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Sample records for basin in-situ decommissioning

  1. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs

  2. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material

  3. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and

  4. Sensor Network Demonstration for In Situ Decommissioning - 13332

    Energy Technology Data Exchange (ETDEWEB)

    Lagos, L.; Varona, J.; Awwad, A. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States); Rivera, J.; McGill, J. [Department of Energy - DOE, Environmental Management Office (United States)

    2013-07-01

    Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to

  5. Sensor Network Demonstration for In Situ Decommissioning - 13332

    International Nuclear Information System (INIS)

    Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensor systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to ensure that the

  6. Use of in-situ gamma spectroscopy during nuclear power plant decommissioning - 59340

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. One of the key objectives of the EPRI Decommissioning Technology Program is to capture the good practices and lessons learned from plants currently undergoing decommissioning. Several major plant decommissioning programs have been successfully completed, so EPRI is documenting relevant experiences to aid future decommissioning activities, both in the United States and internationally. In-situ Gamma Spectroscopy is powerful technology with the potential for widespread application in nuclear power plant radiological surveys. Due to leakage and other events that may occur during nuclear power plant operations, soil, concrete and bedrock have the potential to become contaminated, and therefore must be characterized to demonstrate that they meet strict regulatory site release limits. The radiological surveys conducted during power plant decommissioning have historically been very labor intensive, time consuming and often extend decommissioning duration. The use of hand-held survey meters was typical during early decommissioning. As engineers gained experience, they often replaced the hand-held meters with advanced technologies such as the In-situ Gamma Spectroscopy instruments

  7. USE OF CEMENTITIOUS MATERIALS FOR SRS REACTOR FACILITY IN-SITU DECOMMISSIONING - 11620

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Stefanko, D.; Serrato, M.; Blankenship, J.; Griffin, W.; Waymer, J.; Matheny, D.; Singh, D.

    2010-12-07

    The United States Department of Energy (US DOE) concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., producing (reactor facilities), processing (isotope separation facilities) or storing radioactive materials. The Savannah River Site 105-P and 105-R Reactor Facility ISD requires about 250,000 cubic yards of grout to fill the below grade structure. The fills are designed to prevent subsidence, reduce water infiltration, and isolate contaminated materials. This work is being performed as a Comprehensive Environmental Response, Compensations and Liability Act (CERCLA) action and is part of the overall soil and groundwater completion projects for P- and R-Areas. Cementitious materials were designed for the following applications: (1) Below grade massive voids/rooms: Portland cement-based structural flowable fills for - Bulk filling, Restricted placement and Underwater placement. (2) Special below grade applications for reduced load bearing capacity needs: Cellular portland cement lightweight fill (3) Reactor vessel fills that are compatible with reactive metal (aluminum metal) components in the reactor vessels: Calcium sulfoaluminate flowable fill, and Magnesium potassium phosphate flowable fill. (4) Caps to prevent water infiltration and intrusion into areas with the highest levels of radionuclides: Portland cement based shrinkage compensating concrete. A system engineering approach was used to identify functions and requirements of the fill and capping materials. Laboratory testing was performed to identify candidate formulations and develop final design mixes. Scale-up testing was performed to verify material production and placement as well as fresh and cured properties. The 105-P and 105-R ISD projects are currently in progress and are expected to be complete in 2012. The focus of this paper is to describe the (1) grout mixes

  8. In Situ Decommissioning Sensor Network, Meso-Scale Test Bed - Phase 3 Fluid Injection Test Summary Report

    International Nuclear Information System (INIS)

    The DOE Office of Environmental management (DOE EM) faces the challenge of decommissioning thousands of excess nuclear facilities, many of which are highly contaminated. A number of these excess facilities are massive and robust concrete structures that are suitable for isolating the contained contamination for hundreds of years, and a permanent decommissioning end state option for these facilities is in situ decommissioning (ISD). The ISD option is feasible for a limited, but meaningfull number of DOE contaminated facilities for which there is substantial incremental environmental, safety, and cost benefits versus alternate actions to demolish and excavate the entire facility and transport the rubble to a radioactive waste landfill. A general description of an ISD project encompasses an entombed facility; in some cases limited to the blow-grade portion of a facility. However, monitoring of the ISD structures is needed to demonstrate that the building retains its structural integrity and the contaminants remain entombed within the grout stabilization matrix. The DOE EM Office of Deactivation and Decommissioning and Facility Engineering (EM-13) Program Goal is to develop a monitoring system to demonstrate long-term performance of closed nuclear facilities using the ISD approach. The Savannah River National Laboratory (SRNL) has designed and implemented the In Situ Decommissioning Sensor Network, Meso-Scale Test Bed (ISDSN-MSTB) to address the feasibility of deploying a long-term monitoring system into an ISD closed nuclear facility. The ISDSN-MSTB goal is to demonstrate the feasibility of installing and operating a remote sensor network to assess cementitious material durability, moisture-fluid flow through the cementitious material, and resulting transport potential for contaminate mobility in a decommissioned closed nuclear facility. The original ISDSN-MSTB installation and remote sensor network operation was demonstrated in FY 2011-12 at the ISDSN-MSTB test cube

  9. In Situ Decommissioning Sensor Network, Meso-Scale Test Bed - Phase 3 Fluid Injection Test Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Serrato, M. G.

    2013-09-27

    The DOE Office of Environmental management (DOE EM) faces the challenge of decommissioning thousands of excess nuclear facilities, many of which are highly contaminated. A number of these excess facilities are massive and robust concrete structures that are suitable for isolating the contained contamination for hundreds of years, and a permanent decommissioning end state option for these facilities is in situ decommissioning (ISD). The ISD option is feasible for a limited, but meaningfull number of DOE contaminated facilities for which there is substantial incremental environmental, safety, and cost benefits versus alternate actions to demolish and excavate the entire facility and transport the rubble to a radioactive waste landfill. A general description of an ISD project encompasses an entombed facility; in some cases limited to the blow-grade portion of a facility. However, monitoring of the ISD structures is needed to demonstrate that the building retains its structural integrity and the contaminants remain entombed within the grout stabilization matrix. The DOE EM Office of Deactivation and Decommissioning and Facility Engineering (EM-13) Program Goal is to develop a monitoring system to demonstrate long-term performance of closed nuclear facilities using the ISD approach. The Savannah River National Laboratory (SRNL) has designed and implemented the In Situ Decommissioning Sensor Network, Meso-Scale Test Bed (ISDSN-MSTB) to address the feasibility of deploying a long-term monitoring system into an ISD closed nuclear facility. The ISDSN-MSTB goal is to demonstrate the feasibility of installing and operating a remote sensor network to assess cementitious material durability, moisture-fluid flow through the cementitious material, and resulting transport potential for contaminate mobility in a decommissioned closed nuclear facility. The original ISDSN-MSTB installation and remote sensor network operation was demonstrated in FY 2011-12 at the ISDSN-MSTB test cube

  10. Development of an In-Situ Decommissioning Sensor Network Test Bed for Structural Condition Monitoring - 12156

    International Nuclear Information System (INIS)

    The Savannah River National Laboratory (SRNL) has established an In Situ Decommissioning (ISD) Sensor Network Test Bed, a unique, small scale, configurable environment, for the assessment of prospective sensors on actual ISD system material, at minimal cost. The Department of Energy (DOE) is presently implementing permanent entombment of contaminated, large nuclear structures via ISD. The ISD end state consists of a grout-filled concrete civil structure within the concrete frame of the original building. Validation of ISD system performance models and verification of actual system conditions can be achieved through the development a system of sensors to monitor the materials and condition of the structure. The ISD Sensor Network Test Bed has been designed and deployed to addresses the DOE-Environmental Management Technology Need to develop a remote monitoring system to determine and verify ISD system performance. Commercial off-the-shelf sensors have been installed on concrete blocks taken from walls of the P Reactor Building at the Savannah River Site. Deployment of this low-cost structural monitoring system provides hands-on experience with sensor networks. The initial sensor system consists of groutable thermistors for temperature and moisture monitoring, strain gauges for crack growth monitoring, tilt-meters for settlement monitoring, and a communication system for data collection. Baseline data and lessons learned from system design and installation and initial field testing will be utilized for future ISD sensor network development and deployment. The Sensor Network Test Bed at SRNL uses COTS sensors on concrete blocks from the outer wall of the P Reactor Building to measure conditions expected to occur in ISD structures. Knowledge and lessons learned gained from installation, testing, and monitoring of the equipment will be applied to sensor installation in a meso-scale test bed at FIU and in future ISD structures. The initial data collected from the sensors

  11. Envisioning Communications with Future Stakeholders - A Case Study Using the In-Situ Decommissioning of P-Reactor

    International Nuclear Information System (INIS)

    This paper will explore opportunities to expand the CAB's public outreach by the incorporation of technologies typically used in social networks and distance learning. Envisioning opportunities to engage next generation CAB members in public involvement will be delineated by retracing the decision process used with the in-situ decommissioning of P-Reactor at the Savannah River Site (SRS). This paper will discuss existing opportunities to enable another group of stakeholders to take part in the environmental policy decision making process regarding the inclusion of some very long lived radioactive constituents. The aim of the paper will be to locate places in the current process where alternate or parallel informational dissemination pathways could exist. These alternatives will incorporate the next generation's expectation for instantaneous information and universal ownership of hand-held communication devices. The goal of this paper is to use the present framework of CAB communications and add the components of virtual networking and distance learning in hopes of bridging the generational technology gap and extending the dialog to future stakeholders. (authors)

  12. Blended Calcium Aluminate-Calcium Sulfate Cement-Based Grout For P-Reactor Vessel In-Situ Decommissioning

    International Nuclear Information System (INIS)

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH ≤ 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts (Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010). Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere (Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively). Radiolysis calculations are also provided in a separate document (Reyes-Jimenez, 2010).

  13. BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Stefanko, D.

    2011-03-10

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].

  14. In situ characterization of Hanford K Basins fuel

    International Nuclear Information System (INIS)

    Irradiated N Reactor uranium metal fuel is stored underwater in the Hanford K East and K West Basins. In K East Basin, fuel is stored in open canisters and defected fuel is free to react with the basin water. In K West Basin, the fuel is stored in sealed canisters filled with water containing a corrosion inhibitor (potassium nitrite). To gain a better understanding of the physical condition of the fuel in these basins, visual surveys using high resolution underwater cameras were conducted. The inspections included detailed lift and look examinations of a number of fuel assemblies from selected canisters in each basin. These examinations formed the bases for selecting specific fuel elements for laboratory testing and analyses as prescribed in the characterization plan for Hanford K Basin Spent Nuclear Fuel

  15. Comparison between in situ and ex situ gamma measurements on land areas within a decommissioning nuclear site: a case study at Dounreay.

    Science.gov (United States)

    Rostron, Peter D; Heathcote, John A; Ramsey, Michael H

    2014-09-01

    Measurements made in situ with gamma detectors and ex situ measurements of soil samples in a laboratory can have complementary roles in the assessment of radioactively contaminated land on decommissioning nuclear sites. Both in situ and ex situ methods were used to characterize (137)Cs contamination within an area at the Dounreay site in Scotland. The systematic difference (bias) between estimates of the mean activity concentration was found to be non-significant when in situ measurements were interpreted using a linear depth model, based on ex situ measurements made at two different depths. An established method of evaluating the random components of measurement uncertainty was used. The random component of analytical uncertainty in the in situ measurements, made in field conditions, was found to exceed that for the ex situ measurements, made in the controlled conditions of a laboratory. However, contamination by the target radionuclide was found to be heterogeneous over small spatial scales. This resulted in significantly higher levels of random sampling uncertainty in individual ex situ measurements. As in situ measurements are substantially less costly, a greater number of measurements can be made, which potentially reduces the uncertainty on the mean. Providing the depth profile of contaminants can be modelled with confidence, this can enable estimates of mean activity concentration over an averaging area to be made with lower overall uncertainties than are possible using ex situ methods. PMID:24938421

  16. Groundwater quality and depletion in the Indo-Gangetic Basin mapped from in situ observations

    Science.gov (United States)

    MacDonald, A. M.; Bonsor, H. C.; Ahmed, K. M.; Burgess, W. G.; Basharat, M.; Calow, R. C.; Dixit, A.; Foster, S. S. D.; Gopal, K.; Lapworth, D. J.; Lark, R. M.; Moench, M.; Mukherjee, A.; Rao, M. S.; Shamsudduha, M.; Smith, L.; Taylor, R. G.; Tucker, J.; van Steenbergen, F.; Yadav, S. K.

    2016-10-01

    Groundwater abstraction from the transboundary Indo-Gangetic Basin comprises 25% of global groundwater withdrawals, sustaining agricultural productivity in Pakistan, India, Nepal and Bangladesh. Recent interpretations of satellite gravity data indicate that current abstraction is unsustainable, yet these large-scale interpretations lack the spatio-temporal resolution required to govern groundwater effectively. Here we report new evidence from high-resolution in situ records of groundwater levels, abstraction and groundwater quality, which reveal that sustainable groundwater supplies are constrained more by extensive contamination than depletion. We estimate the volume of groundwater to 200 m depth to be >20 times the combined annual flow of the Indus, Brahmaputra and Ganges, and show the water table has been stable or rising across 70% of the aquifer between 2000 and 2012. Groundwater levels are falling in the remaining 30%, amounting to a net annual depletion of 8.0 +/- 3.0 km3. Within 60% of the aquifer, access to potable groundwater is restricted by excessive salinity or arsenic. Recent groundwater depletion in northern India and Pakistan has occurred within a longer history of groundwater accumulation from extensive canal leakage. This basin-wide synthesis of in situ groundwater observations provides the spatial detail essential for policy development, and the historical context to help evaluate recent satellite gravity data.

  17. In Situ Production of Branched Glycerol Dialkyl Glycerol Tetraethers in a Great Basin Hot Spring (USA

    Directory of Open Access Journals (Sweden)

    Chuanlun eZhang

    2013-07-01

    Full Text Available Branched glycerol dialkyl glycerol tetraethers (bGDGTs are predominantly found in soils and peat bogs. In this study, we analyzed core-bGDGTs and polar (P- bGDGTs after hydrolysis of polar fractions using liquid chromatography-atmospheric pressure chemical ionization-mass spectrometry and analyzed intact P-bGDGTs using total lipid extract (TLE without hydrolysis by liquid chromatography-electrospray ionization-multiple stage mass spectrometry. Our results show multiple lines of evidence for the production of bGDGTs in sediments and cellulolytic enrichments in a hot spring (62-86°C in the Great Basin (USA. First, in situ cellulolytic enrichment led to an increase in the relative abundance of hydrolysis-derived P-bGDGTs over their Core (C-bGDGT counterparts. Second, the hydrolysis-derived P- and C-bGDGT profiles in the hot spring were different from those of the surrounding soil samples; in particular, a monoglycosidic bGDGT Ib containing 13,16-dimethyloctacosane and one cyclopentane moiety was detected in the TLE but it was undetectable in surrounding soil samples even after sample enrichments. Third, previously published 16S rRNA gene pyrotag analysis from the same lignocellulose samples demonstrated the enrichment of thermophiles, rather than mesophiles, and total bGDGT abundance in cellulolytic enrichments correlated with the relative abundance of 16S rRNA gene pyrotags from thermophilic bacteria in the phyla Bacteroidetes, Dictyoglomi, EM3, and OP9 (Atribacteria. These observations conclusively demonstrate the production of bGDGTs in this hot spring; however, the identity of organisms that produce bGDGTs in the geothermal environment remains unclear.

  18. In situ stress and pore pressure in the Kumano Forearc Basin, offshore SW Honshu from downhole measurements during riser drilling

    Science.gov (United States)

    Saffer, D. M.; Flemings, P. B.; Boutt, D.; Doan, M.-L.; Ito, T.; McNeill, L.; Byrne, T.; Conin, M.; Lin, W.; Kano, Y.; Araki, E.; Eguchi, N.; Toczko, S.

    2013-05-01

    situ stress and pore pressure are key parameters governing rock deformation, yet direct measurements of these quantities are rare. During Integrated Ocean Drilling Program (IODP) Expedition #319, we drilled through a forearc basin at the Nankai subduction zone and into the underlying accretionary prism. We used the Modular Formation Dynamics Tester tool (MDT) for the first time in IODP to measure in situ minimum stress, pore pressure, and permeability at 11 depths between 729.9 and 1533.9 mbsf. Leak-off testing at 708.6 mbsf conducted as part of drilling operations provided a second measurement of minimum stress. The MDT campaign included nine single-probe (SP) tests to measure permeability and in situ pore pressure and two dual-packer (DP) tests to measure minimum principal stress. Permeabilities defined from the SP tests range from 6.53 × 10-17 to 4.23 × 10-14 m2. Pore fluid pressures are near hydrostatic throughout the section despite rapid sedimentation. This is consistent with the measured hydraulic diffusivity of the sediments and suggests that the forearc basin should not trap overpressures within the upper plate of the subduction zone. Minimum principal stresses are consistently lower than the vertical stress. We estimate the maximum horizontal stress from wellbore failures at the leak-off test and shallow MDT DP test depths. The results indicate a normal or strike-slip stress regime, consistent with the observation of abundant active normal faults in the seaward-most part of the basin, and a general decrease in fault activity in the vicinity of Site C0009.

  19. Past terrestrial water storage (1980–2008 in the Amazon Basin reconstructed from GRACE and in situ river gauging data

    Directory of Open Access Journals (Sweden)

    M. Becker

    2011-02-01

    Full Text Available Terrestrial water storage (TWS composed of surface waters, soil moisture, groundwater and snow where appropriate, is a key element of global and continental water cycle. Since 2002, the Gravity Recovery and Climate Experiment (GRACE space gravimetry mission provides a new tool to measure large-scale TWS variations. However, for the past few decades, direct estimate of TWS variability is accessible from hydrological modeling only. Here we propose a novel approach that combines GRACE-based TWS spatial patterns with multi-decadal-long in situ river level records, to reconstruct past 2-D TWS over a river basin. Results are presented for the Amazon Basin for the period 1980–2008, focusing on the interannual time scale. Results are compared with past TWS estimated by the global hydrological model ISBA-TRIP. Correlations between reconstructed past interannual TWS variability and known climate forcing modes over the region (e.g., El Niño-Southern Oscillation and Pacific Decadal Oscillation are also estimated. This method offers new perspective for improving our knowledge of past interannual TWS in world river basins where natural climate variability (as opposed to direct anthropogenic forcing drives TWS variations.

  20. In-situ analysis of solid bitumen in coal: Examples from the Bowen Basin and the Illinois Basin

    Science.gov (United States)

    Mastalerz, Maria; Glikson, M.

    2000-01-01

    Solid bitumen and associated vitrinite from selected coals from the Bowen Basin and the Illinois Basin were studied using electron microprobe and micro-FTIR techniques. The coal studied covers a range of vitrinite reflectance from 0.59% to 1.33%. Carbon content in the bitumen is generally lower than in vitrinite in coals with vitrinite reflectance below 0.67%. In coals with reflectance above 0.67%, carbon content of bitumen is higher than in vitrinite, reflecting higher aromaticity due to hydrocarbon generation. Sulfur and iron content are comparable between vitrinite and bitumen. Functional group distribution suggests the presence of two types of bitumen in the Illinois Basin coals. The more aliphatic variety occurring in veins and cleats is interpreted as pre-gas generation bitumen, and the more aromatic variety filling cells and voids in inertinite as post-gas generation bitumen. (C) 2000 Elsevier Science B.V. All rights reserved.Solid bitumen and associated vitrinite from selected coals from the Bowen Basin and the Illinois Basin were studied using electron microprobe and micro-FTIR techniques. The coal studied covers a range of vitrinite reflectance from 0.59% to 1.33%. Carbon content in the bitumen is generally lower than in vitrinite in coals with vitrinite reflectance below 0.67%. In coals with reflectance above 0.67%, carbon content of bitumen is higher than in vitrinite, reflecting higher aromaticity due to hydrocarbon generation. Sulfur and iron content are comparable between vitrinite and bitumen. Functional group distribution suggests the presence of two types of bitumen in the Illinois Basin coals. The more aliphatic variety occurring in veins and cleats is interpreted as pre-gas generation bitumen, and the more aromatic variety filling cells and voids in inertinite as post-gas generation bitumen.

