gomes, Pedro; Neves, José

    The amount of seniors in need of constant care is rapidly rising: an evident consequence of population ageing. There are already some monitorization environments which aim to monitor these persons while they remain at home. This, however, although better than delocalizing the elder to some kind of institution, may not still be the ideal solution, as it forces them to stay inside the home more than they wished, as going out means lack of accompaniment and a consequent sensation of fear. In this paper we propose EMon: a monitorization device small enough to be worn by its users, although powerful enough to provide the higher level monitorization systems with vital information about the user and the environment around him. We hope to allow the representation of an intelligent environment to move with its users, instead of being static, mandatorily associated to a single physical location. The first prototype of EMon, as presented in this paper, provides environmental data as well as GPS coordinates and pictures that are useful to describe the context of its user.

  19. Neuropharmacology of performance monitoring.

    Science.gov (United States)

    Jocham, Gerhard; Ullsperger, Markus

    2009-01-01

    Adaptive, goal-directed behavior requires that organisms evaluate their actions in terms of their outcomes. Neuroimaging studies show that unfavorable outcomes or situations with high level of conflict engage the posterior medial frontal cortex (pMFC). Recording of event-related potentials revealed that these situations are accompanied by a negative deflection, the so-called error-related negativity (ERN), which appears after an erroneous response or after negative feedback. Both activation of the pMFC and the ERN are thought to represent a signal that indicates the need for behavioral adjustment, and to recruit other brain regions that implement these adjustments. While many fMRI and EEG studies have shed light on the anatomical structures and the cognitive processes involved in performance monitoring, only very recently have researchers begun to investigate the underlying neurochemical mechanisms. Drawing on the putative involvement of dopamine (DA) neurons in coding a reward prediction error, an influential theory has ascribed a pivotal role to DA in performance monitoring. However, although important, DA is certainly not the only neuromodulator involved. Recent studies point to a role for serotonin, norepinephrine and GABA, but also for adenosine in performance monitoring. Here, we review the evidence for neurotransmitter effects on this function in humans. In this light, we critically discuss currently debated models of performance monitoring and potential alternatives.

  20. Monitoring of operating processes

    International Nuclear Information System (INIS)

    Barry, R.F.

    1981-01-01

    Apparatus is described for monitoring the processes of a nuclear reactor to detect off-normal operation of any process and for testing the monitoring apparatus. The processes are evaluated by response to their paramters, such as temperature, pressure, etc. The apparatus includes a pair of monitoring paths or signal processing units. Each unit includes facilities for receiving on a time-sharing basis, a status binary word made up of digits each indicating the status of a process, whether normal or off-normal, and test-signal binary words simulating the status binary words. The status words and test words are processed in succession during successive cycles. During each cycle, the two units receive the same status word and the same test word. The test words simulate the status words both when they indicate normal operation and when they indicate off-normal operation. Each signal-processing unit includes a pair of memories. Each memory receives a status word or a test word, as the case may be, and converts the received word into a converted status word or a converted test word. The memories of each monitoring unit operate into a non-coincidence which signals non-coincidence of the converted word out of one memory of a signal-processing unit not identical to the converted word of the other memory of the same unit

  1. Community Radiation Monitoring Program

    International Nuclear Information System (INIS)

    Cooper, E.N.

    1993-05-01

    The Community Radiation Monitoring Program (CRMP) is a cooperative effort between the US Department of Energy (DOE); the US Environmental Protection Agency (EPA); the Desert Research Institute (DRI), a division of the University and Community College System of Nevada and the Nuclear Engineering Laboratory of the University of Utah (UNEL). The twelfth year of the program began in the fall of 1991, and the work continues as an integral part of the DOE-sponsored long-term offsite radiological monitoring effort that has been conducted by EPA and its predecessors since the inception of nuclear testing at the Nevada Test Site (NTS). The program began as an outgrowth of activities that occurred during the Three Mile Island incident in 1979. The local interest and public participation that took place there were thought to be transferrable to the situation at the NTS, so, with adaptations, that methodology was implemented for this program. The CRMP began by enhancing and centralizing environmental monitoring and sampling equipment at 15 communities in the existing EPA monitoring network, and has since expanded to 19 locations in Nevada, Utah and California. The primary objectives of this program are still to increase the understanding by the people who live in the area surrounding the NTS of the activities for which DOE is responsible, to enhance the performance of radiological sampling and monitoring, and to inform all concerned of the results of these efforts. One of the primary methods used to improve the communication link with people in the potentially impacted area has been the hiring and training of local citizens as station managers and program representatives in those selected communities in the offsite area. These managers, active science teachers wherever possible, have succeeded, through their training, experience, community standing, and effort, in becoming a very visible, able and valuable asset in this link

  2. Monitoring volatile anaesthetic agents

    International Nuclear Information System (INIS)

    Russell, W.J.

    2000-01-01

    Full text: The methods that have been used for monitoring volatile anaesthetic agents depend on some physical property such as Density, Refractometry, Mass, Solubility, Raman scattering, or Infra-red absorption. Today, refractometry and infra-red techniques are the most common. Refractometry is used for the calibration of vaporizers. All anaesthetic agents increase the refractive index of the carrier gas. Provided the mixture is known then the refractive change measures the concentration of the volatile anaesthetic agent. Raman Scattering is when energy hits a molecule a very small fraction of the energy is absorbed and re-emitted at one or more lower frequencies. The shift in frequency is a function of the chemical bonds and is a fingerprint of the substance irradiated. Electromagnetic (Infra-red) has been the commonest method of detection of volatile agents. Most systems use a subtractive system, i.e. the agent in the sampling cell absorbed some of the infrared energy and the photo-detector therefore received less energy. A different approach is where the absorbed energy is converted into a pressure change and detected as sound (Acoustic monitor). This gives a more stable zero reference. More recently, the detector systems have used multiple narrow-band wavelengths in the infrared bands and by shape matching or matrix computing specific agent identification is achieved and the concentration calculated. In the early Datex AS3 monitors, a spectral sweep across the 3 micron infrared band was used to create spectral fingerprints. The recently released AS3 monitors use a different system with five very narrow band filters in the 8-10 micron region. The transmission through each of these filters is a value in a matrix which is solved by a micro computer to identify the agent and its concentration. These monitors can assist in improving the safety and efficiency of our anaesthetics but do not ensure that the patient is completely anaesthetized. Copyright (2000

  3. Monitoring volatile anaesthetic agents

    Energy Technology Data Exchange (ETDEWEB)

    Russell, W J [Royal Adelaide Hospital, SA (Australia). Department of Anaesthesia and Intensive Care

    2000-12-01

    Full text: The methods that have been used for monitoring volatile anaesthetic agents depend on some physical property such as Density, Refractometry, Mass, Solubility, Raman scattering, or Infra-red absorption. Today, refractometry and infra-red techniques are the most common. Refractometry is used for the calibration of vaporizers. All anaesthetic agents increase the refractive index of the carrier gas. Provided the mixture is known then the refractive change measures the concentration of the volatile anaesthetic agent. Raman Scattering is when energy hits a molecule a very small fraction of the energy is absorbed and re-emitted at one or more lower frequencies. The shift in frequency is a function of the chemical bonds and is a fingerprint of the substance irradiated. Electromagnetic (Infra-red) has been the commonest method of detection of volatile agents. Most systems use a subtractive system, i.e. the agent in the sampling cell absorbed some of the infrared energy and the photo-detector therefore received less energy. A different approach is where the absorbed energy is converted into a pressure change and detected as sound (Acoustic monitor). This gives a more stable zero reference. More recently, the detector systems have used multiple narrow-band wavelengths in the infrared bands and by shape matching or matrix computing specific agent identification is achieved and the concentration calculated. In the early Datex AS3 monitors, a spectral sweep across the 3 micron infrared band was used to create spectral fingerprints. The recently released AS3 monitors use a different system with five very narrow band filters in the 8-10 micron region. The transmission through each of these filters is a value in a matrix which is solved by a micro computer to identify the agent and its concentration. These monitors can assist in improving the safety and efficiency of our anaesthetics but do not ensure that the patient is completely anaesthetized. Copyright (2000

  4. Selective noble gases monitoring

    International Nuclear Information System (INIS)

    Janecka, S.; Jancik, O.; Kapisovsky, V.; Kubik, I.; Sevecka, S.