  1. In situ and Enriched Microbial Community Composition and Function Associated with Coal Bed Methane from Powder River Basin Coals

    Science.gov (United States)

    Barnhart, Elliott; Davis, Katherine; Varonka, Matthew; Orem, William; Fields, Matthew

    2016-04-01

    Coal bed methane (CBM) is a relatively clean source of energy but current CBM production techniques have not sustained long-term production or produced enough methane to remain economically practical with lower natural gas prices. Enhancement of the in situ microbial community that actively generates CBM with the addition of specific nutrients could potentially sustain development. CBM production more than doubled from native microbial populations from Powder River Basin (PRB) coal beds, when yeast extract and several individual components of yeast extract (proteins and amino acids) were added to laboratory microcosms. Microbial populations capable of hydrogenotrophic (hydrogen production/utilization) methanogenesis were detected in situ and under non-stimulated conditions. Stimulation with yeast extract caused a shift in the community to microorganisms capable of acetoclastic (acetate production/utilization) methanogenesis. Previous isotope analysis from CBM production wells indicated a similar microbial community shift as observed in stimulation experiments: hydrogenotrophic methanogenesis was found throughout the PRB, but acetoclastic methanogenesis dominated major recharge areas. In conjunction, a high proportion of cyanobacterial and algal SSU rRNA gene sequences were detected in a CBM well within a major recharge area, suggesting that these phototrophic organisms naturally stimulate methane production. In laboratory studies, adding phototrophic (algal) biomass stimulated CBM production by PRB microorganisms similarly to yeast extract (~40μg methane increase per gram of coal). Analysis of the British thermal unit (BTU) content of coal from long-term incubations indicated >99.5% of BTU content remained after CBM stimulation with either algae or yeast extract. Biomimicry of in situ algal CBM stimulation could lead to technologies that utilize coupled biological systems (photosynthesis and methane production) that sustainably enhance CBM production and generate

  2. Geologic features of Wunite Erlian basin depression and prospecting analysis on in-situ sandstone-type uranium deposit

    International Nuclear Information System (INIS)

    Wunite depression located in the east of Erlian basin is one of the five biggest depressions in Erlian basin, and its sub-sags can be classified into two types: the units in depression zone and the other ones in uplift zone. Fluvial fan sedimentary-braided river system disposed at the former one, including vertical channel deposit model and centripetal channel deposit model: fan delta-lake system disposed at the later one, including fan deltas deposit model and braid river deltas deposit model. The main structure styles of sags are dustpan single-fault, composite single-fault, and composite double-fault. It is necessary to search these faults, in that the bottom slope belt of dustpan single-fault and composite single-fault is favorable for prospecting; the Saihantala sandstone which is at the two sides of the steep hill of composite single-fault and the sags of composite double-fault formed as monoclinal stratum. The sags featured by braid river deltas and vertical channel deposit model whose Saihantala sandstone possess modest thickness, fine stratification and connectivity, are favorable for prospecting in-situ sandstone-type Uranium deposit at Wunite zone. (authors)

  3. Evapotranspiration Estimation over Yangtze River Basin from GRACE satellite measurement and in situ data

    Science.gov (United States)

    Li, Qiong; Luo, Zhicai; Zhong, Bo; Wang, Haihong; Zhou, Zebing

    2016-04-01

    As the critical component of hydrologic cycle, evapotranspiration (ET) plays an important role in global water exchanges and energy flow across the hydrosphere, atmosphere and biosphere. Influenced by the Asian monsoon, the Yangtze River Basin (YRB) suffer from the several severe floods and droughts over the last decades due to the significant difference between temporal and spatial distribution terrestrial water storages. As an indispensable part, it is practically important to assessment ET in the YRB accompany with increased population and rapid economic and agriculture development. Average ET over the YRB is computed as the residual of terrestrial water budget using the Gravity Recovery and Climate Experiment (GRACE) satellite-based measurements and the ground-based observations. The GRACE-based ET were well coincidence with the ET from MODIS, with the correlation coefficient of 0.853, and the correlation coefficient is 0.696 while comparing with the ET ground-based observation. The mean monthly average of ET from these various estimates is 56.9 mm/month over the whole YRB, and peak between June and August. Monthly variations of ET reach a maximum in Wujiang with 69.11 mm/month and a minimum in Jinshajiang with 39.01 mm/month. Based on the correlation between ET and independent estimates of near-surface temperature and soil moisture, it is showed that as the temperature increased, the ET of the seven sub-catchment were rising except for the Poyang Lake and Donting Lake. And we also can infer that the midstream of YRB is significant correlated with ESON especially in the Hanjiang basin. The Surface Humidity Index over the YRB was gradually decreased and its variations in each sub-catchment showed a significant decreasing trend in Jinshajiang and Mingjiang. This research has important potential for use in large-scale water budget assessments and intercomparison studies. Acknowledgements: This research is supported by the National Natural Science Foundation of

  4. Decommissioning Handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  5. Evaluation of the ISBA-TRIP continental hydrologic system over the Niger basin using in situ and satellite derived datasets

    Science.gov (United States)

    Pedinotti, V.; Boone, A.; Decharme, B.; Crétaux, J. F.; Mognard, N.; Panthou, G.; Papa, F.; Tanimoun, B. A.

    2012-06-01

    During the 1970s and 1980s, West Africa has faced extreme climate variations with extended drought conditions. Of particular importance is the Niger basin, since it traverses a large part of the Sahel and is thus a critical source of water for an ever-increasing local population in this semi arid region. However, the understanding of the hydrological processes over this basin is currently limited by the lack of spatially distributed surface water and discharge measurements. The purpose of this study is to evaluate the ability of the ISBA-TRIP continental hydrologic system to represent key processes related to the hydrological cycle of the Niger basin. ISBA-TRIP is currently used within a coupled global climate model, so that the scheme must represent the first order processes which are critical for representing the water cycle while retaining a limited number of parameters and a simple representation of the physics. To this end, the scheme uses first-order approximations to account explicitly for the surface river routing, the floodplain dynamics, and the water storage using a deep aquifer reservoir. In the current study, simulations are done at a 0.5 by 0.5° spatial resolution over the 2002-2007 period (in order to take advantage of the recent satellite record and data from the African Monsoon Multidisciplinary Analyses project, AMMA). Four configurations of the model are compared to evaluate the separate impacts of the flooding scheme and the aquifer on the water cycle. Moreover, the model is forced by two different rainfall datasets to consider the sensitivity of the model to rainfall input uncertainties. The model is evaluated using in situ discharge measurements as well as satellite derived flood extent, total continental water storage changes and river height changes. The basic analysis of in situ discharges confirms the impact of the inner delta area, known as a significant flooded area, on the discharge, characterized by a strong reduction of the

  6. Evaluation of the ISBA-TRIP continental hydrologic system over the Niger basin using in situ and satellite derived datasets

    Directory of Open Access Journals (Sweden)

    V. Pedinotti

    2012-06-01

    Full Text Available During the 1970s and 1980s, West Africa has faced extreme climate variations with extended drought conditions. Of particular importance is the Niger basin, since it traverses a large part of the Sahel and is thus a critical source of water for an ever-increasing local population in this semi arid region. However, the understanding of the hydrological processes over this basin is currently limited by the lack of spatially distributed surface water and discharge measurements. The purpose of this study is to evaluate the ability of the ISBA-TRIP continental hydrologic system to represent key processes related to the hydrological cycle of the Niger basin. ISBA-TRIP is currently used within a coupled global climate model, so that the scheme must represent the first order processes which are critical for representing the water cycle while retaining a limited number of parameters and a simple representation of the physics. To this end, the scheme uses first-order approximations to account explicitly for the surface river routing, the floodplain dynamics, and the water storage using a deep aquifer reservoir. In the current study, simulations are done at a 0.5 by 0.5° spatial resolution over the 2002–2007 period (in order to take advantage of the recent satellite record and data from the African Monsoon Multidisciplinary Analyses project, AMMA. Four configurations of the model are compared to evaluate the separate impacts of the flooding scheme and the aquifer on the water cycle. Moreover, the model is forced by two different rainfall datasets to consider the sensitivity of the model to rainfall input uncertainties. The model is evaluated using in situ discharge measurements as well as satellite derived flood extent, total continental water storage changes and river height changes. The basic analysis of in situ discharges confirms the impact of the inner delta area, known as a significant flooded area, on the discharge, characterized by a strong

  7. Comparison of Vertical Distributions of Prokaryotic Assemblages in the Anoxic Cariaco Basin and Black Sea by Use of Fluorescence In Situ Hybridization†

    Science.gov (United States)

    Lin, Xueju; Wakeham, Stuart G.; Putnam, Isabell F.; Astor, Yrene M.; Scranton, Mary I.; Chistoserdov, Andrei Y.; Taylor, Gordon T.

    2006-01-01

    Individual prokaryotic cells from two major anoxic basins, the Cariaco Basin and the Black Sea, were enumerated throughout their water columns using fluorescence in situ hybridization (FISH) with the fluorochrome Cy3 or horseradish peroxidase-modified oligonucleotide probes. For both basins, significant differences in total prokaryotic abundance and phylogenetic composition were observed among oxic, anoxic, and transitional (redoxcline) waters. Epsilon-proteobacteria, Crenarchaeota, and Euryarchaeota were more prevalent in the redoxclines, where previous studies reported high rates of chemoautotrophic production relative to those in waters above and below the redoxclines. Relative abundances of Archaea in both systems varied between 1% and 28% of total prokaryotes, depending on depth. The prokaryotic community composition varied between the two anoxic basins, consistent with distinct geochemical and physical conditions. In the Black Sea, the relative contributions of group I Crenarchaeota (median, 5.5%) to prokaryotic communities were significantly higher (P < 0.001; n = 20) than those of group II Euryarchaeota (median, 2.9%). In contrast, their proportions were nearly equivalent in the Cariaco Basin. Beta-proteobacteria were unexpectedly common throughout the Cariaco Basin's water column, accounting for an average of 47% of 4′,6′-diamidino-2-phenylindole (DAPI)-stained cells. This group was below the detection limit (<1%) in the Black Sea samples. Compositional differences between basins may reflect temporal variability in microbial populations and/or systematic differences in environmental conditions and the populations for which they select. PMID:16597973

  8. Decommissioning handbook

    Energy Technology Data Exchange (ETDEWEB)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  9. Decommissioning handbook

    International Nuclear Information System (INIS)

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained

  10. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the United Kingdom, good progress has been made with the Windscale Advanced Gas-cooled Reactor and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level. (author)

  11. Analysis of MODIS LST Compared with WRF Model and in situ Data over the Waimakariri River Basin, Canterbury, New Zealand

    OpenAIRE

    Peyman Zawar-Reza; Wolfgang Rack; Mohammad Sohrabinia

    2012-01-01

    In this study we examine the relationship between remotely sensed, in situ and modelled land surface temperature (LST) over a heterogeneous land-cover (LC) enclosed in alpine terrain. This relationship can help to understand to what extent the remotely sensed data can be used to improve model simulations of land surface parameters such as LST in mountainous areas. LST from the MODerate resolution Imaging Spectro-radiometer (MODIS), the modelled surface skin temperature by the Weather Research...

  12. 1982 international decommissioning symposium

    International Nuclear Information System (INIS)

    Sixty-four papers were presented at the following sessions: policy, regulations, and standards; management of decommissioning wastes; decommissioning experience; decommissioning tooling and techniques; radiological concerns; and planning and engineering

  13. Image feature and recognition of prospective section of in-situ leachable sandstone-type uranium deposits at southern margin of Yili basin

    International Nuclear Information System (INIS)

    The author describes the secondary development of scientific experimental satellite photograph, the three-dimension stereo simulation display and the elaboration principle, methods and procedures of multi-parameter extraction. At the same time, the image features of prospective areas for in-situ leachable sandstone-type uranium deposits in Yili basin on different type images are comprehensively studied, the geological implication and significance of image features are analysed, and recognition of image features for prospective areas is made. On the basis of above research achievements, three-grade prediction, i.e. the regional metallogenic prediction, the selection of prospective area, and the selection of favorable mineralized site, is performed, and good verification results have been obtained

  14. Placing Absolute Timing on Basin Incision Adjacent to the Colorado Front Range: Results from Meteoric and in Situ 10BE Dating

    Science.gov (United States)

    Duehnforth, M.; Anderson, R. S.; Ward, D.

    2010-12-01

    A sequence of six levels of gravel-capped surfaces, mapped as Pliocene to Holocene in age, are cut into Cretaceous shale in the northwestern part of the Denver Basin immediately adjacent to the Colorado Front Range (CFR). The existing relative age constraints and terrace correlations suggest that the incision of the Denver Basin occurred at a steady and uniform rate of 0.1 mm yr-1 since the Pliocene. As absolute ages in this landscape are rare, they have the potential to test the reliability of the existing chronology, and to illuminate the detailed history of incision. We explore the timing of basin incision and the variability of geomorphic process rates through time by dating the three highest surfaces at the northwestern edge of the Denver Basin using both in situ and meteoric 10Be concentrations. As the tectonic conditions have not changed since the Pliocene, much of the variability of generation and abandonment of alluvial surfaces likely reflects the influence of glacial-interglacial climate variations. We selected Gunbarrel Hill (mapped as pre-Rocky Flats (Pliocene)), Table Mountain (mapped as Rocky Flats (early Pleistocene)), and the Pioneer surface (mapped as Verdos (Pleistocene, ~640 ka)) as sample locations. We took two amalgamated clast samples on the Gunbarrel Hill surface, and dated depth profiles using meteoric and in situ 10Be on the Table Mountain and Pioneer surfaces. In addition, we measured the in situ 10Be concentrations of 6 boulder samples from the Table Mountain surface. We find that all three surfaces are significantly younger than expected and that in situ and meteoric age measurements largely agree with each other. The samples from the pre-Rocky Flats site (Gunbarrel Hill) show ages of 250 and 310 ka, ignoring post-depositional surface erosion. The ages of the Table Mountain and Pioneer sites fall within the 120 to 150 ka window. These absolute ages overlap with the timing of the penultimate glaciation during marine isotope stage (MIS) 6

  15. A rapid in situ method for determining the ages of uranium oxide minerals: Evolution of the Cigar Lake deposit, Athabasca Basin

    International Nuclear Information System (INIS)

    The authors present a rapid and accurate technique for making in situ U-Pb isotopic measurements of uranium oxide minerals that utilizes both electron and ion microprobes. U and Pb concentrations are determined using an electron microprobe, whereas the isotopic composition of Pb for the same area is measured using a high-resolution ion microprobe. The advantages of this approach are: mineral separation and chemical digestion are unnecessary; homogeneous uranium oxide standards, which are difficult to obtain, are not required; and precise and accurate U-Pb ages on ∼10 microm spots can be obtained in a matter of hours. The authors have applied their method to study the distribution of U-Pb ages in complexly intergrown uranium oxides from the unconformity-type Cigar Lake uranium deposit, Saskatchewan, Canada. In situ U-Pb results from early formed uraninite define a well-correlated array on concordia with upper and lower intercepts of 1,467 ± 63 Ma and 443 ± 96 Ma (±1σ), respectively. The 1,467 Ma age is interpreted as the minimum age of mineralization and is consistent with the age of clay-mineral alteration (approximately1477 Ma) and magnetization of diagenetic hematite (1,650 to 1,450 Ma) that is associated with these unconformity-type uranium deposits and early diagenesis of the Athabasca Basin sediments. In situ U-Pb isotopic analysis of uraninite and coffinite can document the Pb*/U heterogeneities that can occur on a scale of 15 to 30 microm, thus providing relatively accurate information regarding the timing of fluid interactions associated with the evolution of these deposits

  16. Workshop on decommissioning

    International Nuclear Information System (INIS)

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  17. Characteristic of In Situ Stress and Its Control on the Coalbed Methane Reservoir Permeability in the Eastern Margin of the Ordos Basin, China

    Science.gov (United States)

    Zhao, Junlong; Tang, Dazhen; Xu, Hao; Li, Yong; Li, Song; Tao, Shu; Lin, Wenji; Liu, Zhenxing

    2016-08-01

    Coalbed methane (CBM) development faces many challenges, among which in situ stress and permeability are two of the most important and fundamental factors. Knowledge of the characteristics of these factors is crucial to CBM exploration and development. Based on measured injection/falloff and in situ stress well test data of 55 CBM wells in the eastern margin of the Ordos Basin, correlations between parameters including initial reservoir pressure, in situ stress, lateral stress coefficient, well test permeability, and burial depth were determined. The distribution of in situ stress was analyzed systematically and its influence on permeability was also addressed. The results indicate that the maximum horizontal principal stress ( σ H 10.13-37.84 MPa, average 22.50 MPa), minimum horizontal principal stress ( σ h 6.98-26.88 MPa, average 15.04 MPa) and vertical stress ( σ v 12.30-35.72 MPa, average 22.48 MPa) all have positive correlations with coal burial depth. Stress ratios ( σ H/ σ h, σ H/ σ v, and σ h/ σ v) and lateral stress coefficient slowly attenuated with depth. With increase of horizontal principal stresses, coal reservoir permeability (0.01-3.33 mD, average 0.65 mD) decreases. The permeability variation is basically consistent with change of stress state at a certain burial depth, the essence of which is the deformation and destruction of coal pore structures under the action of stresses. Three types of stress fields exist in the area: in the shallow coal seam at burial depths σ v > σ h), with average permeability 0.89 mD; from 700 to 1000 m depths, there is a stress transition zone ( σ H ≈ σ v > σ h) with average permeability 0.73 mD; in the deep coal seam with burial depths >1000 m, the vertical principal stress is dominant, demonstrating a normal stress regime ( σ v > σ H > σ h) with average permeability 0.11 mD.

  18. Evaluation of Groundwater Storage changes at Konya Closed Basin, Turkey using GRACE-based and in-situ measurements

    Science.gov (United States)

    Kamil Yilmaz, Koray; Saber, Mohamed; Tugrul Yilmaz, Mustafa

    2016-04-01

    The Konya Closed Basin (KCB) located in Central Anatolia, Turkey, is the primary grain producer in Turkey. The lack of sufficient surface water resources and recently changing crop patterns have led to over-exploitation of groundwater resources and resulted in significant drop in groundwater levels. For this reason monitoring of the groundwater storage change in this region is critical to understand the potential of the current water resources and to devise effective water management strategies to avoid further depletion of the groundwater resources. Therefore, the main objective of this study is to examine and assess the utility of the Gravity Recovery and Climate Experiment (GRACE) and the Global Land Data Assimilation System (GLDAS) to monitor and investigate the groundwater storage changes in the Konya Closed Basin. Groundwater storage changes are derived using GRACE and GLDAS data and then are compared with the groundwater changes derived from the observed groundwater levels. The initial results of the comparison indicate an acceptable agreement between declining trends in GRACE-based and observed groundwater storage change during the study time period (2002 to 2015). Additionally, the results indicated that the study region exhibited remarkable drought conditions during 2007-2008 period. This study shows that the GRACE/GLDAS datasets can be used to monitor the equivalent groundwater storage changes which is crucial for long-term effective water management strategies.

  19. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Present concepts on stages of, designing for and costs of decommissioning, together with criteria for site release, are described. Recent operations and studies and assessments in progress are summarized. Wastes from decommissioning are characterized

  20. Utility planning for decommissioning

    International Nuclear Information System (INIS)

    Though the biggest impact on a utility of nuclear power plant decommissioning may occur many years from now, procrastination of efforts to be prepared for that time is unwarranted. Foresight put into action through planning can significantly affect that impact. Financial planning can assure the recovery of decommissioning costs in a manner equitable to customers. Decision-making planning can minimize adverse affects of current decisions on later decommissioning impacts and prepare a utility to be equipped to make later decommissioning decisions. Technological knowledge base planning can support all other planning aspects for decommissioning and prepare a utility for decommissioning decisions. Informed project planning can ward off potentially significant pitfalls during decommissioning and optimize the effectiveness of the actual decommissioning efforts

  1. Decommissioning of a mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Decommissioning of the coprecipitation plant, which made plutonium/uranium oxide fuel, is a lead project in the BNFL Sellafield decommissioning programme. The overall programme has the objectives of gaining data and experience in a wide range of decommissioning operations and hence in this specific project to pilot the decommissioning of plant heavily contaminated with plutonium and other actinides. Consequently the operations have been used to test improvements in temporary containment, contamination control and decontamination methods and also to develop in situ plutonium assay, plutonium recovery and size-reduction methods. Finally the project is also yielding data on manpower requirements, personnel radiation uptake and waste arisings to help in the planning of future decommissioning projects

  2. Temporal variation of soil moisture over the Wuding River basin assessed with an eco-hydrological model, in-situ observations and remote sensing

    Science.gov (United States)

    Liu, S.; Mo, X.; Zhao, W.; Naeimi, V.; Dai, D.; Shu, C.; Mao, L.

    2009-07-01

    The change pattern and trend of soil moisture (SM) in the Wuding River basin, Loess Plateau, China is explored based on the simulated long-term SM data from 1956 to 2004 using an eco-hydrological process-based model, Vegetation Interface Processes model, VIP. In-situ SM observations together with a remotely sensed SM dataset retrieved by the Vienna University of Technology are used to validate the model. In the VIP model, climate-eco-hydrological (CEH) variables such as precipitation, air temperature and runoff observations and also simulated evapotranspiration (ET), leaf area index (LAI), and vegetation production are used to analyze the soil moisture evolution mechanism. The results show that the model is able to capture seasonal SM variations. The seasonal pattern, multi-year variation, standard deviation and coefficient of variation (CV) of SM at the daily, monthly and annual scale are well explained by CEH variables. The annual and inter-annual variability of SM is the lowest compared with that of other CEH variables. The trend analysis shows that SM is in decreasing tendency at α=0.01 level of significance, confirming the Northern Drying phenomenon. This trend can be well explained by the decreasing tendency of precipitation (α=0.1) and increasing tendency of temperature (α=0.01). The decreasing tendency of runoff has higher significance level (α=0.001). Because of SM's decreasing tendency, soil evaporation (ES) is also decreasing (α=0.05). The tendency of net radiation (Rn), evapotranspiration (ET), transpiration (EC), canopy intercept (EI) is not obvious. Net primary productivity (NPP), of which the significance level is lower than α=0.1, and gross primary productivity (GPP) at α=0.01 are in increasing tendency.