    1995-01-01

    The monitoring of leak releases from ventilation stack of NPP requires a system by several orders more sensitive then currently used radiometer Kalina, designed to cover the range up to a design-based accident. To reach this goal a noble gases monitor with a germanium detector (MPVG) has been developed. It enables nuclide selective monitoring of current value of volume activity of particular nuclides in ventilation stack and daily releases of noble gases (balancing). MPVG can be viewed as a system build of three levels of subsystem: measuring level; control level; presentation level. Measuring level consists of gamma-spectroscopy system and operational parameters monitoring unit (flow rate, temperature, humidity). Control level provides communication between presentation and measuring level, acquisition of operational parameters and power supply. The presentation level of MPVG enables: 1) the measured data storage in predetermined time intervals; 2) the presentation of measured and evaluated values of radiation characteristics. The monitored radionuclides - default set: argon-41, krypton-85m, krypton-87, krypton-88, krypton-89, xenon-131m, xenon-133, xenon-133m, xenon-135, xenon-135m, xenon-137 and xenon-138. The values of volume activities observed at maximum releases have been approximately ten times higher. In that case in balancing some other nuclides exceed corresponding detection limits: 88 Kr(67; 22) Bq/m 3 ; 85m Kr(17; 7) Bq/m 3 ; 135m Xe(7.1; 0.5) Bq/m 3 ; 138 Xe(5.9; 0.9) Bq/m 3 . (J.K.)

  5. Selective noble gases monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Janecka, S; Jancik, O; Kapisovsky, V; Kubik, I; Sevecka, S [Nuclear Power Plants Research Institute, a.s., Trnava (Slovakia)

    1996-12-31

    The monitoring of leak releases from ventilation stack of NPP requires a system by several orders more sensitive then currently used radiometer Kalina, designed to cover the range up to a design-based accident. To reach this goal a noble gases monitor with a germanium detector (MPVG) has been developed. It enables nuclide selective monitoring of current value of volume activity of particular nuclides in ventilation stack and daily releases of noble gases (balancing). MPVG can be viewed as a system build of three levels of subsystem: measuring level; control level; presentation level. Measuring level consists of gamma-spectroscopy system and operational parameters monitoring unit (flow rate, temperature, humidity). Control level provides communication between presentation and measuring level, acquisition of operational parameters and power supply. The presentation level of MPVG enables: 1) the measured data storage in predetermined time intervals; 2) the presentation of measured and evaluated values of radiation characteristics. The monitored radionuclides - default set: argon-41, krypton-85m, krypton-87, krypton-88, krypton-89, xenon-131m, xenon-133, xenon-133m, xenon-135, xenon-135m, xenon-137 and xenon-138. The values of volume activities observed at maximum releases have been approximately ten times higher. In that case in balancing some other nuclides exceed corresponding detection limits: {sup 88}Kr(67; 22) Bq/m{sup 3}; {sup 85m}Kr(17; 7) Bq/m{sup 3}; {sup 135m}Xe(7.1; 0.5) Bq/m{sup 3}; {sup 138}Xe(5.9; 0.9) Bq/m{sup 3}. (J.K.).

  6. Rulison Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2010-07-01

    The Project Rulison Monitoring Plan has been developed as part of the U.S. Department of Energy (DOE) Office of Legacy Management's mission to protect human health and the environment. The purpose of the plan is to monitor fluids from gas wells for radionuclides that would indicate contamination is migrating from the Rulison detonation zone to producing gas wells, allowing action to be taken before the contamination could pose a risk. The Monitoring Plan (1) lists the contaminants present and identifies those that have the greatest potential to migrate from the detonation zone (radionuclide source term), (2) identifies locations that monitor the most likely transport pathways, (3) identifies which fluids will be sampled (gas and liquid) and why, (4) establishes the frequency of sampling, and (5) specifies the most practical analyses and where the analysis results will be reported. The plan does not affect the long-term hydrologic sampling conducted by DOE since 1972, which will continue for the purpose of sampling shallow groundwater and surface water near the site. The Monitoring Plan was developed in anticipation of gas wells being drilled progressively nearer the Rulison site. DOE sampled 10 gas wells in 1997 and 2005 at distances ranging from 2.7 to 7.6 miles from the site to establish background concentrations for radionuclides. In a separate effort, gas industry operators and the Colorado Oil and Gas Conservation Commission (COGCC) developed an industry sampling and analysis plan that was implemented in 2007. The industry plan requires the sampling of gas wells within 3 miles of the site, with increased requirements for wells within 1 mile of the site. The DOE plan emphasizes the sampling of wells near the site (Figure 1), specifically those with a bottom-hole location of 1 mile or less from the detonation, depending on the direction relative to the natural fracture trend of the producing formation. Studies indicate that even the most mobile

  7. Towards innovative roadside monitoring

    Science.gov (United States)

    Ojha, G.; Appel, E.; Magiera, T.

    2012-04-01

    Soil contamination along roadsides is an important factor of anthropogenic point source pollution. Climatic and traffic-specific factors influence the amount and characteristics of pollution emitted and deposited in the roadside soil. In our present study we focus on monitoring typical traffic pollutants (heavy metals HM, platinum group elements, polycyclic hydrocarbons PAH), and investigate the use of magnetic parameters, especially magnetic susceptibility (MS) as proxy. Monitoring plots were installed along roadside in areas with different climatic conditions and different traffic-specific activities (traffic density and speed, vehicle types, abrasion of tires, brake linings, petrol/diesel compounds and road maintenance). For monitoring we removed 10-15 cm of top soil at 1 m distance from the roadside edge and placed 30 plastic boxes there filled with clean quartz sand, to be sampled after regular intervals within two years. Preliminary data from the first year of monitoring are presented. Magnetic results revealed that a coarse grained magnetite-like phase is responsible for the enhancement of magnetic concentration. The mass-specific MS and concentration of pollutants (HM, PAH) all show a significant increase with time, however, there are obviously also seasonal and site-dependent effects which lead to more stable values over several months or even some decrease in the upper few cm due to migration into depth. Source identification indicates that the accumulated PAHs are primarily emissions from traffic. In order to be able to discriminate in between different kinds of transport and deposition (surface run off from the road and neighbouring soil material, splash water, air transport), we additionally established pillars at the roadside with clean quartz sampling boxes at different heights (surface, 0.5 m, 2 m). As a first surprising result we observed that the increase in the boxes at surface is not necessarily higher than at 0.5 m height. The results from our

  8. Final Report Technetium Monitor

    International Nuclear Information System (INIS)

    Spencer, W.A.

    2003-01-01

    The Hanford River Protection Project Waste Treatment Plant (WTP) is required by the current contract to remove radioactive technetium FR-om stored caustic nuclear waste solutions. The Savannah River Technology Center (SRTC) has worked with typical envelopes of these wastes to optimize the removal process. To support the studies, SRTC developed a rapid on-line remote analyzer to monitor technetium and rhenium levels in solutions as well as track other metals in the solutions through the process operations. Rhenium was used as a non-radioactive substitute for technetium in process development studies. The remote monitor was based on inductively coupled plasma emission spectroscopy (ICPES). Fiber optic cable and extended RF cabling removed the plasma source FR-om the spectrometer and instrument electronics

  9. Remote monitoring demonstration

    International Nuclear Information System (INIS)

    Caskey, Susan; Olsen, John

    2006-01-01

    The recently upgraded remote monitoring system at the Joyo Experimental Reactor uses a DCM-14 camera module and GEMINI software. The final data is compatible both with the IAEA-approved GARS review software and the ALIS software that was used for this demonstration. Features of the remote monitoring upgrade emphasized compatibility with IAEA practice. This presentation gives particular attention to the selection process for meeting network security considerations at the O'arai site. The Joyo system is different from the NNCA's ACPF system, in that it emphasizes use of IAEA standard camera technology and data acquisition and transmission software. In the demonstration itself, a temporary virtual private network (VPN) between the meeting room and the server at Sandia in Albuquerque allowed attendees to observe data stored from routine transmissions from the Joyo Fresh Fuel Storage to Sandia. Image files from a fuel movement earlier in the month showed Joyo workers and IAEA inspectors carrying out a transfer. (author)

  10. Monitoring the normal body

    DEFF Research Database (Denmark)

    Nissen, Nina Konstantin; Holm, Lotte; Baarts, Charlotte

    2015-01-01

    of practices for monitoring their bodies based on different kinds of calculations of weight and body size, observations of body shape, and measurements of bodily firmness. Biometric measurements are familiar to them as are health authorities' recommendations. Despite not belonging to an extreme BMI category...... provides us with knowledge about how to prevent future overweight or obesity. This paper investigates body size ideals and monitoring practices among normal-weight and moderately overweight people. Methods : The study is based on in-depth interviews combined with observations. 24 participants were...... recruited by strategic sampling based on self-reported BMI 18.5-29.9 kg/m2 and socio-demographic factors. Inductive analysis was conducted. Results : Normal-weight and moderately overweight people have clear ideals for their body size. Despite being normal weight or close to this, they construct a variety...

  11. Environmental monitoring report, 1976

    International Nuclear Information System (INIS)

    1977-01-01

    The effluent and environmental monitoring programs maintained by the Pinellas Plant are designed to determine the efficiencies of treatment and control mechanisms; to provide measurements of discharge concentrations for comparison with applicable standards; and to assess the concentrations of these discharges in the environment. Site perimeter and off-site air samples for tritium gas and tritium oxide, as well as off-site surface water samples obtained to distances of 9.6 kilometers (6 miles) from the plant site and analyzed for tritium content, showed levels significantly less than 1 / 10 of 1 percent of the recommended guide for continuous nonoccupational exposure. Small sealed plutonium sources are utilized at this site. No plutonium was released to the environment and monitoring data showed environmental background levels

  12. Portable radiation monitors

    International Nuclear Information System (INIS)

    Masui, Kaoru; Ishikura, Takeshi; Inui, Daisuke

    2007-01-01

    This paper presents an overview of typical portable radiation monitors and introduces Fuji Electric's latest models. The overview describes the types, uses and performance of ion chamber survey meters, GM survey meters and neutron ambient dose equivalent rate meters. Fuji Electric's new model of a wide-energy-range X/gamma ray survey meter which measures low energy X-rays up to 8 keV, a battery-powered environmental dosemeter system which measures dose history and is capable of continuous measurement with batteries over a year, and a portable monitoring post which measures dose rates from background to 10 8 nGy/h and transmits data by cellular phone are introduced, and their specifications and performance are described. (author)

  13. A Novel Pseudoerror Monitor

    Directory of Open Access Journals (Sweden)

    Wang Peng

    2004-01-01

    Full Text Available The error rate (ER is a crucial criterion in evaluating the performance of a digital communication system. Many ER estimation methods have been described in the literature. Among them, the pseudoerror monitoring solution has attracted special attention due to its consistent performance in different environments and distinctive blind estimation capability, that is, estimating the ER without needing any prior knowledge of the transmitted information. In this paper, a novel pseudoerror monitor (PEM design, the kernel PEM, is developed. Incorporating the strength of the probability density function (pdf approximation technique, the proposed design has remarkable advantage of being able to produce statistically consistent ER estimate within a much shorter observation time. Simulation results are given in support of this claim.

  14. System health monitoring

    International Nuclear Information System (INIS)

    Reneke, J.A.; Fryer, M.O.

    1995-01-01

    Well designed large systems include many instrument taking data. These data are used in a variety of ways. They are used to control the system and its components, to monitor system and component health, and often for historical or financial purposes. This paper discusses a new method of using data from low level instrumentation to monitor system and component health. The method uses the covariance of instrument outputs to calculate a measure of system change. The method involves no complicated modeling since it is not a parameter estimation algorithm. The method is iterative and can be implemented on a computer in real time. Examples are presented for a metal lathe and a high efficiency particulate air (HEPA) filter. It is shown that the proposed method is quite sensitive to system changes such as wear out and failure. The method is useful for low level system diagnostics and fault detection

  15. Corrosion Monitoring System

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Russ Braunling

    2004-10-31

    The Corrosion Monitoring System (CMS) program developed and demonstrated a continuously on-line system that provides real-time corrosion information. The program focused on detecting pitting corrosion in its early stages. A new invention called the Intelligent Ultrasonic Probe (IUP) was patented on the program. The IUP uses ultrasonic guided waves to detect small defects and a Synthetic Aperture Focusing Technique (SAFT) algorithm to provide an image of the pits. Testing of the CMS demonstrated the capability to detect pits with dimensionality in the sub-millimeter range. The CMS was tested in both the laboratory and in a pulp and paper industrial plant. The system is capable of monitoring the plant from a remote location using the internet.

  16. OLYMPUS luminosity monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Ates, Ozgur [Hampton University, Hampton, Virginia (United States); Collaboration: OLYMPUS-Collaboration

    2013-07-01

    The OLYMPUS experiment at DESY has been measuring the ratio of positron-proton and electron-proton elastic scattering cross sections to quantify the effect of two-photon exchange, which is widely considered to be responsible for the discrepancy between measurements of the proton electric to magnetic form factor ratio with the Rosenbluth and polarization transfer methods. In order to control the systematic uncertainties to the percent level, the luminosities are monitored redundantly with high precision by measuring the rates for symmetric Moller and Bhabha scattering, and by measuring the ep-elastic count rates at forward angles and low momentum transfer with tracking telescopes based on GEM (Gas Electron Multiplier) and MWPC (Multi Wire Proportional Chamber) technology. During two data taking periods, performances of GEM and MWPC luminosity monitors are presented.

  17. Method for radioactivity monitoring

    Science.gov (United States)

    Umbarger, C. John; Cowder, Leo R.

    1976-10-26

    The disclosure relates to a method for analyzing uranium and/or thorium contents of liquid effluents preferably utilizing a sample containing counting chamber. Basically, 185.7-keV gamma rays following .sup.235 U alpha decay to .sup.231 Th which indicate .sup.235 U content and a 63-keV gamma ray doublet found in the nucleus of .sup.234 Pa, a granddaughter of .sup.238 U, are monitored and the ratio thereof taken to derive uranium content and isotopic enrichment .sup.235 U/.sup.235 U + .sup.238 U) in the liquid effluent. Thorium content is determined by monitoring the intensity of 238-keV gamma rays from the nucleus of .sup.212 Bi in the decay chain of .sup.232 Th.

  18. Embodied-self-monitoring

    DEFF Research Database (Denmark)

    Bagalkot, Naveen L.

    -hardware drove this co-evolution in collaboration with the rehabilitees, their spouses, and their professional therapists. The explorations resulted in a ‘compositional whole’. This compositional whole is constituted by the theoretical concept of embodied-self-monitoring; the various scenarios of possible...... for compliance. I formulate the theoretical concept of ‘embodied-self-monitoring’ to orient the design towards embracing the embodied actions of the rehabilitees through which they make sense of complying with the therapy. The central argument of this thesis is that the theoretical concept of embodied....... I follow a concept-driven interaction design research process. This is a dialectic process where both the understanding of what is embodied-self-monitoring and what prospects it offers co-evolved through the two groups of design explorations presented in this thesis. A process of sketching -in...

  19. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  20. Radiation monitor reporting requirements

    International Nuclear Information System (INIS)

    Bates, W.F.

    1993-01-01

    Within High-Level Waste Management (HLWM), CAMs and VAMPs are currently considered Class B equipment, therefore, alarm conditions associated with the CAMs and VAMPs result in an Unusual Occurrence or Off-Normal notification and subsequent occurrence reporting. Recent equipment difficulties associated with Continuous Air Monitors (CAMs) and Victoreen Area Radiation Monitors (VAMPs) have resulted in a significant number of notification reports. These notification have the potential to decrease operator sensitivity to the significance of specific CAM and VAMP failures. Additionally, the reports are extremely costly and are not appropriate as a means for tracking and trending equipment performance. This report provides a technical basis for a change in Waste Management occurrence reporting categorization for specific CAM and VAMP failure modes

  1. Tritium monitoring techniques

    International Nuclear Information System (INIS)

    DeVore, J.R.; Buckner, M.A.

    1996-05-01

    As part of their operations, the U.S. Navy is required to store or maintain operational nuclear weapons on ships and at shore facilities. Since these weapons contain tritium, there are safety implications relevant to the exposure of personnel to tritium. This is particularly important for shipboard operations since these types of environments can make low-level tritium detection difficult. Some of these ships have closed systems, which can result in exposure to tritium at levels that are below normally acceptable levels but could still cause radiation doses that are higher than necessary or could hamper ship operations. This report describes the state of the art in commercial tritium detection and monitoring and recommends approaches for low-level tritium monitoring in these environments

  2. Monitoring of environmental radioactivity

    International Nuclear Information System (INIS)

    1986-01-01

    The results are described of monitoring radioactivity of atmospheric fallout, surface waters, soils, plant feeds, cereals, and other agricultural produce. The results were obtained over a long time period. Radioactivity was also measured of milk, milk products, vegetables and fruits, meat and hen eggs, flour and bakery products with a view to radionuclide migration in the food chain. The daily intake of 90 Sr and 137 Cs from food was determined from the values obtained and the consumption of the individual types of food. Strontium-90 distribution was studied in the bones and the teeth of the population in Slovakia. With the commissioning of nuclear power plants, emissions and liquid wastes were monitored and their environmental impact assessed. (E.S.)