  3. Training for decommissioning

    International Nuclear Information System (INIS)

    Plants entering decommissioning face many challenges One of the most important is the challenge of training for decommissioning This is important because: The facility operators and management have spent many years successfully operating the facility; The facility management arrangements are geared to operation; Decommissioning will include non-nuclear specialists and other stakeholders; Other skills are needed to decommission successfully. UKAEA has decommissioned many facilities at its sites in Dounreay, Windscale, Harwell and Winfrith in the UK. We have faced all of the challenges previously described and have developed many training methods for ensuring the challenges are met safely and effectively. We have developed courses for specialised skills such as safety cases which can be deployed to support any decommissioning. (author)

  4. Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Atomic Energy Regulatory Board (AERB) is of the view that every organisation should focus attention on the decommissioning of nuclear facilities after completion of their useful life. AERB is aware that, internationally there is a growing interest in plant life extension due to economic considerations. Regulatory bodies stipulate upgradation of safety features based on international experience and current safety standards. However, decommissioning becomes a necessity at some time after the extended life of the plant. Nuclear industry has demonstrated that, with modern technological developments, decommissioning of nuclear facilities can be carried out without undue risk to the occupational workers, members of the public and protection of the environment. In view of limited experience in the field of decommissioning, this document is being issued as a safety manual instead of a safety guide. This manual elaborates the various technical and safety considerations in the decommissioning of nuclear facilities including ultimate disposal of radioactive materials/ wastes generated during decommissioning. Details that are required to be furnished to the regulatory body while applying for authorisation for decommissioning and till its completion are enumerated. This manual is issued to assist Department of Atomic Energy (DAE) units in formulating a decommissioning programme. Since the subject of decommissioning of nuclear facilities is a continuously evolving process, AERB is of the view, that provisions of this manual will apply for a period of five years from the date of issue and will be subsequently revised, if necessary

  5. Temporal variation of soil moisture over the Wuding River basin assessed with an eco-hydrological model, in-situ observations and remote sensing

    Directory of Open Access Journals (Sweden)

    C. Shu

    2009-07-01

    Full Text Available The change pattern and trend of soil moisture (SM in the Wuding River basin, Loess Plateau, China is explored based on the simulated long-term SM data from 1956 to 2004 using an eco-hydrological process-based model, Vegetation Interface Processes model, VIP. In-situ SM observations together with a remotely sensed SM dataset retrieved by the Vienna University of Technology are used to validate the model. In the VIP model, climate-eco-hydrological (CEH variables such as precipitation, air temperature and runoff observations and also simulated evapotranspiration (ET, leaf area index (LAI, and vegetation production are used to analyze the soil moisture evolution mechanism. The results show that the model is able to capture seasonal SM variations. The seasonal pattern, multi-year variation, standard deviation and coefficient of variation (CV of SM at the daily, monthly and annual scale are well explained by CEH variables. The annual and inter-annual variability of SM is the lowest compared with that of other CEH variables. The trend analysis shows that SM is in decreasing tendency at α=0.01 level of significance, confirming the Northern Drying phenomenon. This trend can be well explained by the decreasing tendency of precipitation (α=0.1 and increasing tendency of temperature (α=0.01. The decreasing tendency of runoff has higher significance level (α=0.001. Because of SM's decreasing tendency, soil evaporation (ES is also decreasing (α=0.05. The tendency of net radiation (Rn, evapotranspiration (ET, transpiration (EC, canopy intercept (EI is not obvious. Net primary productivity (NPP, of which the significance level is lower than α=0.1, and gross primary productivity (GPP at α=0.01 are in increasing tendency.

  6. International Decommissioning Strategies

    International Nuclear Information System (INIS)

    The IAEA has been developing guidance and technical information relating to the decommissioning and decommissioning strategies of nuclear facilities for over 20 years. During this time, the international concept of decommissioning strategies, and its importance, has changed. Three basic decommissioning strategies are envisaged as possibilities for nuclear installations: immediate dismantling, deferred dismantling and entombment. All have advantages and disadvantages, but the International Conference on Safe Decommissioning for Nuclear Activities demonstrated that immediate dismantling is the generally preferred option. However, there are a number of factors that might lead operators to choose one of the other strategies, and each situation has to be examined individually to identify the optimal strategy for that situation. The basic approach of these three strategies is discussed in the paper. (author)

  7. Decommissioning U.K. power stations

    International Nuclear Information System (INIS)

    The strategy for decommissioning U.K. commercial nuclear power stations at the end of their operating lives has hitherto been based on early partial dismantling and clearance to green-field site after about 100 years. This strategy involves a considerable financial liability particularly in the early years following shutdown of the stations. In 1990 Nuclear Electric identified the potential for significantly reducing this liability by reviewing a range of alternative strategies for decommissioning. This review has now been completed by Nuclear Electric and this paper describes the background to it, the review itself and the conclusions. As a result Nuclear Electric are now proposing to adopt a new strategy, referred to as the ''Deferred Safestore strategy'' for all its gas-cooled power stations. This does not involve any significant active dismantling until about 135 years after shutdown, allowing radioactivity levels in the plant to decay to very low levels in-situ. Following defuelling, an initial care and maintenance phase of about 30 years occurs followed by construction of containments (Safestores) around all buildings containing active plant. The purpose of these is to protect the buildings and their contents from deterioration due to weathering for a further 100 years. Complete dismantling is carried out after that time. An alternative option at that time, with further considerable cost savings, could be In-situ decommissioning. (Author)

  8. Time-variations of equivalent water heights'from Grace Mission and in-situ river stages in the Amazon basin Variações temporais do equivalente à altura d'água obtidas da Missão Grace e da altura d'água in-situ nos rios da bacia Amazônica

    Directory of Open Access Journals (Sweden)

    Flavio Guilherme Vaz de Almeida

    2012-03-01

    Full Text Available Gravity Recovery and Climate Experiment (GRACE mission is dedicated to measuring temporal variations of the Earth's gravity field. In this study, the Stokes coefficients made available by Groupe de Recherche en Géodésie Spatiale (GRGS at a 10-day interval were converted into equivalent water height (EWH for a ~4-year period in the Amazon basin (from July-2002 to May-2006. The seasonal amplitudes of EWH signal are the largest on the surface of Earth and reach ~ 1250mm at that basin's center. Error budget represents ~130 mm of EWH, including formal errors on Stokes coefficient, leakage errors (12 ~ 21 mm and spectrum truncation (10 ~ 15 mm. Comparison between in situ river level time series measured at 233 ground-based hydrometric stations (HS in the Amazon basin and vertically-integrated EWH derived from GRACE is carried out in this paper. Although EWH and HS measure different water bodies, in most of the cases a high correlation (up to ~80% is detected between the HS series and EWH series at the same site. This correlation allows adjusting linear relationships between in situ and GRACE-based series for the major tributaries of the Amazon river. The regression coefficients decrease from up to down stream along the rivers reaching the theoretical value 1 at the Amazon's mouth in the Atlantic Ocean. The variation of the regression coefficients versus the distance from estuary is analysed for the largest rivers in the basin. In a second step, a classification of the proportionality between in situ and GRACE time-series is proposed.A missão espacial Gravity Recovery and Climate Experiment (GRACE é dedicada às medidas das variações temporais no campo gravitacional da Terra. Neste estudo, os coeficientes de Stokes disponibilizados pelo Groupe de Recherche en Géodésie Spatiale (GRGS com intervalos de 10 dias foram convertidos no equivalente à altura d'água (EWH para um período de 4 anos na bacia Amazônica (de julho de 2002 a maio de 2006

  9. Decommissioning Russian Research Facilities

    International Nuclear Information System (INIS)

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety of nuclear research facilities (RR), including research reactors, critical assemblies and sub-critical assemblies. Most of the Russian RR were built and put in operation more than 30 years ago. The problems of ageing equipment and strengthening of safety requirements in time, the lack of further experimental programmes and financial resources, have created a condition when some of the RR were forced to take decisions on their decommissioning. The result of these problems was reflected in reducing the number of RR from 113 in 1998 to 81 in the current year. At present, seven RR are already under decommissioning or pending it. Last year, the Ministry of Atomic Energy took the decision to finally shut down two remaining actual research reactors in the Physics and Power Engineering Institute in Obninsk: AM-1, the first reactor in the world built for peaceful purposes, graphite-type reactor, and the fast liquid metal reactor BR-10, and to start their preparation for decommissioning. It is not enough just to declare the decommissioning of a RR: it is also vital to find financial resources for that purpose. For this reason, due to lack of financing, the MR reactor at the Kurchatov Institute has been pending decommissioning since 1992 and still is. The other example of long-lasting decommissioning is TVR, a heavy water reactor at the Institute of Theoretical Physics in Moscow (ITEF). The reason is also poor financing. Another example discussed in the paper concerns on-site disposal of a RR located above the Arctic Pole Circle, owned by the Norilsk Mining Company. Furthermore, the experience of the plutonium reactor decommissioning at the Joint Institute of Nuclear Research is also discussed. As shown, the Russian Federation has had good experiences in the decommissioning of nuclear research facilities. (author)

  10. Improvement of the free-surface tension model in shallow water basin by using in-situ bottom-friction measurements

    Science.gov (United States)

    Alekseenko, Elena; Kuznetsov, Konstantin; Roux, Bernard

    2016-04-01

    Wind stress on the free surface is the main driving force behind the circulation of the upper part of the ocean, which in hydrodynamic models are usually defined in terms of the coefficient of surface tension (Zhang et al., 2009, Davies et al., 2003). Moreover, wave motion impacts local currents and changes sea level, impacts the transport and the stratification of the entire water column. Influence of surface waves at the bottom currents is particularly pronounced in the shallow coastal systems. However, existing methods of parameterization of the surface tension have significant limits, especially in strong wind waves (Young et al., 2001, Jones et al., 2004) due to the difficulties of measuring the characteristics of surface waves in stormy conditions. Thus, the formula for calculating the coefficient of surface tension in our day is the actual problem in modeling fluid dynamics, particularly in the context of strong surface waves. In the hydrodynamic models usually a coefficient of surface tension is calculated once at the beginning of computation as a constant that depends on the averaged wind waves characteristic. Usually cases of strongly nonlinear wind waves are not taken into account, what significantly reduces the accuracy of the calculation of the flow structures and further calculation of the other processes in water basins, such as the spread of suspended matter and pollutants. Thus, wave motion influencing the pressure on the free surface and at the bottom must be considered in hydrodynamic models particularly in shallow coastal systems. A method of reconstruction of a free-surface drag coefficient based on the measured in-situ bottom pressure fluctuations is developed and applied in a three-dimensional hydrodynamic model MARS3D, developed by the French laboratory of IFREMER (IFREMER - French Research Institute for Marine Dynamics). MARS3D solves the Navier-Stokes equations for incompressible fluid in the Boussinesq approximation and with the

  11. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  12. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

  13. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  14. Decommissioning in western Europe

    International Nuclear Information System (INIS)

    This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe and waterproof conditions for a longer period of

  15. Financial aspects of decommissioning

    International Nuclear Information System (INIS)

    European Commission adopted recently two proposals of Directives designed to pave the way for a Community approach to the safety of nuclear power plants and the processing of radioactive waste. Nuclear safety cannot be guaranteed without making available adequate financial resources. With regard, in particular, to the decommissioning of nuclear facilities, the Directive defines the Community rules for the establishment, management and use of decommissioning funds allocated to a body with legal personality separate from that of the nuclear operator. In order to comply with the acquis communautaire, Romanian Government issued the Emergency Ordinance no. 11/2003 which set up the National Agency for Radioactive Waste (ANDRAD) and soon will be established the financial mechanism for raising the necessary funds. Societatea Nationala 'Nuclearelectrica' S.A. operates, through one of its branches, Cernavoda NPP Unit 1 and has to prepare its decommissioning strategy and to analyze the options to assure the financing for covering the future costs. The purpose of this paper is to clarify the financial systems' mechanisms to the satisfaction of the nuclear operator obligations, according to the disbursement schedule foreseen by decommissioning projects . The availability of cash to pay for all the decommissioning expenditure must be foreseen by setting up assets and establishing a suitable financing plan. The different practices of assets management shall be presented in this paper on the basis of the international experience. Some calculation samples shall be given as an illustration. (author)

  16. Decommissioning funding: ethics, implementation, uncertainties

    International Nuclear Information System (INIS)

    This status report on Decommissioning Funding: Ethics, Implementation, Uncertainties also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). The report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems. (authors)

  17. Site decommissioning management plan

    Energy Technology Data Exchange (ETDEWEB)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  18. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  19. Site decommissioning management plan

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff's strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites

  20. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  1. Decommissioning of IFEC

    International Nuclear Information System (INIS)

    The IFEC nuclear fuel fabrication plant operated in Italy for more then thirty years and has now been successfully decommissioned. The rules and regulations relating to Quality Assurance established during the fabrication of Cirene reactor fuel have been adhered to during the decommissioning phase. The use of personnel with large experience in the nuclear field has resulted in vast majority of cares of material and apparatus to be reutilized in conventional activities without the need of calling on the assistance of external firms. The whole decontamination process was successfully completed on time and in particular the quantity of contaminated wastes was kept to eminimun

  2. Particle-accelerator decommissioning

    International Nuclear Information System (INIS)

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given

  3. Decontamination and decommissioning

    International Nuclear Information System (INIS)

    The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. These four phases of work were conducted in accordance with applicable regulations for D and D of research facilities and applicable regulations for packaging, transportation, and burial and storage of radioactive materials. The final result is that the Advanced Fuel Laboratories now meet requirements of ANSI 13.12 and can be released for unrestricted use. The four principal documents utilized in the D and D of the Cheswick Site were: (1) Plan for Fully Decontaminating and Decommissioning, Revision 3; (2) Environmental Assessment for Decontaminating and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pa.; (3) WARD-386, Quality Assurance Program Description for Decontaminating and Decommissioning Activities; and (4) Health Physics, Fire Control, and Site Emergency Manual. These documents are provided as Attachments 1, 2, 3 and 4

  4. Particle-accelerator decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Opelka, J.H.; Mundis, R.L.; Marmer, G.J.; Peterson, J.M.; Siskind, B.; Kikta, M.J.

    1979-12-01

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given.

  5. Lessons Learned for Decommissioning Planning

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Wook; Kim, Young-gook; Kim, Hee-keun [Korea Hydro and Nuclear Power Co. LTD, Daejeon (Korea, Republic of)

    2015-10-15

    The purpose of this paper is to introduce the U.S. nuclear industrial's some key lessons learned especially for decommissioning planning based on which well informed decommissioning planning can be carried out. For a successful decommissioning, it is crucial to carry out a well-organized decommissioning planning before the decommissioning starts. This paper discussed four key factors which should be decided or considered carefully during the decommissioning planning period with introduction of related decommissioning lessons learned of U.S. nuclear industry. Those factors which have been discussed in this paper include the end state of a site, the overall decommissioning strategy, the management of the spent fuels, and the spent fuel pool island. Among them, the end state of a site should be decided first as it directs the whole decommissioning processes. Then, decisions on the overall decommissioning strategy (DECON vs. SAFSTOR) and the management of the spent fuels (wet vs. dry) should follow. Finally, the spent fuel pool island should be given due consideration because its implementation will result in much cost saving. Hopefully, the results of this paper would provide useful inputs to performing the decommissioning planing for the Kori unit 1.

  6. Mobility of heavy metals from polluted sediments of a semi-enclosed basin: in situ benthic chamber experiments in Taranto's Mar Piccolo (Ionian Sea, Southern Italy).

    Science.gov (United States)

    Emili, Andrea; Acquavita, Alessandro; Covelli, Stefano; Spada, Lucia; Di Leo, Antonella; Giandomenico, Santina; Cardellicchio, Nicola

    2016-07-01

    In situ benthic flux experiments were conducted at two stations in the Mar Piccolo of Taranto (Italy), one of the most industrialised and contaminated coastal areas of the Mediterranean. Sediments of the two stations are notably different in their trace metal content, with a station closer to a Navy harbour showing higher mean concentrations of almost all investigated metals (Al, As, Cd, Cr, Cu, Fe, Hg, Mn, Ni, Pb, V and Zn). Conversely, both stations are characterised by significant Hg contamination, compared to the local baseline. Results of a sequential extraction scheme on surface sediments suggest a relatively scarce mobility of the examined metals (Zn > Ni > Cr > As > Cu > Pb). A Hg-specific extraction procedure showed that most of the element (93.1 %) occurs in a fraction comprising Hg bound to Fe/Mn oxi-hydroxides. Reduction of these oxides may affect Hg remobilisation and redistribution. Porewater profiles of dissolved trace metals were quite similar in the two sites, although significant differences could be observed for Al, Cu, Fe and Hg. The highest diffusive fluxes were observed for As, Fe and Mn. Mobility rates of several trace elements (Al, As, Cd, Cr, Cu, Fe, Hg, Mn, Ni, Pb, V and Zn) were directly measured at the sediment-water interface. Results from benthic in situ incubation experiments showed increasing dissolved metal concentrations with time, resulting in higher fluxes for Cu, Fe, Hg, V and Zn in the most contaminated site. Conversely, fluxes of Mn, Ni and Pb were comparable between the two stations. The estimated flux of Hg (97 μg m(-2) day(-1)) was the highest observed among similar experiments conducted in other highly contaminated Mediterranean coastal environments. Benthic fluxes could be partially explained by considering rates of organic matter remineralisation, dissolution of Fe/Mn oxy-hydroxides and metal speciation in sediments. Seasonal and spatial variation of biogeochemical parameters can influence metal remobilisation in

  7. Real time nanogravimetric monitoring of corrosion for nuclear decommissioning

    OpenAIRE

    Tzagkaroulakis, I.; Boxall, C.

    2015-01-01

    Monitoring and understanding of corrosion on nuclear sites plays a key role in safe asset management (predicting plant life, assessing efficacy of corrosion inhibitors for plant lifetime extension) and supporting informed choice of decontamination methods for steels due for decommissioning. Recent advances in Quartz Crystal Nanobalance (QCN) technology offer a means to monitor corrosion in-situ in radiologically harsh environments, in real time and with high sensitivity. Oxalic acid has been ...

  8. On-site disposal as a decommissioning strategy

    International Nuclear Information System (INIS)

    On-site disposal is not a novel decommissioning strategy in the history of the nuclear industry. Several projects based on this strategy have been implemented. Moreover, a number of studies and proposals have explored variations within the strategy, ranging from in situ disposal of entire facilities or portions thereof to disposal within the site boundary of major components such as the reactor pressure vessel or steam generators. Regardless of these initiatives, and despite a significant potential for dose, radioactive waste and cost reduction, on-site disposal has often been disregarded as a viable decommissioning strategy, generally as the result of environmental and other public concerns. Little attention has been given to on-site disposal in previous IAEA publications in the field of decommissioning. The objective of this report is to establish an awareness of technical factors that may or may not favour the adoption of on-site disposal as a decommissioning strategy. In addition, this report presents an overview of relevant national experiences, studies and proposals. The expected end result is to show that, subject to safety and environmental protection assessment, on-site disposal can be a viable decommissioning option and should be taken into consideration in decision making

  9. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  10. Initial results of detected methane emissions from landfills in the Los Angeles Basin during the COMEX campaign by the Methane Airborne MAPper (MAMAP) instrument and a greenhouse gas in-situ analyser

    Science.gov (United States)

    Krautwurst, Sven; Gerilowski, Konstantin; Kolyer, Richard; Jonsson, Haflidi; Krings, Thomas; Horstjann, Markus; Leifer, Ira; Vigil, Sam; Buchwitz, Michael; Schüttemeyer, Dirk; Fladeland, Matthew M.; Burrows, John P.; Bovensmann, Heinrich

    2015-04-01

    the German Research Center for Geoscience (GFZ) in Potsdam. The in-situ measurements were obtained by a greenhouse gas (GHG) in-situ analyser operated by NASA's Ames Research Center (ARC). Both instruments were installed aboard a DHC-6 Twin Otter aircraft operated by the Center for Interdisciplinary Remotely-Piloted Aircraft Studies (CIRPAS). Initial results - including estimated fugitive emission rates - will be presented for the landfill Olinda Alpha in Brea, Orange County, Los Angeles Basin, California, which was overflown on four different days during the COMEX field campaign in late summer 2014.

  11. Decommissioning of facilities for mining and milling or radioactive ores and closeout of residues

    International Nuclear Information System (INIS)

    The purpose of this report is to provide information to Member States in order to assist in planning and implementing the decommissioning/closeout of uranium mine/mill facilities, mines, tailings impoundments, mining debris piles, leach residues and unprocessed ore stockpiles. The report presents an overview of the factors involved in planning and implementing the decommissioning/closeout of uranium mine/mill facilities. The information applies to mines, mills, tailings piles, mining debris piles and leach residues that are present as operational, mothballed or abandoned projects, as well as to future mining and milling projects. The report identifies the major factors that need to be considered in the decommissioning/closeout activities, including regulatory considerations; decommissioning of the mine/mill buildings, structures and facilities; decommissioning/closeout of open pit and underground mines; decommissioning/closeout of tailings impoundments; decommissioning/closeout of mining debris piles, unprocessed ore and other contaminated material such as heap leach piles, in situe leach facilities and contaminated soils; restoration of the site, vicinity properties and groundwater; radiation protection and health and safety considerations; and an assessment of costs and post-decommissioning or post-closeout maintenance and monitoring needs. 55 refs, figs and tabs

  12. Decommissioning and decontamination studies

    International Nuclear Information System (INIS)

    The decommissioning of retired Hanford facilities requires careful consideration of environmentally-related factors. Applicable ecology programs have been designed to: develop the technology associated with burial ground stabilization, thereby minimizing biotic access and transport of radioactive wastes and, characterize present 300 Area burial grounds to ascertain the potential biotic transport of waste materials away from managed facilities. Results are reported from studies on the role of plants, small mammals, and ants as potential transport vectors of radionuclides from radioactive waste burial grounds

  13. Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    Tokai-1 (GCR, Gas Cooled Reactor) nuclear power plant of JAPC (the Japan Atomic Power Company) started commercial operation in 1966 as the first commercial nuclear power plant in Japan. The unit had helped introduction and establishment of the construction and operation technologies regarding nuclear power plant at early stage in Japan by its construction and operating experiences. However, The Japan Atomic Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operation permanently because of a fulfillment of its mission and economical reason. The unit was finally shut down in March 1998 after about 32 year operation. It took about three years for removal of all spent fuels from the site, and then decommissioning started in 2001. JAPC, always on the forefront of the nation's nuclear power generation, is now grappling Japan's first decommissioning of a commercial nuclear power plant, striving to establish effective, advanced decommissioning. The decommissioning for Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static condition ('safe storage period'). While the reactor had been safely stored, the phased decommissioning works started from non-radioactive or low radioactive equipment toward high radioactive equipment. First five years of the project, JAPC concentrated to drain and clean spent fuel cartridge cooling pond and to remove conventional equipments such as turbine, feed water pump and fuel charge machine as planed and budgeted. From 2006, the project came into a new phase. JAPC has been trying to remove four Steam Raising Units (SRUs). The SRUs are huge component (750ton, φ6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are radioactively contaminated. Major concerns are workers safety and minimizing contamination areas during SRU removal. Therefore, JAPC is developing and introducing Jack-down method and remote control multi-functional dismantling system. This

  14. Po-Basin Atmospheric Composition during the Pegasos Field Campaign (summer 2012): Evaluation of ninfa/aodeM Simulation with In-Situ e Remote Sensing Observations

    Science.gov (United States)

    Landi, Tony C.; Bonafe, Giovanni; Stortini, Michele; Minguzzi, Enrico; Cristofanelli, Paolo; Marinoni, Angela; Giulianelli, Lara; Sandrini, Silvia; Gilardoni, Stefania; Rinaldi, Matteo; Ricciardelli, Isabella

    2014-05-01

    Within the EU project PEGASOS one of three field campaigns took place in the Po Valley during the summer of 2012. Photochemistry, particle formation, and particle properties related to diurnal evolution of the PBL were investigated through both in-situ and airborne measurements on board a Zeppelin NT air ship. In addition, 3-D air quality modeling systems were implemented over the Po valley for the summer 2012 to better characterize the atmospheric conditions, in terms of meteorological parameters and chemical composition. In this work, we present a comparison between atmospheric composition simulations carried out by the modeling system NINFA/AODEM with measurements performed during the PEGASOS field campaign for the period 13 June - 12 July 2012. NINFA (Stortini et al., 2007) is based on the chemical transport model CHIMERE (Bessagnet et al., 2008), driven by COSMO-I7, the meteorological Italian Limited Area Model, (Steppeler et al., 2003). Boundary conditions are provided by Prev'air data (www.prevair.org), and emission data input are based on regional, national and European inventory. Besides, a post-processing tool for aerosol optical properties calculation, called AODEM (Landi T. C. 2013) was implemented. Thus, predictions of Aerosol Optical Depth and aerosol extinction coefficient were also used for model comparison to vertical-resolved observations. For this experiment, NINFA/AODEM has been also evaluated by using measurements of size-segregated aerosol samples, number particles concentration and aerosol optical properties collected on hourly basis at the 3 different sampling sites representative of urban background (Bologna), rural background (San Pietro Capofiume) and remote high altitude station (Monte Cimone 2165 ma.s.l.). ). In addition, we focused on new particles formations events and long range transports from Northern Africa observed during the field campaign. References Bessagnet, Bertrand, Laurent Menut, Gabriele Curci, Alma Hodzic, Bruno

  15. Detritiation studies for JET decommissioning

    International Nuclear Information System (INIS)

    JET is the world largest tokamak and has the capacity of operating with a tritium plasma. Three experimental campaigns, the Preliminary Tritium Experiment (0.1g T2) in 1991, the Trace Tritium Experiment (5g T2) in 2005, and the large experiment, the Deuterium-Tritium Experiment (DTE1) (100g T2) in 1997, were carried out at JET with tritium plasmas. In DTE1 about 35 grams of tritium were fed directly into the vacuum vessel, with about 30% of this tritium being retained inside the vessel. In several years time JET will cease experimental operations and enter a decommissioning phase. In preparation for this the United Kingdom Atomic Energy Authority, the JET Operator, has been carrying out studies of various detritiation techniques. The materials which have been the subject of these studies include solid materials, such as various metals (Inconel 600 and 625, stainless steel 316L, beryllium, ''oxygen-free'' copper, aluminium bronze), carbon fibre composite tiles, ''carbon'' flakes and dust present in the vacuum vessel and also soft housekeeping materials. Liquid materials include organic liquids, such as vacuum oils and scintillation cocktails, and water. Detritiation of gas streams was also investigated. The purpose of the studies was to select and experimentally prove primary and auxiliary technologies for in-situ detritiation of in-vessel components and ex-situ detritiation of components removed from the vessel. The targets of ex-vessel detritiation were a reduction of the tritium inventory in and the rate of tritium out-gassing from the materials, and conversion, if possible, of intermediate level waste to low level waste and a reduction in volume of waste for disposal. The results of experimental trials and their potential application are presented. (orig.)

  16. Decommissioning of Radiotherapy Facilities

    International Nuclear Information System (INIS)

    Radiotherapy units containing high activity sealed radioactive sources of 60Co or 137Cs are mainly use for medical, research or calibration applications. After several half-lives of decay, the radionuclide source has to be changed or the unit is decommissioned if no longer required. Before starting a decommissioning project it is very important to look for documents relating to any sources held or installed in equipment. In general this should be no problem because the recommended working life of such sealed radioactive sources is limited to 10 or a maximum of 15 years. These time periods are short in comparison with other facilities like research laboratories or small reactors. These documents (source certificates) will be very helpful to plan the decommissioning because they say everything about the original activity of the source at a reference date, the type of the source and the manufacturer. The next step may be to contact the machine supplier or the source manufacturer, but be aware that neither may still be in existence or may have changed their type of business. In such cases, it is recommended to contact national or international sealed source manufacturers or suppliers for help. Sometimes it is also helpful to contact colleagues in other hospitals or research centres to ask for information about specialists in this topic. In general it is not useful, and even very dangerous, to try to decommission such a unit without expert help It is essential to have specialist tools and shielded containers to recover the source out of the unit. It is strongly recommended to invite the source removal specialist for a site visit to review the situation before starting any decommissioning process. A further problem can occur, if the source must be transported to a national storage centre or even an international storage facility, as the source must be packaged to meet international transport requirements. The end state of such a project should be an empty room where the

  17. In situ Remediation Technologies

    NARCIS (Netherlands)

    Grotenhuis, J.T.C.; Rijnaarts, H.H.M.

    2011-01-01

    A summary of two decades of developments of In Situ remediation is presented in this chapter. The basic principles of In Situ technology application are addressed, such as equilibrium relations between contaminant phases, factors controlling biological and geochemical processes, contaminant characte

  18. Workshop on decommissioning; Seminarium om avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Broden, K. (ed.)

    2005-12-15

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  19. Decommissioning Funding: Ethics, Implementation, Uncertainties

    International Nuclear Information System (INIS)

    This status report on decommissioning funding: ethics, implementation, uncertainties is based on a review of recent literature and materials presented at NEA meetings in 2003 and 2004, and particularly at a topical session organised in November 2004 on funding issues associated with the decommissioning of nuclear power facilities. The report also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). This report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems

  20. Funding Decommissioning - UK Experience

    International Nuclear Information System (INIS)

    'Funding' started with CEGB and SSEB (state-owned electric utilities) in 1976 using the internal un-segregated fund route (i.e unfunded). This continued until privatisation of electricity industry (excluding nuclear) in 1990. Assets bought with the internal un-segregated fund were mostly transferred into non-nuclear private utilities. New state-owned Nuclear Electric (England and Wales) was given a 'Fossil Fuel Levy', a consumer charge of 10% on retail bills, amounting to c. BP 1 bn. annually. This allowed Nuclear Electric to trade legally (A reserve of BP 2.5 bn. was available from Government if company ran out of money). By 1996 the newer nuclear stations (AGRS plus PWR) were privatised as British Energy. British Energy started an external segregated fund, the Nuclear Decommissioning Fund, with a starting endowment of c. BP 225 m. - and BE made annual contributions of British Pound 16 m. into the Fund. Assumptions were that BE had 70 to accumulate cash and could get a 3.5% average annual real return. Older stations (Magnox) were left in private sector and went to BNFL in 1997. Magnox inherited the surplus cash in BE - mostly unspent Fossil Fuel Levy receipts - of c. BP 2.6 bn. Government gave an 'Undertaking' to pay BP 3.8 bn. (escalating at 4.5% real annually) for Magnox liabilities, should Magnox Electric run out of cash. BNFL inherited the BP 2.6 bn. and by 2000 had a 'Nuclear Liabilities Investment Portfolio' of c. BP 4 bn. This was a quasi-segregated internal fund for liabilities in general. [Note: overall UK nuclear liabilities in civilian sector were running at c. BP 48 bn. by now]. BE started profitable and paid BP 100 m. annually in dividends to private investors for several years. BE ran into severe financial problems after 2001 and Government organised restructuring aid, now approved by European Commission. Terms include: - BE now to contribute BP 20 m. a year into an expanded Nuclear Liabilities Fund; - A bond issue of BP 275 m. to go to Fund; - 65

  1. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  2. Planning for decommissioning of Hifar

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO) has operated the 10MW HIFAR research reactor since 1958. In addition to its role in research, the reactor provides radioisotopes for medical and industrial use and is a major supplier of NTD silicon for the semi-conductor industry. It is anticipated that HIFAR will finally shut down operations in December 2006. Although ANSTO has successfully decommissioned MOATA and undertaken other smaller decommissioning projects the proposed HIFAR decommissioning project will be the largest ever undertaken by ANSTO. ANSTO faces a number of challenges in HIFAR's final year of operation. These include: the establishment of a modern decommissioning strategy in the absence of a long-term nuclear waste repository management facility or waste acceptance criteria for the material generated by the decommissioning; the impact of the impeding closure of the facility on staff morale and retention of key staff; and to meet the our customer's needs up to the final closure. These challenges are compounded by competition for skilled resources required to commission the new research reactor (OPAL) and the need to continue to supply radioisotopes. Important 'lessons in progress' that will be discussed in this paper include staffing the decommissioning team, maintenance of a strong safety culture during final stages of operation, working towards regulatory approval for decommissioning and strategies for knowledge retention. (author)

  3. In-Situ Simulation

    DEFF Research Database (Denmark)

    Bjerregaard, Anders Thais; Slot, Susanne; Paltved, Charlotte;

    2015-01-01

    acceptance from department heads, immature organization, and the formation of ad hoc teams for the in situ simulations. Conclusion: In situ simulation provides a way to study team interactions associated with effective interprofessional teamwork and gives rise to team-specific training such as handover......Introduction: In situ simulation offers on-site training to healthcare professionals. It refers to a training strategy where simulation technology is integrated into the clinical encounter. Training in the simulation laboratory does not easily tap into situational resources, e.g. individual, team......, and organisational characteristic. Therefore, it might fail to fully mimic real clinical team processes. Though research on in situ simulation in healthcare is in its infancy, literature is abundant on patient safety and team training1. Patient safety reporting systems that identify risks to patients can improve...

  4. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  5. Decontamination & decommissioning focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  6. Decommissioning Cost Assessment

    International Nuclear Information System (INIS)

    The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in delayed, redirected or halted activities, which has the common denominator of costs increases. In modern democratic countries, information sharing, knowledge transfer and open communication about costs for the management of radioactive waste are prerequisites for the task to develop modern methods for public participation and thus to develop well-founded and justified confidence for further development of nuclear energy. Nuclear and radiation safety Authorities have a clear role to provide unbiased information on any health, safety, financial and environmental related issues. This task requires a good understanding of the values and opinion of the public, and especially those of the younger generation

  7. Power Plant decommissioning

    Directory of Open Access Journals (Sweden)

    Mažeika Jonas

    2014-11-01

    Full Text Available On a first attempt, the determination of 14C and 36Cl activity concentrations in basic operational waste (spent ion-exchange resins and perlite mixture, in decommissioning waste (construction concrete, sand, stainless steel and serpentinite and irradiated graphite from the Ignalina NPP has been performed. The samples for measurement of the specific activity of 14C and 36Cl were obtained from the selected places, where the highest values of the dose rate and the activity concentrations of gamma emitters were found. The performed study of the total 14C and 36Cl activity concentrations was based on estimated chemical forms of 14C (inorganic and organic compounds and 36Cl as Cl- ion. The tested methods used in this study were found to be suitable for estimation of activity concentrations of measured radionuclides.

  8. DECOM experience with decommissioning costing

    International Nuclear Information System (INIS)

    The OMEGA code has been used in numerous Slovak and international decommissioning planning and costing projects and in IAEA R and D projects and is continuously updated and upgraded. The next goal for the DECOM costing activities is to develop an universal and user-friendly ISDC costing tool accessible via internet - eOMEGA taking over the advantages of the long-term experience of DECOM and being in line with up-to date trends in decommissioning costing. DECOM members participate in international expert groups for further improvement of costing methodologies, such as the uncertainties, cost practices and cost peer reviews in decommissioning costing. DECOM members participate also in IAEA projects, expert missions and training courses related to decommissioning costing and planning. (authors)

  9. Decommissioning of the Loviisa NPP

    International Nuclear Information System (INIS)

    Imatran Voima Oy has revised the decommissioning plan for the Loviisa Nuclear Power Plant (Loviisa 1 and Loviisa 2) by the end of the year 1998. The thermal power of the power plant has been increased to 2x1500 MWth, and the life time has been designed to be extended to 45 years in the decommissioning plan. The decommissioning of the power plant is designed to begin in 2022 and it will be finished in 2048. The plan is based on immediate dismantlement (i.e. DECON) after the shut down of the power plant. Experienced plant personnel will still be available to lead the decommissioning work. Only the radioactive plant systems, components and structures will be dismantled and disposed of. Decommissioning wastes will be disposed into the underground disposal tunnels situating at the site in the depth of about 110 m. These tunnels are already partly ready for power plant wastes. The big and heavy reactor components, e.g. pressure vessels and steam generators, will be disposed of as such, without cutting them into smaller parts. This saves time and radiation doses. The total volume of decommissioning wastes is 14 800 m3, when packed in boxes. The manpower needed for decommissioning is about 2 800 manyears. The collective radiation dose for personnel is estimated to be about 9.2 manSv. The cost estimate of the decommissioning is about 1 117 million FIM. The spent fuel will be stored at the plant for 20 years after the shut down of the power plant. After that it will be transported from the site to the encapsulation plant for final disposal. (orig.)

  10. In situ groundwater bioremediation

    Energy Technology Data Exchange (ETDEWEB)

    Hazen, Terry C.

    2009-02-01

    In situ groundwater bioremediation of hydrocarbons has been used for more than 40 years. Most strategies involve biostimulation; however, recently bioaugmentation have been used for dehalorespiration. Aquifer and contaminant profiles are critical to determining the feasibility and strategy for in situ groundwater bioremediation. Hydraulic conductivity and redox conditions, including concentrations of terminal electron acceptors are critical to determine the feasibility and strategy for potential bioremediation applications. Conceptual models followed by characterization and subsequent numerical models are critical for efficient and cost effective bioremediation. Critical research needs in this area include better modeling and integration of remediation strategies with natural attenuation.

  11. Systematization of nuclear fuel facility decommissioning technology

    Energy Technology Data Exchange (ETDEWEB)

    Sugitsue, Noritake [Japan Nuclear Cycle Development Inst., Ningyo Toge Environmental Engineering Center, Kamisaibara, Okayama (Japan)

    2001-09-01

    In the Ningyo-Toge Environmental Engineering Center, the nature of all decommissioning works is clarified and, as an information base for planning the promotion of efficiency of a work, the Decommissioning Engineering System is being developed. The Decommissioning Engineering System consists of a function for performing work support for a decommissioning, a function for gathering information results of the decommissioning technology and a general evaluation function for the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. (author)

  12. Decommissioning planning and the assessment of alternatives for the Hanford production reactors

    International Nuclear Information System (INIS)

    Several years ago, the US Department of Energy began assessing alternatives and planning the decommissioning of eight shut-down plutonium production reactors located on the DOE Hanford Site in Washington State. The first of these graphite-moderated, water-cooled, reactors was built and started up in 1944 as part of the World War II Manhattan Project. The last of them started up in 1955. The eight reactors each operated for 12 to 24 years, with all eight operating simultaneously for about 10 years. In the 1960's, production needs declined and the reactors were one-by-one permanently shut down, the last of them in 1971. (A ninth Hanford production reactor, N Reactor, was started up in 1963; it is still operating and is not within the scope of the decommissioning planning and alternatives assessment work reported in this paper). This paper provides an overview description of the decommissioning plan for the eight shut-down Hanford production reactors and their associated fuel storage basins. Included are descriptions of the decommissioning alternatives considered for the facilities, along with discussions of National Environmental Policy Act (NEPA) process activities applicable to the Hanford decommissioning work. The criteria used in assessing decommissioning alternatives and the assumptions used in the decommissioning planning are identified. 4 refs., 8 figs., 3 tabs

  13. Current international issues in decommissioning

    International Nuclear Information System (INIS)

    In 1999, the Italian Environmental Protection authorities (ANPA at that time) hosted in Rome a Nuclear Energy Agency (NEA) meeting on the Regulatory Aspects of Decommissioning. This 'stock-taking' conference heard views from regulatory authorities, the decommissioning industry, waste management organisations and other relevant industrial sectors (e.g. the scrap metal industry) regarding the issues and aspects of decommissioning that should be further addressed, particularly at an international level. From this conference, six issues of relevance were identified which, since that time, have been addressed within the framework of the NEA. These issues are: - Decommissioning policies and strategies; - Waste management and materials reuse considerations; - Authorised release of sites and facilities; - Securing long-term funding and responsibility; - Framework for safety regulation of decommissioning; - Research and development in decommissioning. The NEA has focused on the international aspects of these issues, and on the roles of national governments in addressing the national and international aspects of these issues. This paper will present an overview of the NEA's findings in these areas. Realizing that these issues are important to the work of other international organisations, the NEA has tried to assess and use as appropriate the work of others in discussing these issues. As such, a brief review of relevant work at other international organisations will be presented. Based on its work, and in order to further advance these issues, the NEA is planning a second workshop on the Regulatory Aspects of Decommissioning, which will again be hosted by the Italian authorities in Rome, and will be held during the second half of 2004. (author)

  14. Uranium in situ leaching

    International Nuclear Information System (INIS)

    Despite the depressed situation that has affected the uranium industry during the past years, the second Technical Committee Meeting on Uranium In Situ Leaching, organized by the International Atomic Energy Agency and held in Vienna from 5 to 8 October 1992, has attracted a relatively large number of participants. A notable development since the first meeting was that the majority of the contributions came from the actual operators of in situ leaching uranium production. At the present meeting, presentations on operations in the USA were balanced by those of the eastern European and Asian countries. Contributions from Bulgaria, China, Czechoslovakia, Germany (from the operation in the former German Democratic Republic), the Russian Federation and Uzbekistan represent new information not commonly available. In situ leach mining is defined in one of the paper presented as a ''mining method where the ore mineral is preferentially leached from the host rock in place, or in situ, by the use of leach solutions, and the mineral value is recovered. Refs, figs and tabs

  15. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  16. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  17. Decommissioning: a problem or a challenge?

    OpenAIRE

    Mele Irena

    2004-01-01

    With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste manageme...

  18. Development of decommissioning system engineering technology

    International Nuclear Information System (INIS)

    In the decommissioning planning stage, it is important to select the optimized decommissioning process considering the cost and safety. Especially the selection of the optimized decommissioning process is necessary because it affects to improve worker's safety and decommissioning work efficiency. The decommissioning process evaluation technology can provide the optimized decommissioning process as constructing various decommissioning scenarios and it can help to prevent the potential accidents as delivering the exact work procedures to workers and to help workers to perform decommissioning work skillfully. It's necessary to measure the radioactive contamination in the highly contaminated facilities such as hot-cells or glove-boxes to be decommissioned for decommissioning planning. These facilities are very high radiation level, so it is difficult to approach. In this case the detector system is preferable to separate the sensor and electronics, which have to locate in the facility outside to avoid the electric noise and worker's radiation exposure. In this project, we developed the remote detection system for radiation measurement and signal transmission in the high radiation area. In order to minimize worker's exposure when decommissioning highly activated nuclear facilities, it is necessary to develop the remote handling tool to perform the dismantling work remotely. Especially, since cutting, measuring, and decontamination works should be performed remotely in the highly activated area, the remote handling tool for conducting these works should be developed. Therefore, the multi-purpose dismantling machine that can measuring dose, facility cutting, and remote handling for maintenance and decommissioning of highly activated facility should be needed

  19. 77 FR 41107 - Decommissioning Planning During Operations

    Science.gov (United States)

    2012-07-12

    ... Decommissioning Planning Rule (DPR) (June 17, 2011, 76 FR 33512). The DPR applies to the operational phase of a..., ``Decommissioning Planning During Operations'' (December 13, 2011, 76 FR 77431). The NRC received more than 100...; ] NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 30, 40, 50, 70, and 72 Decommissioning Planning...

  20. In situ monitoring

    International Nuclear Information System (INIS)

    Systems for in situ analysis of radionuclides around storage areas and nuclear sites are being developed. The development and initial use of an intrinsic Ge system for the determination of Pu and Am in soils were completed. A method based on gamma-ray analysis of grazing animal thyroids was developed as a possible method for U and Th exploration using their 226Ra and 228Ra daughters

  1. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Ha, Jea-Hyun; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost.

  2. In Situ Mass Spectrometer Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The In Situ Mass Spectrometer projects focuses on a specific subsystem to leverage advanced research for laser-based in situ mass spectrometer development...

  3. Remote methods for decontamination and decommissioning operations

    International Nuclear Information System (INIS)

    Three methods for the decontamination and decommissioning of nuclear facilities are described along with operational experience associated with each method. Each method described in some way reduces radiation exposure to the operating personnel involved. Electrochemical decontamination of process tanks is described using an in-situ method. Descriptions of two processes, electropolishing and cerium redox decontamination, are listed. A method of essentially smokeless cutting of process piping using a plasma-arc cutting torch is described. In one technique, piping is cut remotely from a distance using a specially modified torch holder. In another technique, cutting is done with master-slave manipulators inside a hot cell. Finally, a method for remote cutting and scarification of contaminated concrete is described. This system, which utilizes high-pressure water jets, is coupled to a cutting head or rotating scarification head. The system is suited for cutting contaminated concrete for removal or removing a thin layer in a controlled manner for decontamination. 4 refs., 6 figs

  4. Methods of power reactor decommissioning cost recovery

    International Nuclear Information System (INIS)

    This paper analyzes rate-regulatory tax, accounting and cost recovery factors, and these analyses lead to the following overall conclusions in connection with decommissioning cost recovery. 1) The internal use of accumulated decommissioning funds is strongly recommended because it results in the lowest net ratepayer cost of decommissioning, and 2) The most equitable decommissioning cost recovery method is based on current costs and on the prompt and continuous maintenance of the purchasing power of accumulated funds. Finally, it is noted that the cost recovery approach recommended for decommissioning would have similar advantage if applied to spent fuel cost recovery as well

  5. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  6. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  7. A Decommissioning Information Management System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Hong, S. B.; Chung, U. S.; Park, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    In 1996, it was determined that research reactors, the KRR-1 and the KRR-2, would be shut down and dismantled. A project for the decommissioning of these reactors was launched in January 1997 with the goal of a completion by 2008. The total budget of the project was 19.4 million US dollars, including the cost for the waste disposal and for the technology development. The work scopes during the decommissioning project were the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After the removal of the entire radioactivity, the site and buildings will be released for an unconditional use. A separate project for the decommissioning of the uranium conversion plant was initiated in 2001. The plant was constructed for the development of the fuel manufacturing technologies and the localization of nuclear fuels in Korea. It was shut downed in 1993 and finally it was concluded in 2000 that the plant would be decommissioned. The project will be completed by 2008 and the total budget was 9.2 million US dollars. During this project, all vessels and equipment will be dismantled and the building surface will be decontaminated to be utilized as general laboratories.