  3. Loose parts monitoring system

    International Nuclear Information System (INIS)

    Wakasa, Kohji; Nishida, Eiichi; Ishii, Kazuo; Yamanaka, Hiroto.

    1987-01-01

    In the loose parts monitoring system (LPMS), installed for integrity monitoring of the nuclear power plants; when there occur foreign metallic objects in the reactor primary system, including a steam generator and the piping, the sounds caused by them moving with the cooling water and thereby getting in contact with various structures are detected. Its purpose is, therefore, to detect any abnormality in the reactor plant system through such abnormal sounds due to loose or fallen supports etc., and so provide this information to the reactor operators. In principle, accelerometers are distributed in such as reactor vessel, steam generator, coolant pumps, etc., so that various sounds are collected and converted into electrical signals, followed by analysis of the data. Described are the LPMS configuration/functions, the course taken in LPMS development, future problems, etc. (Mori, K.)

  4. Benzene Monitor System report

    International Nuclear Information System (INIS)

    Livingston, R.R.

    1992-01-01

    Two systems for monitoring benzene in aqueous streams have been designed and assembled by the Savannah River Technology Center, Analytical Development Section (ADS). These systems were used at TNX to support sampling studies of the full-scale open-quotes SRAT/SME/PRclose quotes and to provide real-time measurements of benzene in Precipitate Hydrolysis Aqueous (PHA) simulant. This report describes the two ADS Benzene Monitor System (BMS) configurations, provides data on system operation, and reviews the results of scoping tests conducted at TNX. These scoping tests will allow comparison with other benzene measurement options being considered for use in the Defense Waste Processing Facility (DWPF) laboratory. A report detailing the preferred BMS configuration statistical performance during recent tests has been issued under separate title: Statistical Analyses of the At-line Benzene Monitor Study, SCS-ASG-92-066. The current BMS design, called the At-line Benzene Monitor (ALBM), allows remote measurement of benzene in PHA solutions. The authors have demonstrated the ability to calibrate and operate this system using peanut vials from a standard Hydragard trademark sampler. The equipment and materials used to construct the ALBM are similar to those already used in other applications by the DWPF lab. The precision of this system (±0.5% Relative Standard Deviation (RSD) at 1 sigma) is better than the purge ampersand trap-gas chromatograpy reference method currently in use. Both BMSs provide a direct measurement of the benzene that can be purged from a solution with no sample pretreatment. Each analysis requires about five minutes per sample, and the system operation requires no special skills or training. The analyzer's computer software can be tailored to provide desired outputs. Use of this system produces no waste stream other than the samples themselves (i.e. no organic extractants)

  5. Icinga network monitoring

    CERN Document Server

    Mehta, Viranch

    2013-01-01

    This book is written in a concise and easy-to-follow approach, it will guide you to get you started with Icinga and lead you through the difficult concepts with illustrated examples and screenshots.If you are a system administrator or Linux enthusiast who is looking for a flexible tool to monitor network infrastructure efficiently, or trying to understand the Icinga software, this is a great book for you. You are expected to have solid foundation in Linux.

  6. Alpha-monitoring system

    International Nuclear Information System (INIS)

    Dincklage, R.D. von

    1982-01-01

    A continuously operating and fast system for the monitoring of radiactive materials is outlined. Its application to nuclear technology particularly to reprocessing is emphasized. Using high-resolution α-ray spectrocopy and the gas-jet method for the rapid transportation of the radionuclides to the solid state detectors makes detection limits as low as 0.2 μg/cm 3 for Pu-239 feasible. (orig.)

  7. Yacht Race Monitoring

    Science.gov (United States)

    1981-01-01

    Observer Single-handed Transatlantic Race (OSTAR) participants were aided by a French-American space-based monitoring system which reported the yacht's positions throughout the race, and also served as an emergency locator service. Originating from NASA's Nimbus 6 Satellite, use of this system, called ARGOS made the OSTAR competition the most accurately reported sea race ever conducted. Each boat carried a portable transmitter allowing 88 new sources of oceanographic data available during the race.

  8. Nuclear methods monitor nutrition

    International Nuclear Information System (INIS)

    Allen, B.J.

    1988-01-01

    Neutron activation of nitrogen and hydrogen in the body, the isotope dilution technique and the measurement of naturally radioactive potassium in the body are among the new nuclear methods, now under collaborative development by the Australian Nuclear Scientific and Technology Organization and medical specialists from several Sydney hospitals. These methods allow medical specialists to monitor the patient's response to various diets and dietary treatments in cases of cystic fibrosis, anorexia nervosa, long-term surgical trauma, renal diseases and AIDS. ills

  9. Chapter 5: Monitoring results

    DEFF Research Database (Denmark)

    Poel, Bart; Thomsen, Kirsten Engelund; Schultz, Jørgen Munthe

    2003-01-01

    The monitoring results from the IEA Task 13 project "Advanced solar low energy houses" are described in this chapter. The underlying information was collected in the form of questionnaires. The questionnaires were formulated in such a way that participants are provided with a uniform lay......-out to fill in their particular results. Thus it is possible to compare the performances measured, calculated or predicted for the different houses....

  10. Monitoring of environment

    Energy Technology Data Exchange (ETDEWEB)

    Mitsudera, M

    1974-09-01

    The amount of pollutants discharged has now exceeded the environment's natural ability to purify itself. The effect of urbanization is traced especially the degeneration of plants and animals in Tokyo. One of the methods of monitoring plants is remote sensing with multi-band photography and multi-spectroscanning. There is a correlation between the sulfur content of tree leaves and multi-band photograms on red pine trees with a correlation coefficient of -0.862.

  11. Nuclear reactor monitoring system

    International Nuclear Information System (INIS)

    Drummond, C.N.; Bybee, R.T.; Mason, F.L.; Worsham, H.J.

    1976-01-01

    The invention pertains to an improved monitoring system for the neutron flux in a nuclear reactor. It is proposed to combine neutron flux detectors, a thermoelement, and a background radiation detector in one measuring unit. The spatial arrangement of these elements is fixed with great exactness; they are enclosed by an elastic cover and are brought into position in the reactor with the aid of a bent tube. The arrangement has a low failure rate and is easy to maintain. (HP) [de

  12. Genetic monitoring of agrocoenosis

    International Nuclear Information System (INIS)

    Lukin, V.D.

    2005-01-01

    Mutants with high frequency of revertants appearance can be used as biological indicator of genetic monitoring of agrocoenosis. It differs from the initial form in dwarf-size of the shrub, the changed plate of leaf and sterility. The low limit of the mutant sensitiveness on the test of visible reverse mutations to the doses of gamma-irradiation is 0,2 Gy and to the rate of soil contamination by lead is 50 mg per 1 kg of soil. (authors)

  13. Bilevel alarm monitoring multiplexer

    International Nuclear Information System (INIS)

    Johnson, C.S.

    1977-06-01

    This report describes the operation of the Bilevel Alarm Monitoring Multiplexer used in the Adaptive Intrusion Data System (AIDS) to transfer and control alarm signals being sent to the Nova 2 computer, the Memory Controlled Data Processor, and its own integral Display Panel. The multiplexer can handle 48 alarm channels and format the alarms into binary formats compatible with the destination of the alarm data

  14. Poverty Monitor 1999

    OpenAIRE

    1999-01-01

    Original title: Armoedemonitor 1999. The Poverty Monitor 1999 (Armoedemonitor 1999) presents as complete and up-to-date a picture as possible of poverty in the Netherlands, and thus provides a factual basis for the debate on poverty. The Netherlands Institute for Social Research/SCP and Statistics Netherlands (CBS) have together collected and analysed a large amount of data on poverty. The findings are set out in this publication. The report also evaluates some aspects of the policy on povert...

  15. Annex 5. Monitoring committee

    OpenAIRE

    2013-01-01

    Head of monitoring committee: the Research Commission of the govern­ment of French Polynesia. Panel members Representatives of the following organisations: IRD centre in Papeete Oceanologic Center of the Pacific/Ifremer Investment Promotion Authority Environment Division EPIC Vanille Institut Louis-Malardé Gepsun “Natural Substances process engineering” technology platform (cf. Abbreviations) Fisheries Division Economic Affairs Division External Trade Division Development of Industry and the...