  8. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  9. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  10. Options for Steam Generator Decommissioning

    International Nuclear Information System (INIS)

    Selecting the best option for decommissioning steam generators is a key consideration in preparing for decommissioning PWR nuclear power plants. Steam Generators represent a discrete waste stream of large, complex items that can lend themselves to a variety of options for handling, treatment, recycling and disposal. Studsvik has significant experience in processing full size Steam Generators at its metal recycling facility in Sweden, and this paper will introduce the Studsvik steam generator treatment concept and the results achieved to date across a number of projects. The paper will outline the important parameters needed at an early stage to assess options and to help consider the balance between off-site and on-site treatment solutions, and the role of prior decontamination techniques. The paper also outlines the use of feasibility studies and demonstration projects that have been used to help customers prepare for decommissioning. The paper discusses physical, radiological and operational history data, Pro and Contra factors for on- and off-site treatment, the role of chemical decontamination prior to treatment, planning for off-site shipments as well as Studsvik experience This paper has an original focus upon the coming challenges of steam generator decommissioning and potential external treatment capacity constraints in the medium term. It also focuses on the potential during operations or initial shut-down to develop robust plans for steam generator management. (authors)

  11. Reactor decommissioning experience and perspectives

    International Nuclear Information System (INIS)

    This paper first describes the existing market context and available techniques, then reviews the contribution of past and present operations and research before discussing the future orientations necessary to develop the means (cutting tools, decontamination processes, telemanipulation and waste conditioning) required to improve the cost effectiveness of decommissioning nuclear power plants. (author)

  12. 76 FR 35511 - Decommissioning Planning

    Science.gov (United States)

    2011-06-17

    ... the January 27, 1988 (53 FR 24018), rule on planning for decommissioning require licensees to provide... regulations in 1997 as Subpart E of 10 CFR part 20 (62 FR 39058; July 21, 1997). This set of requirements is... contamination and the amount of funds set aside and expended on cleanup. (62 FR 39082; July 21, 1997)....

  13. Decommissioning: a problem or a challenge?

    Directory of Open Access Journals (Sweden)

    Mele Irena

    2004-01-01

    Full Text Available With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste management programme for each nuclear facility in time, and financial provisions for implementing such programme should be provided. In this paper a presentation of current decommissioning experience in Slovenia is given. The main problems and difficulties in decommissioning of the Žirovski Vrh Uranium Mine are exposed and the lesson learned from this case is presented. The preparation of the decommissioning programme for the Nuclear Power Plant Krško is also described, and the situation at the TRIGA research reactor is briefly discussed.

  14. Assessment of foreign decommissioning technology with potential application to US decommissioning needs

    International Nuclear Information System (INIS)

    This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs

  15. Status of the NRC Decommissioning Program

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

    2003-02-24

    On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

  16. Basic Research on Selecting ISDC Activity for Decommissioning Costing in KRR-2 Decommissioning Project Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    KAERI is performing research for calculation of expected time of a decommissioning work and evaluation of decommissioning cost and this research calculate a decommissioning work unit productivity based on the experience data of decommissioning activity for KRR-2. The KAERI be used to calculate the decommissioning cost and manage the experience data from the decommissioning activity through the Decommissioning Information Management System (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), and Decommissioning Work-unit Productivity Calculation System (DEWOCS). In this paper, the methodology was presented how select the ISDC activities in dismantling work procedures of a 'removal of radioactive concrete'. The reason to select the 'removal of radioactive concrete' is main key activity and generates the amount of radioactive waste. This data will take advantage of the cost estimation after the code for the selected items derived ISDC. There are various efforts for decommissioning costing in each country. In particular, OECD/NEA recommends decommissioning cost estimation using the ISDC and IAEA provides for Cost Estimation for Research Reactors in Excel (CERREX) program that anyone is easy to use the cost evaluation from a limited decommissioning experience in domestic. In the future, for the decommissioning cost evaluation, the ISDC will be used more widely in a strong position. This paper has described a method for selecting the ISDC item from the actual dismantling work procedures.

  17. In situ zymography.

    Science.gov (United States)

    George, Sarah J; Johnson, Jason L

    2010-01-01

    In situ zymography is a unique laboratory technique that enables the localisation of matrix-degrading metalloproteinase (MMP) activity in histological sections. Frozen sections are placed on glass slides coated with fluorescently labelled matrix proteins. After incubation MMP activity can be observed as black holes in the fluorescent background due to proteolysis of the matrix protein. Alternatively frozen sections can be incubated with matrix proteins conjugated to quenched fluorescein. Proteolysis of the substrate by MMPs leads to the release of fluorescence. This technique can be combined with immunohistochemistry to enable co-location of proteins such as cell type markers or other proteins of interest. Additionally, this technique can be adapted for use with cell cultures, permitting precise location of MMP activity within cells, time-lapse analysis of MMP activity and analysis of MMP activity in migrating cells. PMID:20135289

  18. Decontamination of dismantled parts from phosphate rock fertilizer plant decommissioning

    International Nuclear Information System (INIS)

    Decommissioning of the Uranium Recovery Section at the Phosphate Rock Fertilizer Plant in Gresik, East Java, Indonesia requires decontamination activity be applied to dismantled parts. The decontamination study has categorized the dismantled parts into three types, type A, type B and type C parts. Type A parts were the equipment having very low surface activity or below the clearance level. Type B parts were the equipment having surface activity beyond the clearance level, containing radioactive scale, which is easily removed by in situ decontamination to become parts that are useable unrestrictedly. Type C parts were the equipment having surface activity beyond the clearance level whose nature is very difficult to remove. In situ decontamination of the type B parts have been studied. Mechanical surface cleaning methods and strippable coating methods can be applied for in situ decontamination. The application of strippable coating methods with a composition of 10.0% phosphoric acid, 1.0% HEDPA, 3.0% tartaric acid, 12.0% polyvinyl alcohol and 4.3% absorbent clynoptilolyte was considered to be very effective. (author)

  19. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

    A title that critically reviews the decommissioning and decontamination processes and technologies available for rehabilitating sites used for nuclear power generation and civilian nuclear facilities, from fundamental issues and best practices, to procedures and technology, and onto decommissioning and decontamination case studies.$bOnce a nuclear installation has reached the end of its safe and economical operational lifetime, the need for its decommissioning arises. Different strategies can be employed for nuclear decommissioning, based on the evaluation of particular hazards and their attendant risks, as well as on the analysis of costs of clean-up and waste management. This allows for decommissioning either soon after permanent shutdown, or perhaps a long time later, the latter course allowing for radioactivity levels to drop in any activated or contaminated components. It is crucial for clear processes and best practices to be applied in decommissioning such installations and sites, particular where any ...

  20. Decommissioning: a United Kingdom perspective

    Energy Technology Data Exchange (ETDEWEB)

    Haworth, A.; Reed, D.L.; Bleeze, A. [Health and Safety Executive, London (United Kingdom)

    1995-12-31

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate`s policy on decommissioning which has arisen as a result of a review made in response to these changes. (author).

  1. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    During the next decade the two major nuclear powers will each have to decommission more than 100 naval nuclear vessels, in particular submarines. The problems connected with this task is considered in this report. Firstly the size of the task is considered, i.e. the number of nuclear vessels that has to be decommissioned. Secondly the reactors of these vessels, their fuel elements, their power level, the number of reactors per vessel and the amount of radioactivity to be handled are discussed. Thirdly the decommissioning procedures, i.e. The removal of fuel from the vessels, the temporary storage of the reactor fuel near the base, and the cleaning and disposal of the reactor and the primary circuit components are reviewed. Finally alternative uses of the newer submarines are briefly considered. It should be emphasizes that much of the detailed information on which this report is based, may be of dubious nature, and that may to some extent affect the validity of the conclusions of the report. (au)

  2. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  3. European Decommissioning Academy (EDA). Ready to start

    Energy Technology Data Exchange (ETDEWEB)

    Slugen, Vladimir [Slovak University of Technology, Bratislava (Slovakia). Inst. of Nuclear and Physical Engineering

    2015-02-15

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  4. European Decommissioning Academy (EDA). Ready to start

    International Nuclear Information System (INIS)

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  5. Experiences in teaching decommissioning - 16179

    International Nuclear Information System (INIS)

    The paper describes the experience gained by the author in teaching decommissioning in the Highlands of Scotland. Initially when asked to teach the subject of decommissioning to students sitting for a BSc degree in 'Electrical or Mechanical Engineering with Decommissioning Studies', the author was taken aback, not having previously taught degree students and there was no precedent since there was no previous material or examples to build on. It was just as difficult for the students since whilst some had progressed from completing HND studies, the majority were employed at the Dounreay site and were mature students with families who were availing themselves of the opportunity for career advancement (CPD). Some of the students were from the UKAEA and its contractors whilst others were from Rolls-Royce working at Vulcan, the Royal Navy's establishment for testing nuclear reactors for submarines. A number of the students had not been in a formal learning environment for many years. The College which had originally been funded by the UKAEA and the nuclear industry in the 1950's was anxious to break into the new field of Decommissioning and were keen to promote these courses in order to support the work progressing on site. Many families in Thurso, and in Caithness, have a long tradition of working in the nuclear industry and it was thought at the time that expertise in nuclear decommissioning could be developed and indeed exported elsewhere. In addition the courses being promoted by the College would attract students from other parts so that a centre of excellence could be established. In parallel with formal teaching, online courses were also developed to extend the reach of the College. The material was developed as a mixture of power point presentations and formal notes and was obtained from existing literature, web searches and interactive discussions with people in the industry as well as case studies obtained from actual situations. Assignments were set and

  6. In Situ Nuclear Characterization Infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    James A. Smith; J. Rory Kennedy

    2011-11-01

    To be able to evolve microstructure with a prescribed in situ process, an effective measurement infrastructure must exist. This interdisciplinary infrastructure needs to be developed in parallel with in situ sensor technology. This paper discusses the essential elements in an effective infrastructure.

  7. Research in decommissioning techniques for nuclear fuel cycle facilities in JNC. 7. JWTF decommissioning techniques

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-02-01

    Decommissioning techniques such as radiation measuring and monitoring, decontamination, dismantling and remote handling in the world were surveyed to upgrading technical know-how database for decommissioning of Joyo Waste Treatment Facility (JWTF). As the result, five literatures for measuring and monitoring techniques, 14 for decontamination and 22 for dismantling feasible for JWTF decommissioning were obtained and were summarized in tables. On the basis of the research, practical applicability of those techniques to decommissioning of JWTF was evaluated. This report contains brief surveyed summaries related to JWTF decommissioning. (H. Itami)

  8. Publication bias in situ

    Directory of Open Access Journals (Sweden)

    Phillips Carl V

    2004-08-01

    Full Text Available Abstract Background Publication bias, as typically defined, refers to the decreased likelihood of studies' results being published when they are near the null, not statistically significant, or otherwise "less interesting." But choices about how to analyze the data and which results to report create a publication bias within the published results, a bias I label "publication bias in situ" (PBIS. Discussion PBIS may create much greater bias in the literature than traditionally defined publication bias (the failure to publish any result from a study. The causes of PBIS are well known, consisting of various decisions about reporting that are influenced by the data. But its impact is not generally appreciated, and very little attention is devoted to it. What attention there is consists largely of rules for statistical analysis that are impractical and do not actually reduce the bias in reported estimates. PBIS cannot be reduced by statistical tools because it is not fundamentally a problem of statistics, but rather of non-statistical choices and plain language interpretations. PBIS should be recognized as a phenomenon worthy of study – it is extremely common and probably has a huge impact on results reported in the literature – and there should be greater systematic efforts to identify and reduce it. The paper presents examples, including results of a recent HIV vaccine trial, that show how easily PBIS can have a large impact on reported results, as well as how there can be no simple answer to it. Summary PBIS is a major problem, worthy of substantially more attention than it receives. There are ways to reduce the bias, but they are very seldom employed because they are largely unrecognized.

  9. Project gnome decontamination and decommissioning plan

    International Nuclear Information System (INIS)

    The document presents the operational plan for conducting the final decontamination and decommissioning work at the site of the first U.S. nuclear detonation designed specifically for peaceful purposes and the first underground event on the Plowshare Program to take place outside the Nevada Test Site. The plan includes decontamination and decommissioning procedures, radiological guidelines, and the NV concept of operations

  10. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Science.gov (United States)

    2011-01-21

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction AGENCY... 23, 2010 (75 FR 80697) relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is...

  11. Survey of decontamination and decommissioning techniques

    International Nuclear Information System (INIS)

    Reports and articles on decommissioning have been reviewed to determine the current technology status and also attempt to identify potential decommissioning problem areas. It is concluded that technological road blocks, which limited decommissioning facilities in the past have been removed. In general, techniques developed by maintenance in maintaining the facility have been used to decommission facilities. Some of the more promising development underway which will further simplify decommissioning activities are: electrolytic decontamination which simplifies some decontaminating operations; arc saw and vacuum furnace which reduce the volume of metallic contaminated material by a factor of 10; remotely operated plasma torch which reduces personnel exposure; and shaped charges, water cannon and rock splitters which simplify concrete removal. Areas in which published data are limited are detailed costs identifying various components included in the total cost and also the quantity of waste generated during the decommissioning activities. With the increased awareness of decommissioning requirements as specified by licensing requirements, design criteria for new facilities are taking into consideration final decommissioning of buildings. Specific building design features will evolve as designs are evaluated and implemented

  12. 75 FR 80697 - Nuclear Decommissioning Funds

    Science.gov (United States)

    2010-12-23

    ... two types of costs are (1) costs to decommission structures, systems, and components from a nuclear... provides that costs for the final decommissioning of structures, systems, and components from a nuclear... nuclear power reactor that is used predominantly in the trade or business of the furnishing or sale...

  13. Decommission of nuclear ship `MUTSU`

    Energy Technology Data Exchange (ETDEWEB)

    Tateyama, Takeshi [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

    1996-11-01

    The nuclear-powered ship `MUTSU` was decommissioned by removing the reactor room in June 1995, which was hoisted and transported by a floating crane to a shore storage room at Sekinehama, Aomori Prefecture. This work was carried out in three stages: extraction of the spent fuel assemblies and neutron sources, dismantling of the machinery in the reactor auxiliary room, and separation and transportation of the reactor together with the secondary shielding structure and surrounding hull. IHI mainly conducted the third stage work. The separation work of the reactor room structure using a semisubmersible barge is outlined. Stress analysis and design of the reactor room for lifting work is also described. (author)

  14. Fugitive emissions of methane from abandoned, decommissioned oil and gas wells

    Science.gov (United States)

    Worrall, Fred; boothroyd, Ian; Almond, Sam; Davies, Richard

    2015-04-01

    The aim of this study was to consider the potential legacy of increased onshore, unconventional gas production by examining the integrity of decommissioned, onshore, oil and gas wells in the UK. In the absence of a history of unconventional hydrocarbon exploitation in the UK, conventional onshore sites were considered and an examination of pollution incidents records had suggested that only a small fraction of onshore wells could show integrity failures. In this study the fugitive emissions of methane from former oil and gas production wells onshore in the UK were considered as a measure of well integrity. The survey considered 49 decommissioned (abandoned) wells from 4 different basins that were between 8 and 78 years old; all but one of these wells would be considered as having been decommissioned properly, i.e. wells cut, sealed and buried by soil cover to the extent that the well sites were being used for agriculture. For each well site the soil gas methane was analysed multiple times and assessed relative to a nearby control site of similar land-use and soil type. The results will be expressed in terms of the proportion and extent of well integrity failure, or success, over time since decommissioning and relative to local control sites. The probability of failure and the emissions factor for decommissioned wells will be presented.

  15. Decommissioning plan for TRIGA Mark-2

    International Nuclear Information System (INIS)

    Korea Research Reactor 1(KRR 1; TRIGA Mark-2) is the first reactor in Korea, but its decommissioning is underway due to its life. In this paper, presenting the reason and object of decommissioning KRR 1, then describing reactor structure and survey result of the facility, activation and contamination status around reactor and nearby equipment and vicinity. Estimating dose rate was evaluated for every work stage. Those of survey, evaluation and radiological status were considered to determine the safe and reasonable decommissioning methods. The order of decommissioning works are divided by section to minimize possible hazard. Proposed decommissioning plan is based on hazard and operability study to protect workers and residents from radiation expose. (author). 12 refs., 5 tabs., 6 figs

  16. Decommissioning plan for TRIGA Mark-2

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Kook; Lee, B.J.

    1999-04-01

    Korea Research Reactor 1(KRR 1; TRIGA Mark-2) is the first reactor in Korea, but its decommissioning is underway due to its life. In this paper, presenting the reason and object of decommissioning KRR 1, then describing reactor structure and survey result of the facility, activation and contamination status around reactor and nearby equipment and vicinity. Estimating dose rate was evaluated for every work stage. Those of survey, evaluation and radiological status were considered to determine the safe and reasonable decommissioning methods. The order of decommissioning works are divided by section to minimize possible hazard. Proposed decommissioning plan is based on hazard and operability study to protect workers and residents from radiation expose. (author). 12 refs., 5 tabs., 6 figs.

  17. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    The objectives of this coordinated research programme (CRP) were to promote the exchange of information on the practical experience by Member States in decontamination and decommissioning. The scope of the programme included several areas of decontamination and decommissioning rather than focusing on a single aspect of it, in line with recommendation of the experts who participated in Phase 1 of the CRP. Experts felt that this format would generate better awareness of decontamination and decommissioning and would be more effective vehicle for the exchange of information by stimulating broader discussion on all aspects of decontamination and decommissioning. Special emphasis was given to the development of principles and methodologies to facilitate decommissioning and to the new methods and techniques for optimization of decontamination and disassembly of equipment. Refs, figs, tabs

  18. The development of a tailings decommissioning concept: A case history, Rabbit Lake, Canada

    International Nuclear Information System (INIS)

    The Rabbit Lake orebody was discovered in 1968. From 1975 to 1985, approximately 6.5 million tonnes of tailings were deposited in a valley confined by bedrock ridges and two earth-filled dams. Planning for the decommissioning of the Rabbit Lake tailings management facility started in 1983 when the relocation of the tailings into the mined out Rabbit Lake open pit and alternatively, the in-situ decommissioning were examined. The latter was preferred since it offered a sufficiently low individual dose rate and an insignificant environmental impact. To pursue the in-situ decommissioning, three options were considered: (1) A concave surface with natural cover, surface water management and dam stabilization, (2) a convex surface with natural cover, surface water management and dam stabilization and (3) a minimum reclamation option incorporating surface water management only. By 1988, an electromagnetic conductivity survey, a pathway analysis, a stream flow reconnaissance and continued environmental monitoring in the vicinity of the tailings area were completed. On the basis of the results, the cover design was optimized taking into account areas of higher consolidation defined by the presence of distal slimes and frozen layers. In addition, pre-loading of the slime area was considered to alleviate post-construction settlements. (Abstract only)

  19. Measuring and reporting on decommissioning progress

    International Nuclear Information System (INIS)

    One of the challenges facing AECL, as well as other organizations charged with the responsibility of decommissioning nuclear facilities, is the means by which to measure and report on decommissioning progress to various audiences which, in some cases, may only have a peripheral knowledge or understanding of the complexities associated with the decommissioning process. The reporting and measurement of decommissioning progress is important for a number of reasons, i.e., It provides a vehicle by which to effectively communicate the nature of the decommissioning process; It ensures that stakeholders and shareholders are provided with a transparent and understandable means for assessing value for money; It provides a means by which to integrate the planning, measurement, and operational aspects of decommissioning One underlying reason behind the challenge of reporting decommissioning progress lies in the fact that decommissioning programs are generally executed over periods of time that far exceed those generally associated with typical design and build projects. For example, a decommissioning program could take decades to complete in which case progress on the order of a few percent in any one year might be typical. However, such progress may appear low compared to that seen with more typical projects that can be completed in a matter of years. As a consequence, AECL undertook to develop a system by which to measure decommissioning progress in a straightforward, meaningful, and understandable fashion. The system is not rigorously objective, and there are subjective aspects that are necessitated by the need to keep the system readily understandable. It is also important to note that while the system is simple in concept, there is, nonetheless, significant effort involved in generating and updating the parameters used as input, and in the actual calculations. (author)

  20. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  1. In-situ uranium leaching

    International Nuclear Information System (INIS)

    This invention provides a method for improving the recovery of mineral values from ore bodies subjected to in-situ leaching by controlling the flow behaviour of the leaching solution. In particular, the invention relates to an in-situ leaching operation employing a foam for mobility control of the leaching solution. A foam bank is either introduced into the ore bed or developed in-situ in the ore bed. The foam then becomes a diverting agent forcing the leaching fluid through the previously non-contacted regions of the deposit

  2. Role of the statistician in the decommissioning of the New Brunswick Laboratory and other nuclear facilities

    International Nuclear Information System (INIS)

    This report examines what the statistician can contribute to decommissioning operations, with particular emphasis on the New Brunswick Laboratory (NBL) currently scheduled for decommissioning beginning in FY81. In the opinion of the author, a professional statistician should be a full member of the planning team directing decommissioning operations at the New Brunswick Laboratory. This opinion is based in part on the familiarity with the valuable contributions made by statisticians toward the cleanup of transuranics in soil on the Enewetak Atoll. More generally, however, the professional statistician can help plan the decommissioning effort to help ensure that representative data are obtained, analyzed and, interpreted in appropriate ways so that RA decisions can be made with the required confidence. The statistician's contributions at the NBL could include providing guidance on the number and location of samples and in-situ measurements, analyzing and interpreting these data, designing a data management and documentation system, interfacing with the certification contractor's statistician, and assisting in writing documentation and final reports. In all cases, the statistician should work closely with the professional health physicist and others on the planning team in a closely coordinated effort of planning and data analysis

  3. The decommissioning NPP A-1

    International Nuclear Information System (INIS)

    Project of decommissioning NPP A-1 is split into 4 main groups of tasks. Tasks in group 1 are focused on the solution of selected problems that have immediate impact on the environment. It is mainly the solution of problems in the building of cleaning station of wastage water and in the building with underground storage tanks for wastage water and solid radwaste, including the prevention of wash-out and penetration of contaminated soil from these buildings into surface and underground waters. A part of addressing these tasks is a controlled of generated radwaste-predominatly sludge with various physical and chemical properties. Tasks in group 2- following the removal of spent fuel-are focused on the management of all radwaste in the long-term storage facility, in the short-term storage facility, equipment of transport and technology part, equipment in hot cells. Tasks in group 3 are focused on development of technology procedures for treatment and conditioning of sludge, contaminated soils and concrete crush, saturated ionexes and ash from incineration facility of the Bohunice radwaste treatment and conditioning complex. Tasks in group 4 are focused on the methodology. And technical support for particular activities applicable during decommissioning NPP

  4. Uranium hexafluoride production plant decommissioning

    International Nuclear Information System (INIS)

    The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF6) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

  5. Government Assigns New Supervisory Task. Safe Decommissioning

    International Nuclear Information System (INIS)

    When the Government decided to shutdown one of the two Barsebaeck reactors in February of 1998, it presented SKI with a task that came much earlier than expected; the supervision of the decommissioning of a reactor. As a result of proposals presented in Parliament, SKI began the formulation of a long-term strategy in 1997 for the inspection of a nuclear plant during the decommissioning process. As a preliminary task, SKI started a research programme dealing with the potential risks associated with the transition from normal operations through shutdown to final deconstruction of the power plant. Emphasis was laid on safety culture issues and on questions of organization, as opposed to an earlier stress on the purely technical aspects of decommissioning. After a long period of uncertainty, following much discussion, in July 1998 a Government decision was finally reached to shutdown the first reactor at Barsebaeck. This was carried out in November 1999. It is still uncertain as to when the other reactor will be decommissioned; a decision is expected at the earliest in 2004. This uncertainty, resulting from the prolonged decision making process, could be detrimental to the safety culture on the site; motivation could diminish, and key personnel could be lost. Decommissioning is a new phase in the life cycle of a plant, giving rise to new inspection issues of supervision. During the period of uncertainty, while awaiting SKI has identified ten key areas, dealing with the safety culture of the organization, in connection with the decommissioning of Barsebaeck 1. 1. Obtaining and retaining staff competence during decommissioning; 2. Sustaining organizational memory; 3. Identifying key organizational functions and management skills that are critical during the transition from operations to decommissioning. 4. Sustaining organizational viability and accountability for decommissioning; 5. Sustaining motivation and trust in management of dismantlement; 6. Overseeing

  6. In Situ Aerosol Detector Project

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA is developing new platform systems that have the potential to benefit Earth science research activities, which include in situ instruments for atmospheric...

  7. In situ leaching of uranium

    International Nuclear Information System (INIS)

    A process is described for the in-situ leaching of uranium-containing ores employing an acidic leach liquor containing peroxymonosulphuric acid. Preferably, additionally, sulphuric acid is present in the leach liquor. (author)

  8. The decommissioning plan of the Nuclear Ship MUTSU

    Energy Technology Data Exchange (ETDEWEB)

    Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T. [Japan Atomic Energy Research Inst., Mutsu, Aomori (Japan). Mutsu Establishment

    1995-07-01

    This paper describes the review about the decommissioning plan and present state of the Nuclear Ship Mutsu. The decommissioning of the Mutsu is carried out by Removal and Isolation method. The procedure of the decommissioning works is presented in this paper. The decommissioning works started in April, 1992 and it takes about four years after her last experimental voyage. (author).

  9. 26 CFR 1.88-1 - Nuclear decommissioning costs.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs... collect nuclear decommissioning costs from ratepayers residing in State A. With respect to the sale...

  10. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

  11. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    Energy Technology Data Exchange (ETDEWEB)

    Agnew, Kieran [AWE, Aldermaston, Reading, RG7 4PR (United Kingdom)

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes

  12. Social effects of decommissioning Trawsfynydd Power Station

    International Nuclear Information System (INIS)

    The decision to close Trawsfynydd in 1993 had significant implications for the staff and local community. The site is situated within a National Park and local employment opportunities are limited. The staff and local communities were consulted regarding the issues arising from closure and decommissioning. This consultation influenced the decommissioning strategy for the site, with emphasis placed on the mitigation of the effects of closure. Subsequent studies have shown that the adopted strategies have served to limit the social and economic effects. The experience at Trawsfynydd has proved to be generally applicable at other decommissioning sites. (author)

  13. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  14. Deactivation, Decontamination and Decommissioning Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  15. Development of a Decommissioning Certificate Program

    International Nuclear Information System (INIS)

    A Decommissioning Certificate Program has been developed at Washington State University Tri-Cities (WSU TC) in conjunction with Bechtel Hanford, Inc. (BHI), and the U.S. Department of Energy (DOE)to address the increasing need for qualified professionals to direct and manage decommissioning projects. The cooperative effort between academia, industry, and government in the development and delivery of this Program of education and training is described, as well as the Program's design to prepare students to contribute sooner, and at a higher level, to decommissioning projects

  16. TA-2 Water Boiler Reactor Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Durbin, M.E. (ed.); Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m{sup 3} of low-level solid radioactive waste and 35 m{sup 3} of mixed waste. 15 refs., 25 figs., 3 tabs.

  17. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    International Nuclear Information System (INIS)

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method

  18. Considerations about the European Decommissioning Academy (EDA)

    International Nuclear Information System (INIS)

    The concept of the European Decommissioning Academy, to be launched in Slovakia in June 2015, is described. The main goal is to educate a new generation of experts in the decommissioning of nuclear facilities, with focus on VVER type reactors. This year the Academy activities will include lessons, practical exercises in laboratories, and 2 days on-site training at the Jaslovske Bohunice V-1 nuclear power plant. A 4-days' visit to major European decommissioning facilities in Switzerland and Italy is also planned. (orig.)

  19. Decommissioning the Research Nuclear Reactor Vvr-S Magurele - Analyze, Justification and Selection of Decommissioning Strategy

    Science.gov (United States)

    Dragusin, M.; Popa, V.; Boicu, A.; Tuca, C.; Iorga, I.; Mustata, C.

    2004-09-01

    The decommissioning of Research Nuclear Reactor VVR-S Magurele - Bucharest involves the removal of the radioactive and hazardous materials to permit the facility to be released without representing a further risk to human health and the environment [1-3]. A very important aspect of decommissioning is the analyze, justification and selection of the decommissioning strategy. Two strategies: DECON (Immediate Dismantling) and SAFSTOR (Safe Enclosure) are in study (see Table 1)... Note from Publisher: This article contains the abstract and references only.

  20. Decommissioning cost estimates based on the international structure for decommissioning costing

    International Nuclear Information System (INIS)

    Decommissioning cost estimates is essential part of decommissioning planning in all stages of nuclear installation lifetime. It has been recognized that there is a variety of formats, content and practice in decommissioning costing, due to the specific national requirement or to different assumptions. These differences make the process of decommissioning costing less transparent and more complicated to review. To solve these issues the document: 'A Proposed Standardised List of Items for Costing Purposes in the Decommissioning of Nuclear Installation' (known as 'Yellow Book') was jointly published by IAEA, OECD/NEA and EC in 1999. After a decade, the document was revised and issued by same organizations under the title: 'International Structure for Decommissioning Costing (ISDC) of Nuclear Installation. ISDC as the list of typical decommissioning activities (could be used also a check-list) provides s general cost structure suitable for use for all types of nuclear installations i.e. power plants, research reactors, fuel cycle facilities or laboratories. The purpose of the ISDC, is to facilitate the communication and to promote uniformity and to provide a common platform in presenting the decommissioning costs. Clear definition of ISDC items supports the common understanding of cost items, i.e. what is behind the cost. ISDC decommissioning activities are organised in a hierarchical structure, with the 1st and 2nd levels being aggregations of basic activities identified at the 3rd level. At (author)

  1. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    International Nuclear Information System (INIS)

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  2. The NEA Co-operative Programme on Decommissioning. A Decade of Progress

    International Nuclear Information System (INIS)

    -operative Programme on Decommissioning, and in particular through the information exchange and review within the TAG, it has become evident that: decommissioning can and has been done in a safe, cost-effective and environmentally friendly manner; current technologies have demonstrated their effectiveness and robust performance in numerous decommissioning activities; and feedback of experience on design, construction and operation is a considerable help for reliable planning, cost evaluation and successful realisation of a decommissioning project. Regarding technical challenges, specific trends have been observed over the last decade. Large contaminated components, for example heat exchangers, steam generators, large tanks etc., that have been segmented in situ into smaller pieces, are increasingly removed 'in one piece' and transported outside the contained area into separated facilities for further processing. Regarding the use of robotics, the CPD observed that industrial robots may have a limited applicability in decommissioning, in contrary to earlier expectations that robotic methods would be extensively used in the dismantling of radioactive components, especially in the high radiation areas in fuel facilities. Experience collected within the CPD also pointed to challenges in the release of alpha contaminated areas, where seepage of contamination into cracks and reappearance of activity in walls previously declared as 'clean' posed specific problems. On the side of organisational trends a movement towards sequential licensing has been observed. This is seen as being advantageous for the management of projects, but also increases the efforts needed for documentation. Other challenges for management raise from company reorganisation, privatisation and budgetary difficulties. The lessons learnt by the participants in the CPD have been helpful for individual projects in making project decisions and in many cases have influenced general project directions. Key examples concern

  3. Decommissioning of DR 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2006-01-15

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  4. The cost of decommissioning uranium mill tailings

    International Nuclear Information System (INIS)

    This report identifies several key operations that are commonly carried out during decommissioning of tailings areas in the Canadian environment. These operations are unit costed for a generic site to provide a base reference case. The unit costs have also been scaled to the quantities required for the decommissioning of four Canadian sites and these scaled quantities compared with site-specific engineering cost estimates and actual costs incurred in carrying out the decommissioning activities. Variances in costing are discussed. The report also recommends a generic monitoring regime upon which both short- and longer-term environmental monitoring costs are calculated. Although every site must be addressed as a site-specific case, and monitoring programs must be tailored to fit a specific site, it would appear that for the conventional decommissioning and monitoring practices that have been employed to date, costs can be reasonably estimated when site-specific conditions are taken into account

  5. Sellafield Decommissioning Programme - Update and Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Lutwyche, P. R.; Challinor, S. F.

    2003-02-24

    The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted.

  6. Health physics considerations in decontamination and decommissioning

    International Nuclear Information System (INIS)

    These proceedings contain papers on legal considerations, environmental aspects, decommissioning equipment and methods, instrumentation, applied health physics, waste classification and disposal, and project experience. Separate abstracts have been prepared for individual papers

  7. Decommissioning: from COMECON to CIS and RUSSIA

    International Nuclear Information System (INIS)

    NPP decommissioning experience in the USSR and the Commonwealth Independent States (CIS) members was actively accumulated over ten years since 1982, by Russian experts in particular. Nevertheless, it is not well renowned throughout the scientists and engineers from both Russia and other near' (the CIS) and 'distant' foreign countries. A general review on NPP decommissioning in the CIS has been published just now. An unshown before NPP decommissioning issues are presented in the report. The first program on NPP decommissioning was developed under the aegis of COMECOM with the leadership of Russian experts. The most considerable results are the feasibility studies of Armenia NPP, the Novovoronezh NPP first construction stage (two units) and Bohunice V - 1 unit. (J.P.N.)

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

    International Nuclear Information System (INIS)

    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. Decommissioning of the BR3 PWR

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V.; Klein, M

    1998-07-01

    The objectives, programme and main achievements of SCK-CEN's decommissioning programme in 1997 are summarised. Particular emphasis is on the BR3 decommissioning project. In 1997, auxiliary equipment and loops were dismantled; concrete antimissile slabs were decontaminated; the radiology of the primary loop was modelled; the quality assurance procedure for dismantling loops and equipment were implemented; a method for the dismantling of the reactor pressure vessel was selected; and contaminated thermal insulation of the primary loop containing asbestos was removed.

  10. Decommissioning Project Manager's Implementing Instructions (PMII)

    International Nuclear Information System (INIS)

    Decommissioning Project personnel are responsible for complying with these PMII. If at any time in the performance of their duties a conflict between these instructions and other written or verbal direction is recognized or perceived, the supervisor or worker shall place his/her work place in a safe condition, stop work, and seek resolution of the conflict from the Decommissioning Project Manager or his designee

  11. Risk Management of Large Component in Decommissioning

    International Nuclear Information System (INIS)

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down

  12. Safety in decommissioning of research reactors

    International Nuclear Information System (INIS)

    This Guide covers the technical and administrative considerations relevant to the nuclear aspects of safety in the decommissioning of reactors, as they apply to the reactor and the reactor site. While the treatment, transport and disposal of radioactive wastes arising from decommissioning are important considerations, these aspects are not specifically covered in this Guide. Likewise, other possible issues in decommissioning (e.g. land use and other environmental issues, industrial safety, financial assurance) which are not directly related to radiological safety are also not considered. Generally, decommissioning will be undertaken after planned final shutdown of the reactor. In some cases a reactor may have to be decommissioned following an unplanned or unexpected event of a series or damaging nature occurring during operation. In these cases special procedures for decommissioning may need to be developed, peculiar to the particular circumstances. This Guide could be used as a basis for the development of these procedures although specific consideration of the circumstances which create the need for them is beyond its scope

  13. CPP-603 Chloride Removal System Decontamination and Decommissioning

    International Nuclear Information System (INIS)

    The CPP-603 (annex) Chloride Removal System (CRS) Decontamination and Decommissioning (D ampersand D) Project is described in this report. The CRS was used for removing Chloride ions and other contaminants that were suspended in the waters of the underwater fuel storage basins in the CPP-603 Fuel Receiving and Storage Facility (FRSF) from 1975 to 1981. The Environmental Checklist and related documents, facility characterization, decision analysis', and D ampersand D plans' were prepared in 1991. Physical D ampersand D activities were begun in mid summer of 1992 and were completed by the end of November 1992. All process equipment and electrical equipment were removed from the annex following accepted asbestos and radiological contamination removal practices. The D ampersand D activities were performed in a manner such that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) occurred

  14. In situ measurements of microbially-catalyzed nitrification and nitrate reduction rates in an ephemeral drainage channel receiving water from coalbed natural gas discharge, Powder River Basin, Wyoming, USA

    Science.gov (United States)

    Harris, S.H.; Smith, R.L.

    2009-01-01

    Nitrification and nitrate reduction were examined in an ephemeral drainage channel receiving discharge from coalbed natural gas (CBNG) production wells in the Powder River Basin, Wyoming. CBNG co-produced water typically contains dissolved inorganic nitrogen (DIN), primarily as ammonium. In this study, a substantial portion of discharged ammonium was oxidized within 50??m of downstream transport, but speciation was markedly influenced by diel fluctuations in dissolved oxygen (> 300????M). After 300??m of transport, 60% of the initial DIN load had been removed. The effect of benthic nitrogen-cycling processes on stream water chemistry was assessed at 2 locations within the stream channel using acrylic chambers to conduct short-term (2-6??h), in-stream incubations. The highest ambient DIN removal rates (2103????mol N m- 2 h- 1) were found at a location where ammonium concentrations > 350????M. This occurred during light incubations when oxygen concentrations were highest. Nitrification was occurring at the site, however, net accumulation of nitrate and nitrite accounted for nitrification was not a factor and changes in DIN removal rates were controlled by nitrate reduction, diel fluctuations in oxygen concentration, and availability of electron donor. This study indicates that short-term adaptation of stream channel processes can be effective for removing CBNG DIN loads given sufficient travel distances, but the long-term potential for nitrogen remobilization and nitrogen saturation remain to be determined.

  15. International Atomic Energy Agency activities in decommissioning

    International Nuclear Information System (INIS)

    Full text: The International Atomic Energy Agency (IAEA) has been addressing the safety and technical issues of decommissioning for over 20 years, but their focus has been primarily on planning. Up to know, the activities have been on an ad hoc basis and sometimes, important issues have been missed. A new Action Plan on the Decommissioning of Nuclear Facilities has recently been approved by the Agency's board of Governors which will focus the Agency's efforts and ensure that our Member States' concerns are addressed. The new initiatives associated with this Action Plan will help ensure that decommissioning activities in the future are performed in a safe and coherent manner. The International Atomic Energy Agency (IAEA) has been preparing safety and technical documents concerning decommissioning since the mid-1980's. There have been over 30 documents prepared that provide safety requirements, guidance and supporting technical information. Many of these documents are over 10 years old and need updating. The main focus in the past has been on planning for decommissioning. During the past five years, a set of Safety Standards have been prepared and issued to provide safety requirements and guidance to Member States. However, decommissioning was never a real priority with the Agency, but was something that had to be addressed. To illustrate this point, the first requirements documents on decommissioning were issued as part of a Safety Requirements [1] on pre-disposal management of radioactive waste. It was felt that decommissioning did not deserve its own document because it was just part of the normal waste management process. The focus was mostly on waste management. The Agency has assisted Member States with the planning process for decommissioning. Most of these activities have been focused on nuclear power plants and research reactors. Now, support for the decommissioning of other types of facilities is being requested. The Agency is currently providing technical

  16. Decommissioning of nuclear facilities: Germany’s experience

    International Nuclear Information System (INIS)

    Germany has gained considerable experience in the decommissioning of nuclear facilities since the 1970s. Currently 16 nuclear power plants, both power and prototype reactors, are at different stages of decommissioning. Three decommissioning projects have been completed. Future tasks in Germany are the completion of the current decommissioning projects and the decommissioning of the nuclear facilities that are still operating once they have reached the end of their operating life. The number of parallel decommissioning projects of large scale facilities required by the phase-out of nuclear power could pose challenges in terms of the availability and maintenance of competences at all levels (operators, regulatory body, technical support organizations, and suppliers)

  17. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  18. In situ solution mining technique

    International Nuclear Information System (INIS)

    A method of in situ solution mining is disclosed in which a primary leaching process employing an array of 5-spot leaching patterns of production and injection wells is converted to a different pattern by converting to injection wells all the production wells in alternate rows

  19. Securing decommissioning funds. Why organization matters?

    International Nuclear Information System (INIS)

    Full text: Securing decommissioning funds requires that the financial resources set aside for the purpose of decommissioning be managed prudently. Decommissioning of nuclear power plant is prescribed by National Atomic Laws or by other nuclear legislation. It is a mandatory operation. The operators of nuclear power plants set money aside for that purpose. This is known as 'Decommissioning reserve fund'. Decommissioning implies costs very distant in time. Thus, it is obvious, from an economic point of view, that the funds set aside should be managed. As decommissioning is mandatory, the funds accumulated should be secured. In others words, they should be available when needed. Availability of funds is influenced by endogenous and exogenous factors. Endogenous factors are a matter of design of the reserve funds. They include the management of the funds, its monitoring and control... Availability of funds is influenced by these factors, depending on the rules to which the behaviour of the manager of the funds is subjected. In contrast, exogenous factors deal with the energy context. These factors are mainly the electricity sector organisation and/or the overall economic situation. They are decisive factors of the economic performance of the reserve fund for a given design. Therefore, the requirement of availability of funds, when needed, is a matter of compatibility between the design of the decommissioning funds and the electricity context. Put differently, reserve fund's design need to be consistent with the electricity context's features in respect of the availability of funds. Current reserve funds were designed in a context of monopoly regime. In this context, availability of decommissioning funds was not questionable. At least, as far as the design of the reserve funds is concerned. This is because nuclear generator didn't confront any competition pressure. Electricity prices were set trough rate base mechanism, and all the business risks were borne by the

  20. Decommissioning of an irradiation unit

    Energy Technology Data Exchange (ETDEWEB)

    Richards, A.G. [Radiation Protection and Safety Services, Univ. of Leeds, Leeds (United Kingdom)

    2000-05-01

    Distributed throughout hospital, research establishments in the United Kingdom and many other countries are Irradiation Units and Teletherapy machines used for either research purposes or treatment of patients for radiotherapy. These Irradiation Units and Teletherapy machines are loaded with radioactive sources of either Cobalt 60 or Caesium 137. The activity of these sources can range from 1 Terabecquerel up to 100 Terabecquerels or more. Where it is possible to load the radioactive sources without removal from the shielded container into a transport package which is suitable for transport decommissioning of a Teletherapy machine is not a major exercise. When the radioactive sources need to be unloaded from the Irradiation Unit or Teletherapy machine the potential exists for very high levels of radiation. The operation outlined in the paper involved the transfer from an Irradiation Unit to a transport package of two 3.25 Terabecquerel sources of Cobalt 60. The operation of the removal and transfer comes within the scope of the United Kingdom Ionising Radiation Regulations 1985 which were made following the Recommendations of the International Commission on Radiological Protection. This paper illustrates a safe method for this operation and how doses received can be kept within ALARA. (author)