  16. Neutral beam monitoring

    International Nuclear Information System (INIS)

    Fink, J.H.

    1979-01-01

    A neutral beam generated by passing accelerated ions through a walled cell containing a low energy neutral gas, such that charge exchange partially neutralizes the high energy beam, is monitored by detecting the current flowing through the cell wall produced by low energy ions which drift to the wall after the charge exchange. By segmenting the wall into radial and longitudinal segments various beam conditions are identified. (U.K.)

  17. RTP Radiation Monitoring System

    International Nuclear Information System (INIS)

    Alfred, S.L.; Mohd Fairus Abdul Farid; Ahmad Nabil Abdul Rahim; Nurhayati Ramli

    2015-01-01

    Radiation Monitoring System aiming to limiting dose exposed to personnel to the lowest level referring to the concept of ALARA (As Low As Reasonably Achievable). Atomic Energy Licensing (Basic Safety Radiation Protection) Regulation 2010 (Act 304) is a baseline to control employee and public radiation protection program and guideline, as well as to meet the requirement of the Occupational Safety and Health 1994 (Act 514). (author)

  18. Open Access Monitor - DK

    DEFF Research Database (Denmark)

    Svendsen, Michael; Hansen, Lars Asger Juel; Andersen, Dorte

    2017-01-01

    Open Access Monitor - DK (OAM-DK) is a 2-year DEFF funded [DEFF.2016-0018] national project running in 2017-2018 with the aim of collecting, documenting and administrating Open Access publishing costs. OAM-DK is lead by Copenhagen University Library under the Royal Danish Library with participation...... of all Danish University Libraries. This poster presents the first results of Open Access costs related to 2015 publications at the The University of Copenhagen....

  19. Targets of operation monitoring

    International Nuclear Information System (INIS)

    Wenger, H.

    1997-01-01

    The condition monitoring system of a nuclear power plant should be an assurance for the user and the authorities that the safety of the installation constantly corresponds to the nominal condition. As soon as deviations from these conditions occur, it should quickly provide fundamentals for corrective measures. It contributes to a high degree of availability of the installation and makes safe and economical operation throughout the whole life of the installation possible. (author) 1 fig

  20. Whole body monitoring - Goiania

    International Nuclear Information System (INIS)

    Oliveira, C.A.N. de; Lourenco, M.C.; Bertelli Neto, L.; Lucena, E.A. de; Becker, P.H.B.

    1988-01-01

    Due to the radiological Cs accident in Goiania, Goias in September 1987, it became necessary to evaluate internal contamination levels of: - Individual from the general public that for any reason had direct or indirect involvement with the radioactive source (group 1). - Occupationally involved persons (group 2). For each of these groups, procedures of whole body monitoring were developped. In order to attend group 1 individuals, the IRD/CNEN installed a whole body unit in the INAMPS General Hospital of Goiania in 11.08.87, which was later transferred to 121,57 street, Central Sector in Goiania in 2.06.88. In this unit 547 people were monitored, 356 from group 1 and 241 from group 2, until 04.13.88. In the IRD whole body counter installation, 194 individuals were counted, 185 from group 2 and 9 from group 1. The frequency of monitoring of each individual was established according to the Cs activity present in the body or to the job to be assigned. In this paper we will present some burden activity curves for Cs 137 as a function of the time elapsed from the first measurement. There people from group 1 were measured in both counters, the IRD and the Goiania ones. The values obtained in both installations are compatible with the body activity x time curve. (author) [pt

  1. 1984 environmental monitoring report

    International Nuclear Information System (INIS)

    Day, L.E.; Miltenberger, R.P.; Naidu, J.R.

    1985-04-01

    The environmental monitoring program has been designed to ensure that BNL facilities operate such that the applicable environmental standards and effluent control requirements have been met. A listing, as required by DOE Order 5484.1 of BNL facilities, of environmental agencies and permits is provided in the Environmental Program Information Section 3.0, Table B. Since the aquifer underlying Long Island has been designated a ''sole source'' aquifer, the Environmental Protection Agency (EPA) Drinking Water Standards have been used in the assessment of ground water data. However, the limits prescribed in the regulations are not directly applicable to the monitoring well data since (1) the standards apply to a community water supply system, i.e., one serving more than 25 individuals, and (2) the standards represent an annual average concentration. Since the monitoring wells are not components of the Laboratory's water supply system, the EPA drinking water standards are employed as reference criteria to which the surveillance well data is compared. The standards also serve as guidance levels for any appropriate remedial action. 36 refs., 9 figs., 40 tabs

  2. Equipment abnormality monitoring device

    International Nuclear Information System (INIS)

    Ando, Yasumasa

    1991-01-01

    When an operator hears sounds in a plantsite, the operator compares normal sounds of equipment which he previously heard and remembered with sounds he actually hears, to judge if they are normal or abnormal. According to the method, there is a worry that abnormal conditions can not be appropriately judged in a case where the number of objective equipments is increased and in a case that the sounds are changed gradually slightly. Then, the device of the present invention comprises a plurality of monitors for monitoring the operation sound of equipments, a recording/reproducing device for recording and reproducing the signals, a selection device for selecting the reproducing signals among the recorded signals, an acoustic device for converting the signals to sounds, a switching device for switching the signals to be transmitted to the acoustic device between to signals of the monitor and the recording/reproducing signals. The abnormality of the equipments can be determined easily by comparing the sounds representing the operation conditions of equipments for controlling the plant operation and the sounds recorded in their normal conditions. (N.H.)

  3. Radiation monitoring by minicomputer

    International Nuclear Information System (INIS)

    Seamons, M.

    1977-01-01

    Radiation monitoring at the Los Alamos Scientific Laboratory (LASL) ranges from measuring the potential build-up of alpha particle radiation in the offices and laboratories of LASL to the detection of radiation leakage from nuclear tests at the Nevada Test Site (NTS). This paper describes PDP-11 based systems to accomplish both types of monitoring. In the first system, filter papers are collected from monitoring stations around LASL. One filter paper is placed under any of 128 photomultiplier (PM) tubes exposing it to alpha radiation. Alpha particle ''hits'' are recorded in a 64-word hardware FIFO, which interrupts and is read by the computer. The FIFO makes it possible to handle short aggregate alpha particle bursts of up to 10 6 hits/s in a computer that can only process 10 4 hits/s. In the second system, up to 100 current measuring radiation probes feed data from the site of the nuclear test(s) to the computer by microwave. The software system can support three tests simultaneously. Both systems offer a high degree of flexibility in configuring for a new test and in real-time control of such things as channel assignment, selective data retrieval, and output formatting

  4. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Bruecher, L.; Langmueller, G.; Tuerschmann, G.

    1997-01-01

    The safety, the quality and efficiency of the radiological monitoring systems for block one and two of the NPP Mochovce, designed and delivered by the general designer, should be increased by EUCOM Siemens. Modern, accident resistant and/or more powerful monitoring systems have been designed by Siemens will be added to the existing systems. To achieve this radiation measuring units will be installed inside the hermetic zone, in the reactor hall, at the stack, at the release water system and in the environment in the vicinity of the NPP. The presentation, the storage distribution and the processing of all measuring results also will be optimised by installing a modern high-performance computer system, the so-called Central Radiological Computer System 'CRCS', featuring a high availability. The components will be installed in the relevant control rooms all over the plant. With this computer system it is easy to control the radiation level inside and outside the NPP during normal operation and during and after an accident. Special programs, developed by Siemens support the staff by interpreting the consequences of radioactive releases into the environment and by initiating protection procedures during and after an accident. All functions of the system are available for emergency protection drills and training the staff interruption of the normal control procedure. For the personal protection a digital personal dosimetry system completely considering with the requirements of ICRP 60 and several contamination monitors will be installed. (authors)

  5. Neutron monitoring system

    International Nuclear Information System (INIS)

    Okido, Fumiyasu; Arita, Setsuo.