  1. Decontamination and decommissioning costing efforts

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE), Office of Environmental Management (EM) is responsible for decontamination and decommissioning (D and D) of a wide variety of facilities ranging from reactors to fuel cycle processing buildings throughout the country. The D and D effort represents a large financial investment and a considerable challenge for the DOE and contractor program and project managers. Specifically, the collection and sharing of useful cost data and development of cost estimates are difficult in an environment in which the availability of these data is limited and the technologies and project methods are evolving. Sound cost data are essential for developing project cost estimates; baselines; and project management, benchmarking, and continuous improvement purposes. This paper will focus on some initiatives that in coordination with other federal agencies and international organizations, the DOE Environmental Management Applied Cost Engineering (ACE) Team is taking to standardize cost definitions; to collect, analyze, and report D and D cost data; and to develop fast, accurate, and easy-to-use cost-estimating models for D and D work

  2. Decommissioning of fast reactors after sodium draining

    International Nuclear Information System (INIS)

    Acknowledging the importance of passing on knowledge and experience, as well mentoring the next generation of scientists and engineers, and in response to expressed needs by Member States, the IAEA has undertaken concrete steps towards the implementation of a fast reactor data retrieval and knowledge preservation initiative. Decommissioning of fast reactors and other sodium bearing facilities is a domain in which considerable experience has been accumulated. Within the framework and drawing on the wide expertise of the Technical Working Group on Fast Reactors (TWG-FR), the IAEA has initiated activities aiming at preserving the feedback (lessons learned) from this experience and condensing those to technical recommendations on fast reactor design features that would ease their decommissioning. Following a recommendation by the TWG-FR, the IAEA had convened a topical Technical Meeting (TM) on 'Operational and Decommissioning Experience with Fast Reactors', hosted by CEA, Centre d'Etudes de Cadarache, France, from 11 to 15 March 2002 (IAEA-TECDOC- 1405). The participants in that TM exchanged detailed technical information on fast reactor operation and decommissioning experience with various sodium cooled fast reactors, and, in particular, reviewed the status of the various decommissioning programmes. The TM concluded that the decommissioning of fast reactors to reach safe enclosure presented no major difficulties, and that this had been accomplished mainly through judicious adaptation of processes and procedures implemented during the reactor operation phase, and the development of safe sodium waste treatment processes. However, the TM also concluded that, on the path to achieving total dismantling, challenges remain with regard to the decommissioning of components after sodium draining, and suggested that a follow-on TM be convened, that would provide a forum for in-depth scientific and technical exchange on this topic. This publication constitutes the Proceedings of

  3. Decommissioning database of V1 NPP

    International Nuclear Information System (INIS)

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, have been carrying out BIDSF B6.4 project - Decommissioning database development (June 2008 until July 2010). The main purpose of the B6.4 project is to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. After finalization of all activities DDB includes over 75.000 records related to individual equipment and civil structures described by almost 3.000.000 parameters. On the basis of successful completion of the original contract the amendment was signed between JAVYS and Consultant's Consortium related to experimental characterization of NPP activated components. The works within this amendment have been still running. (authors)

  4. Closing responsibilities: decommissioning and the law

    International Nuclear Information System (INIS)

    Laws change over time, with the times. Interpretations of old laws shift and the need for new laws emerges. There are endless reasons for these necessary changes, but the basic impetus is the changing nature of societal circumstance. Fifty years ago there were no laws directly governing nuclear power in any way. Today we know that nuclear power touches people from their wallets to their descendants. Currently, many laws related to nuclear power are in place, laws which protect all sectors of society from electricity generating bodies to a newborn child, and the Chernobyl accident has broadened the legal ramifications of nuclear power even more. This expanding body of nuclear law reflects our expanding understanding of nuclear power from its technical beginnings to its societal consequences and implications. The law is now beginning to reflect the growing significance of decommissioning. What are the relationships between decommissioning and the existing laws, government agencies, and policies? Ironically, although the UK will lead the world in addressing decommissioning responsibilities, there are no explicit laws in place to govern the process. In the absence of specific legislation governing decommissioning, the primary responsibilities fall to the operators of the power plants, a circumstance not lost on those involved in privatization. In this chapter, the wide and varied legal ramifications of decommissioning are examined. (author)

  5. Current trends in decommissioning and environmental remediation of nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning and environmental remediation of civil nuclear facilities represents a considerable challenge for the countries involved in this activity around the world. It includes aspects and problems associated with management, technology, safety and the environment. Over the past few decades, operators worldwide have acquired important experience in the decommissioning and environmental remediation of nuclear sites. A large number of nuclear facilities have ceased operations, and it is envisaged that this number will increase considerably over the coming years. Seventeen power reactors have already been decommissioned, out of more than 150 power reactors shut down or undergoing decommissioning, while more than 180 research reactors have been shut down or are being decommissioned with more than 300 already fully decommissioned. A total of 170 other nuclear cycle facilities have been shut down or are being decommissioned and a further 125 have been completely decommissioned. Spain is one of the countries with experience and activity under way in this field

  6. The collection of information, data and materials samples from concrete structures on nuclear facilities under decommissioning for ageing and degradation evaluation

    International Nuclear Information System (INIS)

    The collection of information from nuclear facilities under decommissioning can usefully inform operators of existing plant and designers of new facilities. The evaluation of the performance of concrete structures long after their construction is a relevant safety issue for nuclear installations. Many nuclear facilities are approaching the end of their design life and programmes to extend operating licences have been undertaken to ensure adequate safety levels for extended operational periods and the complete decommissioning phase lasting from a few years up to some decades before dismantling. Ageing management programmes should encompass the full life cycle from conceptual design through to final decommissioning. During decommissioning, dismantling and demolition it is possible to obtain samples from systems, structures and components that have experienced ageing mechanisms in situ and are therefore superior to artificially aged laboratory specimens in informing ageing management programmes and designers of new plant. Such programmes are of value not just to NPPs but also fuel cycle and waste facilities. In order that full benefit may be obtained from the collection of information, data and materials samples from concrete structures on nuclear facilities under decommissioning for ageing and degradation evaluation, these activities must be included in decommissioning plans. In cases where systems, structures and components have been selected for removal, sampling or testing for such purposes, these should be clearly identified and described. This allows specific hazards during these operations to be identified and prevents unintentional loss or destruction of the relevant systems, structures and components during decommissioning. This paper describes the information that may be collected during decommissioning in order to inform plant life management and ageing programmes and new plant designs and the activities required to collect this. Suggestions are also given

  7. Decommissioning of research nuclear reactor WWR-S Bucharest. Analysis, justification and selection of decommissioning strategy

    International Nuclear Information System (INIS)

    The decommissioning of Research Nuclear Reactor WWR-S Bucharest involves the removal of the radioactive and hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. The National Institute of Physics and Nuclear Engineering has overall responsibilities in decommissioning including actions of contractors, submit a decommissioning plan to the regulatory body for approval and no decommissioning activities shall begin without the appropriate approval of the regulatory body. A very important aspect of decommissioning is analysis, justification and selection of decommissioning strategy. There are three strategies: Immediate Dismantling, Safe Enclosure, and Entombment. These strategies have been analyzed taking into account: - Future use of site and facilities; - Infrastructure of the specific site and facilities; - Waste storage and disposal options; - Financial aspects; - Geographical Location; - National, Local and International Legislation; - Facility characterization; Identification of decommissioning objectives; - Description of alternatives: scope, features, specific end points, release criteria, risks and safety issues, effectiveness, feasibility, nature and amount of waste of generated and disposal plans, material recycling/reusing opportunities, cost, schedule, comparative analysis; - Rationale for selecting the preferred alternative. (authors)

  8. Decommissioning in the United Kingdom Atomic Energy Authority

    International Nuclear Information System (INIS)

    The United Kingdom Atomic Energy Authority's policy on decommissioning is described. Several fission reactors have already been taken out of service and the state of decommissioning is given. Estimates of the volume of decommissioning wastes are made. The wastes will be either intermediate-level or low-level wastes. Research and development programmes have been undertaken to allow decommissioning to be safe and cost-effective. Some of the contaminated facilities have been decontaminated and re-used. (U.K.)

  9.  Heavy Lift Methods in Decommissioning of Installations

    OpenAIRE

    Breidablikk, Line Småge

    2010-01-01

     In this report decommissioning of offshore petroleum platforms have been investigated. It treats decommissioning in general, the process of a typical project. A variety of suitable lifting vessels have been presented, and some concepts of removal have been evaluated.Decommissioning is important to go through with because of the environment and the use of the area after the petroleum activities ceases. Other ocean users benefit from the decommissioning because the area can be utilized when it...

  10. Development Of Decommissioning Information Management System for 101 HWRR

    Institute of Scientific and Technical Information of China (English)

    Yi Song

    2016-01-01

    Decommissioning of 101 Heavy Water Research Reactor (HWRR) is radioactive and high-risk project which has to consider the effects of radiation and nuclear waste disposal, so the information system covering 101 HWRR decommissioning project must be established to ensure safety of the project. In this study, by col ecting the decommissioning activity data to establish the decommissioning database, and based on the database to develop information management system.

  11. Eastern and Central Europe Decommissioning, ECED 2015 - Book of Abstracts

    International Nuclear Information System (INIS)

    Scientific conference deals with problems of reactor decommissioning and radioactive waste management in the Central Europe. The Conference included the following sessions: (1): Characterisation and Radioactive Waste Management; (2) Managerial Aspects of Decommissioning; (3) JAVYS Experience with Back-End of Nuclear Power Engineering - Progress in Last 2 Years; (4) Decommissioning Planning and Costing and Education; (5) Technical Aspects of Decommissioning; (6) Radioactive Waste Management; (4) Poster Session. The Book of Abstracts contains two invitation speeches and 30 abstracts.

  12. In situ vadose zone bioremediation.

    Science.gov (United States)

    Höhener, Patrick; Ponsin, Violaine

    2014-06-01

    Contamination of the vadose zone with various pollutants is a world-wide problem, and often technical or economic constraints impose remediation without excavation. In situ bioremediation in the vadose zone by bioventing has become a standard remediation technology for light spilled petroleum products. In this review, focus is given on new in situ bioremediation strategies in the vadose zone targeting a variety of other pollutants such as perchlorate, nitrate, uranium, chromium, halogenated solvents, explosives and pesticides. The techniques for biostimulation of either oxidative or reductive degradation pathways are presented, and biotransformations to immobile pollutants are discussed in cases of non-degradable pollutants. Furthermore, research on natural attenuation in the vadose zone is presented.

  13. Decommissioning in western Europe; Kaernkraftsavveckling i Vaesteuropa

    Energy Technology Data Exchange (ETDEWEB)

    Lundqvist, K. [Castor arbetslivskonsulter AB, Stockholm (Sweden)

    1999-12-01

    This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe

  14. Polyolefin nanocomposites in situ polymerization

    Energy Technology Data Exchange (ETDEWEB)

    Galland, Griselda Barrera; Fim, Fabiana de C.; Milani, Marceo A.; Silva, Silene P. da; Forest, Tadeu; Radaelli, Gislaine, E-mail: griselda.barrera@ufrgs.br [Universidade Federal do Rio Grande de Sul - UFRGS, Porto Alegre, RS (Brazil); Basso, Nara R.S. [Pontificia Universidade Catolica do Rio Grande do Sul, Porto Alegre, RS (Brazil); Quijada, Raul [Universidad de Chile, Santiago (Chile)

    2011-07-01

    Polyethylene and polypropylene nanocomposites using grapheme nanosheets and treated chrysotile have been synthesized by in situ polymerization using metallocene catalysts. The fillers have been submitted to acid, thermal and/ou ultrasound treatments before to introduce them into the polymerization reactor. A complete characterization of the fillers has been done. The nanocomposites have been characterized by SEM, TEM, DRX and AFM. The thermal, mechanic -dynamic, mechanical and electrical properties of the nanocomposites are discussed. (author)

  15. Reactor decommissioning in a deregulated market

    International Nuclear Information System (INIS)

    This paper seeks to summarise BNFL's experience with regard to recent developments in reactor decommissioning and demonstrate how commercial projects in crucial areas of strategy development, project implementation and site restoration are beginning to reduce the risks and uncertainties associated with this important aspect of the nuclear power generation industry. Although the reactor decommissioning market cannot yet be regarded as mature, the key elements of strategy development, waste treatment, dismantling and delicensing have been separately demonstrated as achievable. Together with the implementation of the right organisation, and the developing technology, the risks are being reduced. As more decommissioning projects are delivered, the risks will be reduced further and the confidence of the regulator in the process will improve. This paper sets out to demonstrate this viewpoint. (author)

  16. Decommissioning of DR 2. Final report

    International Nuclear Information System (INIS)

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  17. Site Decommissioning Management Plan. Supplement 1

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC) staff has identified 51 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety, they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC stairs strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 51 sites and describes the status of decommissioning activities at the sites. This is supplement number one to NUREG-1444, which was published in October 1993

  18. Decommissioning of the Loviisa power plant

    International Nuclear Information System (INIS)

    In accordance with the provisions laid in the decision of the Ministry for Trade and Industry Imatran Voima Oy has revised the decommissioning plan for the Loviisa power plant, and submitted it to the authorities for review in December 1993. The plan outlines the technical measures needed to dismantle the radioactive parts of the Loviisa power plant, explains how the resulting waste will be packed and disposed of, and estimates how many people will be needed for the decommissioning waste will be. A general timetable and a cost estimate have also been drawn up on the basis of a detailed working plan. In this report the plan has been revised for cost estimate, activity inventory of the decommissioning waste and radiation dose caused by dismantling work. (orig.). (11 refs., 10 figs., 8 tabs.)

  19. Decommissioning and environmental remediation: An overview

    International Nuclear Information System (INIS)

    The objective in both decommissioning and environmental remediation is to lower levels of residual radioactivity enough that the sites may be used for any purpose, without restriction. In some cases, however, this may not be practical and restrictions may be placed on future land use. Following decommissioning, for example, some sites may be reused for non-nuclear industrial activities, but not for habitation. Some former uranium mining sites may be released for reuse as nature reserves or for other leisure activities. Both decommissioning and environmental remediation are major industrial projects in which the safety of the workforce, the local public and the environment must be ensured from both radiological and conventional hazards. Hence, an appropriate legal and regulatory framework, as well as proper training for personnel both in implementation and in regulatory oversight are among the necessary preconditions to ensure safety

  20. Decommissioning of DR 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N.

    2009-02-15

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  1. Nuclear data requirements for fission reactor decommissioning

    International Nuclear Information System (INIS)

    The meeting was attended by 13 participants from 8 Member States and 2 International Organizations who reviewed the status of the nuclear data libraries and computer codes used to calculate the radioactive inventory in the reactor unit components for the decommissioning purposes. Nuclides and nuclear reactions important for determination of the radiation fields during decommissioning and for the final disposal of radioactive waste from the decommissioned units were identified. Accuracy requirements for the relevant nuclear data were considered. The present publication contains the text of the reports by the participants and their recommendations to the Nuclear Data Section of the IAEA. A separate abstract was prepared for each of these reports. Refs, figs and tabs

  2. Radiation Measurements in the Decommissioning of a Rare Earth Plant

    Institute of Scientific and Technical Information of China (English)

    WANG; Shao-lin

    2012-01-01

    <正>Radiation measurement including radiological source term investigation before the decommissioning, supervisory monitoring during the decommissioning and termination survey after the decommissioning of a rare earth plant were implemented successfully by Radiation Monitoring and Assessment Research Section, Department of Radiation Safety, China Institute of Atomic Energy. The measurements were started in July 2009 and finished in the end of April 2010.

  3. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2013-10-25

    ... COMMISSION Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION... regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC... decommissioning process for nuclear power reactors. The revision takes advantage of the 13 years...

  4. An analysis on the annual decommissioning deposit in NPP

    International Nuclear Information System (INIS)

    This study re-evaluated the methods for estimating and distributing decommissioning cost of nuclear power plant over lifetime. It was resulted out that the annual decommissioning deposit and consequently, the annual decommissioning cost could vary significantly depending on estimating and distributing methods, for instances, the accounting method being used presently by KEPCO and the lifetime levelized method being commonly applied in economic analysis

  5. General principles underlying the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Previous statements on the use of the term 'decommissioning' by the International Atomic Energy Agency, the Atomic Energy Control Board, and the Advisory Committee on Nuclear Safety are reviewed, culminating in a particular definition for its use in this paper. Three decommissioning phases are identified and discussed, leading to eight general principles governing decommissioning including one related to financing

  6. Maintaining Quality in a Decommissioning Environment

    International Nuclear Information System (INIS)

    The decommissioning of AECL's Whiteshell Laboratories is Canada's largest nuclear decommissioning project to date. This research laboratory has operated for forty years since it was set up in 1963 in eastern Manitoba as the Whiteshell Nuclear Research Establishment, complete with 60 MW(Th) test reactor, hot cells, particle accelerators, and multiple large-scale research programs. Returning the site to almost complete green state will require several decades of steady work in combination with periods of storage-with-surveillance. In this paper our approach to maintaining quality during the long decommissioning period is explained. In this context, 'quality' includes both regulatory aspects (compliance with required standards) and business aspects (meeting the customers' needs and exceeding their expectations). Both aspects are discussed, including examples and lessons learned. The five years of development and implementation of a quality assurance program for decommissioning the WL site have led to a number of lessons learned. Many of these are also relevant to other decommissioning projects, in Canada and elsewhere: - Early discussions with the regulator can save time and effort later in the process; - An iterative process in developing documentation allows for steady improvements and input throughout the process; - Consistent 2-way communication with staff regarding the benefits of a quality program assists greatly in adoption of the philosophy and procedures; - Top-level management must lead in promoting quality; - Field trials of procedures ('beta testing') ensures they are easy to use as well as useful. Success in decommissioning the Whiteshell Laboratories depends on the successful implementation of a rigorous quality program. This will help to ensure both safety and efficiency of all activities on site, from planning through execution and reporting. The many aspects of maintaining this program will continue to occupy quality practitioners in AECL, reaping

  7. Planning for decommissioning power plants in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Komatsu, Junji (Research Association for Nuclear Facility Decommissioning, Tokaimura, Ibaraki (Japan))

    1993-02-01

    The first decommissioning of a commercial nuclear power plant in Japan is not expected before the early 2000s, but the technology and regulations needed are being developed now. Valuable technical experience is being gained from three current projects. These are the decommissioning of the Japan Reprocessing Test Facility, the Japan Power Demonstration Reactor and the nuclear ship Mutsu. Improving and commercialising the technology are seen as essential for the future to reduce occupational radiation exposure, the amount of waste and costs. International cooperation and information exchange are of increasing importance for developing technology and regulations. (U.K.).

  8. Cost Estimation for Research Reactor Decommissioning

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of this publication is to develop a costing methodology and a software tool in order to support cost estimation for research reactor decommissioning. The costing methodology is intended for the preliminary cost estimation stages for research reactor decommissioning with limited inventory data and other input data available. Existing experience in decommissioning costing is considered. As the basis for the cost calculation structure, the costing model uses the International Structure for Decommissioning Costing (ISDC) that is recommended by the IAEA, the Organisation for

  9. No small fry: Decommissioning research reactors

    International Nuclear Information System (INIS)

    To get a permit to build a research reactor, would-be operators need to submit an initial decommissioning plan for the eventual shutdown of their new facility. This, however, was not a requirement back in the 1950s, 60s and 70s when most research reactors that are now nearing the end of their working lives were built. The result: many unused reactors sit idle in the middle of university campuses, research parks and hospital compounds, because their operators lack the proper plans to decommission them

  10. Decontamination, decommissioning, and vendor advertorial issue, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  11. Nuclear power plants. Safe and efficient decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Huger, Helmut [TUEV SUED Energietechnik GmbH, Filderstadt (Germany). Div. of Radiation Protection, Waste Management and Decommissioning; Woodcock, Richard [TUEV SUED Nuclear Technologies, Warrington, Cheshire (United Kingdom). Environment and Radioactive Waste Management

    2016-02-15

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  12. The health risks of decommissioning nuclear facilities.

    Science.gov (United States)

    Dodic-Fikfak, M; Clapp, R; Kriebel, D

    1999-01-01

    The health risks facing workers involved in decommissioning nuclear facilities are a critical concern as the nuclear weapons complex and nuclear power plants begin to be dismantled. In addition to risks from exposure to radioactive materials, there are risks from other common industrial materials like crystalline silica dust and asbestos. We discuss these issues in the context of recent research on the risk of low-level ionizing radiation, the classification of crystalline silica as a carcinogen, and early experience with decommissioning nuclear facilities in the United States. Health and safety advocates will need to be vigilant to prevent worker exposure. PMID:17208791

  13. Optimization in the decommissioning of uranium tailings

    International Nuclear Information System (INIS)

    This report examines in detail the problem of choosing the optimal decommissioning approach for uranium and mill tailings sites. Various decision methods are discussed and evaluated, and their application in similar decision problems are summarized. This report includes, by means of a demonstration, a step by step guide of how a number of selected techniques can be applied to a decommissioning problem. The strengths and weaknesses of various methods are highlighted. A decision system approach is recommended for its flexibility and incorporation of many of the strengths found in other decision methods

  14. Decommissioning technology development for research reactors; establishment on the classification scheme of the decommissioning information and data

    Energy Technology Data Exchange (ETDEWEB)

    Ser, J. S.; Jang, Se Kyu; Kim, Young Do [Chungchong Institute of Regional Information System, Taejeon (Korea)

    2002-04-01

    The establishment of the decommissioning DB is the first thing in KOREA. It has never been decided the standardization in relation to the decommissioning DB all over the world and many countries has been constructed their decommissioning DB which serve their purpose. Owing to get the classification of the decommissioning information and data, it is used a prototyping design that is needed the DB construction as a basic data and applied to a nuclear facilities in the future. 10 refs. (Author)

  15. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    OpenAIRE

    Dragusin Mitica; Pavelescu Octavian Alexandru; Iorga Ioan

    2011-01-01

    The VVR-S Nuclear Research Reactor at the “Horia Hulubei” National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper.