    1994-01-01

    The present invention concerns neutron monitoring for monitoring reactor power, and presents a generation state of abnormal signals by monitoring output signals from neutron sensors, judges abnormal signals at an excessively high level outputted from the sensors to a measuring operator or a reactor operator. That is, a threshold value judging means judges whether a sensor signal exceeds a predetermined threshold value or not. When it exceeds the value, recognition signals are outputted to a memory means. The memory means memorizes the times of input of the recognition signals on every period of interval signals outputted from a reference signal generation means. The memory content of the memory means and the previously inputted hysteresis of the sensor are compared and judged, to determine the extent of the degradation of the sensors and output the result of the judgement and hysteresis information to the display means. The input means accesses to the judging means and the memory means to retrieve and correct the content of the memory means and the hysteresis information inputted to the judging means. (I.S.)

  6. Solar weather monitoring

    Directory of Open Access Journals (Sweden)

    J.-F. Hochedez

    2005-11-01

    Full Text Available Space Weather nowcasting and forecasting require solar observations because geoeffective disturbances can arise from three types of solar phenomena: coronal mass ejections (CMEs, flares and coronal holes. For each, we discuss their definition and review their precursors in terms of remote sensing and in-situ observations. The objectives of Space Weather require some specific instrumental features, which we list using the experience gained from the daily operations of the Solar Influences Data analysis Centre (SIDC at the Royal Observatory of Belgium. Nowcasting requires real-time monitoring to assess quickly and reliably the severity of any potentially geoeffective solar event. Both research and forecasting could incorporate more observations in order to feed case studies and data assimilation respectively. Numerical models will result in better predictions of geomagnetic storms and solar energetic particle (SEP events. We review the data types available to monitor solar activity and interplanetary conditions. They come from space missions and ground observatories and range from sequences of dopplergrams, magnetograms, white-light, chromospheric, coronal, coronagraphic and radio images, to irradiance and in-situ time-series. Their role is summarized together with indications about current and future solar monitoring instruments.

  7. Radiation monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

  8. Bulk laundry monitoring system

    International Nuclear Information System (INIS)

    Thakur, Vaishali M.; Jain, Amit; Verma, Amit; Anilkumar, S.; Babu, D.A.R.; Sharma, D.N.; Rande, N.R.; Singh, B.N.

    2012-01-01

    Protective wear (like boiler suits, hand gloves etc.) is essential while handling radioactive material in plants/laboratories. During the course of work, it is quite possible that protective wear may get contaminated. These protective wears are packed in laundry bags and send to Decontamination Centre (DC). There is a need for monitoring the laundry bags at the time of receipt, as well as before dispatch to respective locations to comply with AERB guidelines, To avoid cross contamination during wash cycle, contaminated bags (> 0.5 mR/h on surface) need to be segregated. Present paper describes the development of such system for monitoring surface dose rate on bags at the time of receipt. The system installed at ETP after calibration, effectively segregates the contaminated bags from the rest and prevents from cross contamination during wash cycle. Reduction in man-rem consumption due to semi automatic monitoring. Improved sensitivity due to good geometry, long counting time, background and attenuation corrections. Optimum utilization of decontamination chemicals based on level of contamination and keeping track of its inventory. Generation of decontamination process data base for improvement

  9. Environmental monitoring using lasers

    International Nuclear Information System (INIS)

    Iqbal, M.; Ahmed, N.

    1997-01-01

    Activities of human beings are creating slow and long term changes in the Earth's atmosphere. As the sun provides the driving force for earth's ecosystem, therefore earth's radiation budget is an important parameter. Composition of the atmosphere is of basic importance in determining this radiation budget. Out of the atmospheric species, ozone is of special importance because it filters out much of the solar UV, while certain other molecular species, such as SO/sub 2/ , NO/sub 2/, benzene, toluene and aerosols have very harmful effects on life. Depletion of ozone layer over Antarctic and addition of chemical species to atmosphere and oceans have disturbed our ecosystem seriously. Thorough monitoring of distribution and dynamics of these species is essential for devising any countermeasure for their control. Conventional method of atmospheric monitoring (balloon, rocket or satellite borne sensors) are limited either in range or type of measurement apart from being complex and somewhat expensive. LASER based 'light detection and ranging (LIDAR) technique, on the other hand, enjoys a number of advantages over others. Due to recent developments in LASER technique, on the other hand, enjoys a number of advantages over other. Due to recent developments in LASER technology, LIDARS are economical and very flexible in range and type of measurement. This paper presents an overview of the technique. It includes principle of LIDAR, highlights its applications to the monitoring of atmosphere, biosphere and hydrosphere. (author)

  10. Radiation monitoring system

    International Nuclear Information System (INIS)

    Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino

    2015-01-01

    Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

  11. A simple condition monitoring model for a direct monitoring process

    NARCIS (Netherlands)

    Christer, A.H.; Wang, Wenbin

    1995-01-01

    This paper addresses the problem of condition monitoring of a component which has available a measure of condition called wear. Wear accumulates over time and monitoring inspections are performed at chosen times to monitor and measure the cumulative wear. If past measurements of wear are available

  12. 1988 Monitoring Activities Review (MAR) of the environmental monitoring program

    International Nuclear Information System (INIS)

    1989-03-01

    The EGandG Idaho Environmental Monitoring (EM) Unit is responsible for coordinating and conducting environmental measurements of radioactive and hazardous contaminants around facilities operated by EGandG Idaho. The EM Unit has several broad program objectives, which include complying with regulatory standards and developing a basis for estimating future impacts of operations at EGandG Idaho facilities. To improve program planning and to provide bases for technical improvement of the monitoring program, the EGandG Environmental Monitoring organization has regularly used the Monitoring Activities Review (MAR) process since 1982. Each MAR is conducted by a committee of individuals selected for their experience in the various types of monitoring performed by the EM organization. Previous MAR studies have focused on procedures for all currently monitored media except biota. Biotic monitoring was initiated following the last MAR. This report focuses on all currently monitored media, and includes the first review of biotic monitoring. The review of biotic monitoring has been conducted at a level of detail consistent with initial MAR reports for other parts of the Waste Management Program Facilities Environmental Monitoring Program. The review of the biotic monitoring activities is presented in Section 5.5 of this report. 21 refs., 7 figs., 4 tabs

  13. Induced Seismicity Monitoring System

    Science.gov (United States)

    Taylor, S. R.; Jarpe, S.; Harben, P.

    2014-12-01

    There are many seismological aspects associated with monitoring of permanent storage of carbon dioxide (CO2) in geologic formations. Many of these include monitoring underground gas migration through detailed tomographic studies of rock properties, integrity of the cap rock and micro seismicity with time. These types of studies require expensive deployments of surface and borehole sensors in the vicinity of the CO2 injection wells. Another problem that may exist in CO2 sequestration fields is the potential for damaging induced seismicity associated with fluid injection into the geologic reservoir. Seismic hazard monitoring in CO2 sequestration fields requires a seismic network over a spatially larger region possibly having stations in remote settings. Expensive observatory-grade seismic systems are not necessary for seismic hazard deployments or small-scale tomographic studies. Hazard monitoring requires accurate location of induced seismicity to magnitude levels only slightly less than that which can be felt at the surface (e.g. magnitude 1), and the frequencies of interest for tomographic analysis are ~1 Hz and greater. We have developed a seismo/acoustic smart sensor system that can achieve the goals necessary for induced seismicity monitoring in CO2 sequestration fields. The unit is inexpensive, lightweight, easy to deploy, can operate remotely under harsh conditions and features 9 channels of recording (currently 3C 4.5 Hz geophone, MEMS accelerometer and microphone). An on-board processor allows for satellite transmission of parameter data to a processing center. Continuous or event-detected data is kept on two removable flash SD cards of up to 64+ Gbytes each. If available, data can be transmitted via cell phone modem or picked up via site visits. Low-power consumption allows for autonomous operation using only a 10 watt solar panel and a gel-cell battery. The system has been successfully tested for long-term (> 6 months) remote operations over a wide range

  14. Monitoring Your Blood Sugar Level

    Science.gov (United States)

    ... and NutritionHealth Insurance: Understanding What It CoversHigh Homocysteine Level: How It Affects Your Blood VesselsUnderstanding Your Medical ... Health Resources Healthcare Management Monitoring Your Blood Sugar Level Monitoring Your Blood Sugar Level Share Print What ...

  15. Area monitoring intelligent system - SIMA

    International Nuclear Information System (INIS)

    Bhoem, P.; Hisas, F.; Gelardi, G.

    1990-01-01

    The area monitoring intelligent system (SIMA) is an equipment to be used in radioprotection. SIMA has the function of monitoring the radiation levels of determined areas of the installations where radioactive materials are handled. (Author) [es

  16. Esophageal pH monitoring

    Science.gov (United States)

    pH monitoring - esophageal; Esophageal acidity test ... Esophageal pH monitoring is used to check how much stomach acid is entering the esophagus. It also checks how well the acid is cleared downward into the ...

  17. Subcriticality monitoring method for reactor

    International Nuclear Information System (INIS)

    Ueda, Makoto.

    1991-01-01

    The present invention accurately monitors the reactor subcriticality and ensures the critical safety, irrespective of the presence or absence of artificial neutron sources. That is, when the subcriticality is monitored upon reactivity changing operation which causes reactivity change to the reactor during shutdown, neutron monitors are disposed at a plurality of monitoring positions. Then, neutron counting ratio before and after conducting the reactivity changing operation is determined. The subcriticality of the reactor is monitored by the ratio and the state of scattering of the ratio of neutron counting rate between each of the neutron monitors. With such procedures, signals of the neutron monitors are used, the characteristic that the change of the signals depend on the change of the neutron multiplication of the reactor core can be utilized whether artificial neutron sources (external neutron sources) are disposed or not. Accordingly, the subcriticality can be monitored more reliably. (I.S.)

  18. Electrostatic beam-position monitor

    CERN Multimedia

    CERN PhotoLab

    1969-01-01

    Electrostatic beam-position monitor installed in its final location (bake-out cover removed). The ISR will contain about 110 of these monitors. Their accuracy is better than 1 mm, their band width about 1 MHz.

  19. The Danish Marine Monitoring System

    DEFF Research Database (Denmark)

    Ærtebjerg, G.

    1997-01-01

    Indeholder abstracts fra Workshop on Marine Monitoring Systems and Technology, Risø, 17-18 April 1996.......Indeholder abstracts fra Workshop on Marine Monitoring Systems and Technology, Risø, 17-18 April 1996....

  20. Event monitoring of parallel computations

    Directory of Open Access Journals (Sweden)

    Gruzlikov Alexander M.

    2015-06-01

    Full Text Available The paper considers the monitoring of parallel computations for detection of abnormal events. It is assumed that computations are organized according to an event model, and monitoring is based on specific test sequences

  1. Calibration of radiation monitoring instruments

    International Nuclear Information System (INIS)

    1973-01-01

    Radiation protection is dependent on good radiation monitoring, and properly calibrated instruments are essential for this work. Simple procedures for periodically checking and recalibrating different kinds of radiation monitoring instruments are shown in this training film

  2. Iowater Water Quality Monitoring Sites

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — This coverage contains points representing monitoring locations on streams, lakes and ponds that have been registered by IOWATER monitors. IOWATER, Iowa's volunteer...

  3. Calibration of radiation monitoring instruments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-12-31

    Radiation protection is dependent on good radiation monitoring, and properly calibrated instruments are essential for this work. Simple procedures for periodically checking and recalibrating different kinds of radiation monitoring instruments are shown in this training film

  4. Lunar Health Monitor, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — During the Phase II Lunar Health Monitor program, Orbital Research will develop a second generation wearable sensor suite for astronaut physiologic monitoring. The...

  5. Dose monitoring in nuclear emergency

    International Nuclear Information System (INIS)

    Nan Hongjie; Yang Zhongping; Lei Xin

    2012-01-01

    In order to protect people from irradiation sickness and rebuild the radiation filed in nuclear emergency, personal and environmental dose need to be monitored. The application of TLD in dose monitoring is discussed in this paper. (authors)

  6. Soil monitoring as a part of environment monitoring in Slovakia

    International Nuclear Information System (INIS)

    Kobza, J.

    1997-01-01

    In frame of Soil monitoring system it is going about a lot of methods in advance as follows: methods of soil monitoring sites selection and soil monitoring network construction, as well; methods of soil survey and soil sampling; analytical methods (indicating of chemical, agrochemical and physical properties); soil database and methods of evaluation and interpretation of measured results. The monitoring network was constructed on the base of ecological principles - including the monitoring of all soil types and subtypes, various climatic and emission regions as well as relatively clean regions, lowland and highland. Soil monitoring network in forest land is regular (8 x 8 km) with regard to International monitoring system in Forestry. The soil monitoring network in Slovakia consist of 650 monitoring sites (312 sites in farming land and 338 sites in forest land). In addition soil monitoring network includes also 21 monitoring sites. All monitoring sites are geodesically located and reported on the map at a scale of 1:5000. There are the methods concerning the important soil parameters indication with regard to main soil degradation processes a s follows: soil contamination (heavy metals and organic contaminants); soil acidification; soil salinity; soil erosion (deluometrically by the Cs-137 and remote sensing methods); soil compaction; soil fertility and protection. Analytical control system was elaborated according to Good Laboratory Practice. Evaluation of soil monitoring network results is not simple because it depends on various monitored parameters, on aim of evaluation as well as on the scale of landscape which is object for evaluation. There are used the modern statistical methods in monitoring system which can be: universal; disjunctive; simulated. Used statistical methods are significant for interpretation of measured results as follows: trends in landscape; anisotropy; comparison. The evaluation and interpretation way is very significant with regard not

  7. Protocol Monitoring Energy Conservation; Protocol Monitoring Energiebesparing

    Energy Technology Data Exchange (ETDEWEB)

    Boonekamp, P.G.M. [ECN Beleidsstudies, Petten (Netherlands); Mannaerts, H. [Centraal Planburea CPB, Den Haag (Netherlands); Tinbergen, W. [Centraal Bureau voor de Statistiek CBS, Den Haag (Netherlands); Vreuls, H.H.J. [Nederlandse onderneming voor energie en milieu Novem, Utrecht (Netherlands); Wesselink, B. [Rijksinstituut voor Volksgezondheid en Milieuhygiene RIVM, Bilthoven (Netherlands)

    2001-12-01

    On request of the Dutch ministry of Economic Affairs five institutes have collaborated to create a 'Protocol Monitoring Energy Conservation', a common method and database to calculate the amount of energy savings realised in past years. The institutes concerned are the Central Bureau of Statistics (CBS), the Netherlands Bureau for Economic Policy Analysis (CPB), the Energy research Centre of the Netherlands (ECN), the National Agency for Energy and Environment (Novem) and the Netherlands Institute of Public Health and the Environment (RIVM). The institutes have agreed upon a clear definition of energy use and energy savings. The demarcation with renewable energy, the saving effects of substitution between energy carriers and the role of import and export of energy have been elaborated. A decomposition method is used to split up the observed change in energy use in a number of effects, on a national and sectoral level. This method includes an analysis of growth effects, effects of structural changes in production and consumption activities and savings on end use or with more efficient conversion processes. To calculate these effects the total energy use is desegregated as much as possible. For each segment a reference energy use is calculated according to the trend in a variable which is supposed to be representative for the use without savings. The difference with the actual energy use is taken as the savings realised. Results are given for the sectors households, industry, agriculture, services and government, transportation and the energy sector; as well as a national figure. A special feature of the protocol method is the application of primary energy use figures in the determination of savings for end users. This means that the use of each energy carrier is increased with a certain amount, according to the conversion losses caused elsewhere in the energy system. The losses concern the base year energy sector and losses abroad for imports of secondary

  8. Design of tool monitor simulator

    International Nuclear Information System (INIS)

    Yao Yonggang; Deng Changming; Zhang Jia; Meng Dan; Zhang Lu; Wang Zhi'ai; Shen Yang

    2011-01-01

    It is based on tool monitor in Qinshan Nuclear Power Plant for the object of study, and manufacture a tool monitor simulator. The device is designed to automatically emulate-monitor the contamination level of objects for training students. Once if the tool monitor reports the contamination, the students can handle properly. The brief introduction of main function and system design of the simulator are presented in the paper. (authors)

  9. Monitoring in traumatic brain injury.

    Science.gov (United States)

    Matz, P G; Pitts, L

    1997-01-01

    In the past several years, improvements in technology have advanced the monitoring capabilities for patients with TBI. The primary goal of monitoring the patient with TBI is to prevent secondary insults to the brain, primarily cerebral ischemia. Cerebral ischemia may occur early and without clinical correlation and portends a poor outcome. Measurement of ICP is the cornerstone of monitoring in the patient with TBI. Monitoring of ICP provides a measurement of CPP and a rough estimation of CBF. However, with alterations in pressure autoregulation, measurement of CPP does not always allow for determination of CBF. To circumvent this problem, direct measurements of CBF can be performed using clearance techniques (133Xe, N2O, Xe-CT) or invasive monitoring techniques (LDF, TDF, NIRS). Although direct and quantitative, clearance techniques do not allow for continuous monitoring. Invasive CBF monitoring techniques are new, and artifactual results can be problematic. The techniques of jugular venous saturation monitoring and TCD are well established and are powerful adjuncts to ICP monitoring. They allow the clinician to monitor cerebral oxygen extraction and blood flow velocity, respectively, for any given CPP. Use of TCD may predict posttraumatic vasospasm before clinical sequelae. Jugular venous saturation monitoring may detect clinically occult episodes of cerebral ischemia and increased oxygen extraction. Jugular venous saturation monitoring optimizes the use of hyperventilation in the treatment of intracranial hypertension. Although PET and SPECT scanning allow direct measurement of CMRO2, these techniques have limited application currently. Similarly, microdialysis is in its infancy but has demonstrated great promise for metabolic monitoring. EEG and SEP are excellent adjuncts to the monitoring arsenal and provide immediate information on current brain function. With improvements in electronic telemetry, functional monitoring by EEG or SEP may become an important

  10. Monitoring Activities Review action report for the Environmental Monitoring Program

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.

    1990-12-01

    To improve program planning and to provide bases for technical improvement of the monitoring program, the EG ampersand G Environmental Monitoring (EM) organization has regularly used the Monitoring Activities Review (MAR) process since 1982. Each MAR is conducted by a committee of individuals selected for their experience in the various types of monitoring performed by the EM organization. An MAR of the Environmental Monitoring Program was conducted in 1988. This action report identifies and discusses the recommendations of this MAR committee. This action report also identifies the actions already taken by the EM Unit in response to these recommendations, as well as the actions and schedules to be taken. 10 refs

  11. Wireless transmission of monitoring data out of the Hades underground laboratory

    International Nuclear Information System (INIS)

    Schroeder, T.J.; Hart, J.

    2012-01-01

    Document available in extended abstract form only. For the monitoring of geological waste disposal in the post-closure phase, data acquired by the underground monitoring system inside the repository need to be transmitted wirelessly through the underground to the surface. Low frequency magneto-induction techniques as applied in mine communication and rescue can potentially be used for the wireless transmission of data from the repository to the surface. However, the propagation of magnetic fields through porous argillaceous rocks like the Boom Clay is hindered by the high electrical conductivity of the rock. As part of the European 7. framework project MoDeRn, Monitoring Developments for safe Repository operation and staged closure, NRG is conducting tests on the wireless transmission of monitoring data under conditions representative for a generic Dutch disposal in Boom Clay. This should help to judge the general feasibility of long-term wireless data transmission from an underground repository through the enclosing host rock and the overlying geosphere to the surface. Experimental work As contribution to the MoDeRn Work Package 3, In-situ demonstration of innovative monitoring techniques, NRG conducts tests on the wireless transmission of signals and data. The wireless data transmission experiments of NRG are being performed at the HADES Underground Research Laboratory (URL) in Mol, Belgium, situated at 225 m depth in a 100 m thick layer of Boom Clay. The main objective of the contribution is to quantify and optimise the energy efficiency of the transmission technique used. Because the Boom Clay and the overlying aquifers attenuate the magnetic fields more strongly than other host rocks, it is assumed that transmission experiments performed in the HADES give a more realistic picture on field propagation than experiments performed e.g. in granite, salt rock or Opalinus clay. Although the generic depth for the Dutch disposal design is 500 m, the experiments

  12. Integrated environmental monitoring -- prototype demonstration

    International Nuclear Information System (INIS)

    Bryce, R.W.; Vail, L.W.; Hostetler, D.D.; Meyer, P.D.; Carlson, T.J.; Miller, P.L.

    1994-01-01

    Groundwater monitoring is an important activity at US Department of Energy (DOE) sites. Monitoring programs at DOE facilities have evolved in response to operational needs at the facilities, public outcries for information, regulatory requirements, DOE orders, and improvements in monitoring technology. Decisions regarding sampling location, sampling frequency, analyses performed, and other aspects of monitoring network design can have major implications for detecting releases and for making subsequent higher level decisions about facility operation and remediation. The Integrated Environmental Monitoring (IEM) concept is a set of analytical procedures and software tools that can be used to improve monitoring network design decisions. Such decisions include the choice of monitoring locations, sampling frequencies, sensor technologies, and monitored constituents. IEM provides a set of monitoring alternatives that balance the tradeoffs between competing monitoring objectives such as the minimization of cost and the minimization of uncertainty. The alternatives provided are the best available with respect to the monitoring objectives, consistent with the physical and chemical characteristics of the site, and consist with applicable regulatory requirements. The selection of the best monitoring alternative to implement is made by the stakeholders after reviewing the alternatives and tradeoffs produced by the IEM process

  13. No-migration variance petition

    International Nuclear Information System (INIS)

    1990-03-01

    Volume V contains the appendices for: closure and post-closure plans; RCRA ground water monitoring waver; Waste Isolation Division Quality Program Manual; water quality sampling plan; WIPP Environmental Procedures Manual; sample handling and laboratory procedures; data analysis; and Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant

  14. No-migration variance petition. Appendices C--J: Volume 5, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    Volume V contains the appendices for: closure and post-closure plans; RCRA ground water monitoring waver; Waste Isolation Division Quality Program Manual; water quality sampling plan; WIPP Environmental Procedures Manual; sample handling and laboratory procedures; data analysis; and Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant.

  15. Islay LIMPET project monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Heath, T.

    2002-07-01

    Wavegen was contracted by the DTI as part of its Sustainable Energy Programmes to monitor and report on the final stages of the construction, installation of turbo-generation equipment, commissioning and operation of the LIMPET wave energy system. The report discusses the choice of technology, where the system was installed, power take off, construction of the collector, installation of the turbo-generator, maintenance, operation, management and planning issues. The performance of the system was found to be poorer than expected and the reasons for this were identified. The main conclusions were that the system is sufficiently robust to operate in the marine environment and downtimes are expected to be short.

  16. Mitigation Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    The Final Supplemental Environmental Impact Report (SEIR) (September 1992) for the Proposed Renewal of the Contract between the United States Department of Energy and The Regents of the University of California for the Operation and Management of the Lawrence Berkeley Laboratory identifies the environmental impacts associated with renewing the contract and specifies a series of measures designed to mitigate adverse impacts to the environment. This Mitigation Monitoring Plan describes the procedures the University will use to implement the mitigation measures adopted in connection with the approval of the Contract.

  17. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  18. NASA Lunar Impact Monitoring

    Science.gov (United States)

    Suggs, Robert M.; Moser, D. E.

    2015-01-01

    The MSFC lunar impact monitoring program began in 2006 in support of environment definition for the Constellation (return to Moon) program. Work continued by the Meteoroid Environment Office after Constellation cancellation. Over 330 impacts have been recorded. A paper published in Icarus reported on the first 5 years of observations and 126 calibrated flashes. Icarus: http://www.sciencedirect.com/science/article/pii/S0019103514002243; ArXiv: http://arxiv.org/abs/1404.6458 A NASA Technical Memorandum on flash locations is in press

  19. Fetal body movement monitoring.

    Science.gov (United States)

    Rayburn, W F

    1990-03-01

    Recording fetal activity serves as an indirect measure of central nervous system integrity and function. The coordination of whole body movement, which requires complex neurologic control, is likely similar to that of the newborn infant. Short-term observations of the fetus are best performed using real-time ultrasound imaging. Monitoring fetal motion has been shown to be clinically worthwhile in predicting impending death or compromise, especially when placental insufficiency is longstanding. The presence of a vigorous fetus is reassuring. Perceived inactivity requires a reassessment of any underlying antepartum complication and a more precise evaluation by fetal heart rate testing or real-time ultrasonography before delivery is contemplated.

  20. Radiation monitoring system

    International Nuclear Information System (INIS)

    Takeuchi, Nobuyoshi; Fujimoto, Toshiaki; Nagama, Hideyo

    2007-01-01

    A positive outlook toward nuclear power plants and a higher level of technologies for using radiation in the medical field are trends that are spreading throughout the world, and as a consequence, demand is increasing for equipment and systems that measure and control radiation. Equipment ranging from radiation detection and measurement devices to computer-based radiation management systems will be set up in overseas. Products that depend on overseas specifications based on IEC and other international standards are being developed. Fuji Electric is advancing the overseas deployment of radiation monitoring systems by adopting measures that will ensure the reliability and traceability of radiation equipment. (author)