  16. Decommissioning of denison and Stanrock tailings management areas

    International Nuclear Information System (INIS)

    The Denison Mines Limited uranium mining and milling facility in Elliot Lake ceased operations in April of 1992. Since that time major site decommissioning projects were completed. These projects involved demolition of site facilities and acid mine drainage (AMD) mitigation in the three tailings management areas known as TMA-1, TMA-2 at Denison and TMA-3 at Stanrock. The work on TMA-1 and TMA-2 was generally completed in late 1996 and the work at TMA-3 was essentially completed in late 1998. The use of water covers was chosen as the best technology for long term tailings stabilization for TMA-1 and -2. In the gently sloped and partially flooded basin of TMA-1, 1.83 million cubic metres of tailings were dredged and relocated to deeper areas of the basin to establish 0.9 metre water cover (also termed 'dredge the wedge'). Perimeter dams were regraded to add additional factors of safety and an upstream seepage reduction berm and a downstream toe stabilization berm were constructed at, the western most dam, Dam 10. (author)

  17. The decommissioning and redevelopment of NECSA site

    International Nuclear Information System (INIS)

    Full text: The South African nuclear programme started in 1948 and was focussed on research and development in the nuclear field. In the early 70s a uranium conversion plant and a uranium enrichment plant were constructed on the NECSA site. The enriched uranium was used for military purposes, as fuel for the research reactor SAFARI-1 at Necsa. A semi-commercial uranium enrichment plant and a fuel manufacturing plant were commissioned in the 80's to supply fuel for the nuclear power plant at Koeberg near Cape Town. Currently the research reactor is utilized for the generation of radioactive isotopes for industrial and medical applications. Various other research projects were initiated and buildings constructed on the Necsa site to accommodate the different projects. The uranium conversion and enrichment projects were terminated in the early 90's, and many buildings on the Necsa site became redundant. An initial decommissioning strategy was to return the Necsa site to green fields. This endpoint of decommissioning has changed dramatically with the nuclear renaissance to include redevelopment and reuse options. In the case of a multi-facility nuclear site, such as the Necsa site, it is vital to develop a total site redevelopment plan rather than to decommission and allocate individual facilities for isolated reuse demands. A holistic approach should be assured by considering current and projected future redevelopment demands in the development of a redevelopment and reuse plan. It is important not to allow the redevelopment and reuse of a single facility on a multi-facility site based on short- term financial gain. With the recent increase in demand for nuclear facilities the redevelopment and reuse of nuclear facilities for non-nuclear applications should generally not be considered due to the inherent advantages associated with an existing licensed site. The initial decommissioning plan did not consider the Necsa site as a whole. Decommissioning costs, and the

  18. Needs for European decommissioning academy (EDA)

    International Nuclear Information System (INIS)

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year. Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning, as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the over-bridging this gap. The main goal is - from about 74% of nuclearized experts (graduated at different technical Universities and increased their nuclear knowledge and skills mostly via on-job training and often in the area of NPP operation) to create nuclear experts for decommissioning via our post-gradual coursed organized in two semester study at our Academy, which will include the lessons, practical exercises in our laboratories, on-site training at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 3 days technical tour to JAVYS (Slovakia), UJV Rez (Czech Rep.) and PURAM (Hungary), respectively. Beside the exams in selected topics (courses), the final thesis written under supervision of recognized experts will be the precondition for graduation and certification of the participants. For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe. The growing decommissioning market creates a potential for new activities, with highly skilled jobs in an innovative field, involving high-level technologies. A clear global positioning of the EU will stimulate the export of know-how to

  19. Environmental restoration and waste management program decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Oak Ridge National Laboratory (ORNL), Robotics and Process Systems Division (RPSD), Telerobotic Systems Section (TSS) is responsible for performing a Technology Demonstration for the Decontamination and Decommissioning (D and D) Project in the Environmental Restoration and Waste Management (ER and WM) Program of the US Department of Energy (DOE). This technology demonstration is scheduled for early October of 1992 at the ORNL RPSD. The demonstration will use robotic and telerobotic technology applied to D and D tasks in hot cell environments. The goals of D and D robotics and remote systems technology development are to provide technologies which improve the quality, safety, and cost effectiveness of future D and D projects. This is accomplished by removing humans from hazardous conditions, increasing the speed, reliability, and performance associated with typical D and D tasks; and minimizing the waste stream. Four operations are basic to the D and D needs surveying, decontamination, dismantling, and material disposition. The technology demonstration at ORNL TSS will demonstrate that a pipe section can be surveyed and dismantled in an in situ environment with the use of robotic and telerobotic technology at ORNL facilities

  20. Validation of Decommissioning Engineering System Application against KRR-2

    International Nuclear Information System (INIS)

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES

  1. Status of industry standards for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    This paper discusses how several professional societies are preparing industry standards on nuclear facility decommissioning: ASTM (American Society for Testing and Materials), Nuclear Technology Committee, Decommissioning Subcommittee, E10.03; ASME (American Society of Mechanical Engineers), Nuclear Quality Assurance (NQA) Committee's Working Group on Decommissioning and the Reactor Services Committee's Subcommittee on Decommissioning; and Health Physics Society Standards Committee (HPSSC) working under the auspices of the American National Standards Institute (ANSI). According to the author, the standards of these diverse groups mesh to form a cohesive body of guidance for planning a nuclear facility decommissioning

  2. Decontamination and decommissioning focus area. Technology summary

    International Nuclear Information System (INIS)

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities

  3. Virtual reality technology and nuclear decommissioning

    International Nuclear Information System (INIS)

    During past years, an important activity at the Halden VR Centre (HVRC), Institute for Energy Technology (IFE) in Halden has been the development of virtual reality (VR) software for use in the decommissioning of nuclear facilities. It is hoped that use of VR technology in the planning process may prove beneficial both with regard to minimizing workers' radiation exposure, as well as in helping to achieve the efficient use of human resources. VR can also be a valuable tool in the dismantling phase. In addition to this, VR provides the decommissioning project team with an effective medium in presentations to the public, as well as for communicating with relevant engineers and licensing authorities. The most extensive IFE VR decommissioning project is at present the VRdose project, conducted in co-operation with the Japan Nuclear Cycle Development Institute (JNC). VRdose will be used in the decommissioning of one of JNC's reactors, the Fugen Nuclear Power Station.The paper describes the present and planned versions of the VRdose system, but also briefly describes other related activities at HVRC. (author)

  4. Decommissioning technology development for research reactors

    International Nuclear Information System (INIS)

    Although it is expected that the decommissioning of a nuclear power plant will happen since 2020, the need of partial decommissioning and decontamination for periodic inspection and life extension has been on an increasing trend and domestic market has gradually been extended. Therefore, in this project the decommissioning DB system on the KRR-1 and 2 was developed as establishing the information classification system of the research reactor dismantling and the structural design and optimization of the decommissioning DB system. Also in order to secure the reliability and safety about the dismantling process, the main dismantling simulation technology that can verify the dismantling process before their real dismantling work was developed. And also the underwater cutting equipment was developed to remove these stainless steel parts highly activated from the RSR. First, the its key technologies were developed and then the design, making, and capability analysis were performed. Finally the actual proof was achieved for applying the dismantling site. an automatic surface contamination measuring equipment was developed in order to get the sample automatically and measure the radiation/radioactivity

  5. Decontamination and decommissioning focus area. Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  6. Spent fuel disposal impact on plant decommissioning

    International Nuclear Information System (INIS)

    Regardless of the decommissioning option selected (DECON, SAFSTOR, or ENTOMB), a 10 CFR 50 license cannot be terminated until the spent fuel is either removed from the site or stored in a separately 10 CFR 72 licensed Independent Spent Fuel Storage Installation (ISFSI). Humboldt Bay is an example of a plant which has selected the SAFSTOR option. Its spent fuel is currently in wet storage in the plant's spent fuel pool. When it completes its dormant period and proceeds with dismantlement, it will have to dispose of its fuel or license an ISFSI. Shoreham is an example of a plant which has selected the DECON option. Fuel disposal is currently critical path for license termination. In the event an ISFSI is proposed to resolve the spent fuel removal issue, whether wet or dry, utilities need to properly determine the installation, maintenance, and decommissioning costs for such a facility. In considering alternatives for spent fuel removal, it is important for a utility to properly account for ISFSI decommissioning costs. A brief discussion is presented on one method for estimating ISFSI decommissioning costs

  7. Sodium Reactor Experiment decommissioning. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  8. Decontamination and decommissioning of Shippingport commercial reactor

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, J. [Dept. of Energy, Pittsburgh, PA (United States)

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  9. Financing strategies for nuclear power decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1980-07-01

    The report analyzes several alternatives for financing the decommissioning of nuclear power plants from the point of view of assurance, cost, equity, and other criteria. Sensitivity analyses are performed on several important variables and possible impacts on representative companies' rates are discussed and illustrated.

  10. Consideration of ISDC for Decommissioning Cost Estimation

    International Nuclear Information System (INIS)

    In 2009, they decided to update the Yellow Book, and began to update it by analyzing user experiences. They found that several countries have adopted the proposed standardized cost structure for the production of cost estimates directly or for mapping national estimates onto a common structure. They also made conclusions that more detailed advice should be given on the use of the standardized structure and on the definition of cost items to avoid ambiguity. The revised cost structure, to be known as the International Structure for Decommissioning Costing (ISDC), was published in 2012. The standardized cost structure developed in the report may be used for estimating the costs of decommissioning of any type of nuclear facility. We analyzed this standardized cost structure (ISDC) and applied it to DECOMMIS which was developed by KAERI. The appropriate estimation system for domestic application was examined by comparing the estimation results. KAERI made WBS code in DECOMMIS and data obtained during decommissioning work of KRR2 and UCP. Recently the IAEA updated the decommissioning cost items and its structure by ISDC. The cost estimation items of the DECOMMIS were applied to ISDC structure. For applying, the ISDC code compared with WBS code of DECOMMIS as on text of the activity name from daily report basis. The mapping result of the ISDC items to WBS code of the DECOMMIS is much different. AS results of this study that it need the corresponding cost category which classified in accordance with the national standard price estimates

  11. The decommissioning of the water boiler reactor

    International Nuclear Information System (INIS)

    Following completion of service, the Water Boiler Reactor (WBR) has been decommissioned by the Institute of Nuclear Energy Research (INER) under the Atomic Energy Council's (AEC) regulation. The WBR is a light water moderated and graphite reflected research reactor with peak thermal power of 100 kW. The unique feature of the WBR is that it is fueled with uranyl sulfate (UO2SO4) which is in liquid form. Since there is another research reactor owned by I7NER of megawatt scale in the planning stages for decommissioning, the WBR project was conducted with great care to accumulate experience. Extensive planning by INER and step-by-step regulative activities by AEC were followed regardless of the structural simplicity of the WBR. Valuable information was gathered in the task and will be useful for preparing future decommissioning needs. The major work in the WBR decommissioning project was finished within six months and the accumulated dose received during the work was 1 9.63mSv. (author)

  12. Decommissioning of nuclear facilities. Feasibility, needs and costs

    International Nuclear Information System (INIS)

    Reactor decommissioning activities generally are considered to begin after operations have ceased and the fuel has been removed from the reactor, although in some countries the activities may be started while the fuel is still at the reactor site. The three principal alternatives for decommissioning are described. The factors to be considered in selecting the decommissioning strategy, i.e. a stage or a combination of stages that comprise the total decommissioning programme, are reviewed. One presents a discussion of the feasibility of decommissioning techniques available for use on the larger reactors and fuel cycle facilities. The numbers and types of facilities to be decommissioned and the resultant waste volumes generated for disposal will then be projected. Finally, the costs of decommissioning these facilities, the effect of these costs on electricity generating costs, and alternative methods of financing decommissioning are discussed. The discussion of decommissioning draws on various countries' studies and experience in this area. Specific details about current activities and policies in NEA Member Countries are given in the short country specific Annexes. The nuclear facilities that are addressed in this study include reactors, fuel fabrication facilities, reprocessing facilities, associated radioactive waste storage facilities, enrichment facilities and other directly related fuel cycle support facilities. The present study focuses on the technical feasibility, needs, and costs of decommissioning the larger commercial facilities in the OECD member countries that are coming into service up to the year 2000. It is intended to inform the public and to assist in planning for the decommissioning of these facilities

  13. Development of computer program for estimating decommissioning cost - 59037

    International Nuclear Information System (INIS)

    The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning. To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co. Ltd, developed a decommissioning cost estimating computer program called 'DeCAT-Pro', which is Decommission-ing Cost Assessment Tool - Professional. (Hereinafter called 'DeCAT') This program allows users to easily assess the decommissioning cost with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the conditions of radwaste disposal and transportation automatically. (authors)

  14. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  15. In situ dehydration of yugawaralite

    DEFF Research Database (Denmark)

    Artioli, G.; Ståhl, Kenny; Cruciani, G.;

    2001-01-01

    The structural response of the natural zeolite yugawaralite (CaAl2Si6O16. 4H(2)O) upon thermally induced dehydration has been studied by Rietveld analysis of temperature-resolved powder diffraction data collected in situ in the temperature range 315-791 K using synchrotron radiation. The room...... progressively disappearing as the dehydration proceeds. The yugawaralite structure reacts to the release of water molecules with small changes in the Ca-O bond distances and minor distortions of the tetrahedral framework up to about 695 K. Above this temperature the Ca coordination falls below 7 (four framework...

  16. In situ bypass og diabetes

    DEFF Research Database (Denmark)

    Jensen, Leif Panduro; Schroeder, T V; Lorentzen, J E

    1993-01-01

    From 1986 through to 1990 a total of 483 in situ bypass procedures were performed in 444 patients. Preoperative risk-factors were equally distributed among diabetic (DM) and non-diabetic (NDM) patients, except for smoking habits (DM:48%, NDM:64%, p = 0.002) and cardiac disease (DM:45%, NDM:29%, p...... decreased survival rate was found in diabetics (p bypass technique very useful in the treatment of critical ischaemia of the lower limb in diabetic patients. The overall results in diabetic patients, whether insulin-dependent or not, were equal to those in non...

  17. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Arabic Edition)

    International Nuclear Information System (INIS)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  18. Study on decommissioning (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    This project consists of researches for 1. review plan for decommissioning plan, 2. specific method to confirm completion of decommissioning and 3. dismantling waste management method. Dismantling experiences and knowledge of domestic and international trends of decommissioning were examined and the confirmation items for authorization of decommissioning plan were extracted. The estimation of site contamination during dismantling period was performed by use of radioactive material release data of the Tokai NPP. Domestic and some foreign countries knowledge of experience of decommissioning completion confirmation was examined. This knowledge was reflected in NISA's Committee Report 'Basic concept to confirm completion of decommissioning (Interim report) - Main issues and direction of future investigation-'. Three concrete cores were sampled in biological shield of the Tokai NPP to establish method of waste package verification based on radiation level evaluation in decommissioning and dismantling waste management method. (author)

  19. Roadmap for implementation of light water reactor decommissioning

    International Nuclear Information System (INIS)

    While decommissioning of Tokai-mura reactor and JATR reactor has already started in Japan, Tsuruga reactor is announced shutdown in 2010 as the first decommissioning of commercial light water reactor (LWR). In 2030s or may be more earlier due to economic reasons, decommissioning of LWRs will take place in succession. Since rational decommissioning needs operating data of individual plants, ample time should be allowed for planning the reactor decommissioning. Committee of Nuclear Power Engineering Cooperation (NUPEC) had identified relevant issues to implement LWR decommissioning and established roadmaps showing fundamental approaches to solve seventeen items categorized in seven areas as action items. Harmonization of policy, regulations and technology development as a whole and reflection of accumulated lessons learned from overseas decommissioning experiences needed further study. (T. Tanaka)

  20. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  1. Decommissioning of TRIGA Mark II type reactor

    International Nuclear Information System (INIS)

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor

  2. Decommissioning of TRIGA Mark II type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Dooseong; Jeong, Gyeonghwan; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor

  3. SOGIN Decommissioning strategy and funding (Italy)

    International Nuclear Information System (INIS)

    Statement: In Italy, as it is well known, there are no more operational NPPs. The four existing nuclear plants are definitely shutdown and ready for decommissioning. Considerations on decommissioning funding system have to take into account this particular situation. Strategy for decommissioning: New inputs given to SOGIN by the Italian Government are: conditioning all radioactive waste existing on the NPPs within the year 2010, release all nuclear sites - free of radiological constraints - by 2020. The last task is conditioned by availability of the national waste repository by the year 2009. Strategy for decommissioning: Key issue is prompt dismantling considering No more nuclear activities in Italy and Progressive loss of competencies. Previously Existing funds: Before plant shutdown, ENEL has cumulated provisions for decommissioning, even in absence of a clear regulatory framework. These provisions were not sufficient for decommissioning, considering the early closure of the plants. An additional fund was granted to ENEL by the government, in the form of a 'credit' to be paid by the 'electric system' (CCSE). This fund (provisions + credit) was considered sufficient by ENEL for a decommissioning with Safe Store strategy (fund = discounted foreseen costs). The total fund (provisions + credit) was assigned to Sogin at the incorporation date. The amount, money 1999, was about 800 M euros. Considering the new context: new strategy (Prompt Dismantling with site release by 2020), Sogin constitution (societal costs), new economic conditions. The fund was not considered sufficient for all Sogin tasks. This conclusion was agreed upon also by the independent 'Authority for electric energy and gas'. A new regulatory framework was therefore defined. Regulatory aspects: The Legislative Decree 79/99 has stated that costs for the decommissioning of NPP, fuel cycle back end and related activities should be considered as stranded costs for the general electric system. The same

  4. NMSS handbook for decommissioning fuel cycle and materials licensees

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ''Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.'' The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC's SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook

  5. NMSS handbook for decommissioning fuel cycle and materials licensees

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  6. 30 CFR 250.1753 - After I decommission a pipeline, what information must I submit?

    Science.gov (United States)

    2010-07-01

    ... Decommissioning Activities Pipeline Decommissioning § 250.1753 After I decommission a pipeline, what information must I submit? Within 30 days after you decommission a pipeline, you must submit a written report to... 30 Mineral Resources 2 2010-07-01 2010-07-01 false After I decommission a pipeline,...

  7. In situ trace element microanalysis

    Science.gov (United States)

    Burnett, D. S.; Woolum, D. S.

    1983-01-01

    The use of particle-track-radiography and X-ray- fluorescence techniques in the in situ measurement of trace (less than 1000 ppm) elements in single mineral phases of polished sections is surveyed, and examples of their application to ordinary, carbonaceous and enstatite chondrites are provided. Radiographic methods surveyed include fission-track radiography (for U, Th, and Pu-244), alpha radiography using nuclear reactions (for Li and B), alpha autoradiography (for Bi and Pb), and beta autoradiography (for several elements in synthetic or biological samples). Two X-ray-fluorescence methods are compared: (1) photon-induced X-ray emission (PIXE), and (2) the potential use of synchrotron radiation. The latter is shown to allow much greater sensitivity than current PIXE technology and a much broader range of elements than particle-track radiography: the ppm analysis of 10-micron grains for all elements heavier than Na. These advantages are seen as balancing the high cost of accelerator use.

  8. In situ treatability test plan

    International Nuclear Information System (INIS)

    This document describes the plans for the in situ treatment zone (ISTZ) treatability test for groundwater contaminated with strontium-90. The treatability test is to be conducted at the Hanford Site in Richland, Washington, in a portion of the 100-N Area adjacent to the Columbia River referred to as N-Springs. The purpose of the treatability test is to evaluate the effectiveness of an innovative technology to prevent the discharge of strontium-90 contaminated groundwater into the Columbia River. The ISTZ is a passive technology that consists of placing a treatment agent in the path of the groundwater. The treatment agent must restrict target radioactive contaminants and provide time for the contaminant to decay to acceptable levels. The permeability of the treatment zone must be greater than or equal to that of the surrounding sediments to ensure that the contaminated groundwater flows through the treatment zone agent and not around the agent

  9. DOE In Situ Remediation Integrated Program

    International Nuclear Information System (INIS)

    The In Situ Remediation Integrated Program (ISRP) supports and manages a balanced portfolio of applied research and development activities in support of DOE environmental restoration and waste management needs. ISRP technologies are being developed in four areas: containment, chemical and physical treatment, in situ bioremediation, and in situ manipulation (including electrokinetics). the focus of containment is to provide mechanisms to stop contaminant migration through the subsurface. In situ bioremediation and chemical and physical treatment both aim to destroy or eliminate contaminants in groundwater and soils. In situ manipulation (ISM) provides mechanisms to access contaminants or introduce treatment agents into the soil, and includes other technologies necessary to support the implementation of ISR methods. Descriptions of each major program area are provided to set the technical context of the ISM subprogram. Typical ISM needs for major areas of in situ remediation research and development are identified

  10. In situ measurements of neutron multiplying systems

    International Nuclear Information System (INIS)

    Historical and recent examples of the application of in situ measurements to provide knowledge for specific operations and general criticality safety guidance are reviewed. The importance of the American National Standard, Safety in Conducting Subcritical Neutron-Multiplication Measurements In Situ, ANSI/ANS-8.6, 1988 is discussed. Examples of possible future applications of in-situ measurements are provided. 4 refs., 4 figs

  11. Training for teamwork through in situ simulations

    OpenAIRE

    Sorensen, Asta; Poehlman, Jon; Bollenbacher, John; Riggan, Scott; Davis, Stan; Miller, Kristi; Ivester, Thomas; Kahwati, Leila

    2015-01-01

    In situ simulations allow healthcare teams to practice teamwork and communication as well as clinical management skills in a team's usual work setting with typically available resources and equipment. The purpose of this video is to demonstrate how to plan and conduct in situ simulation training sessions, with particular emphasis on how such training can be used to improve communication and teamwork. The video features an in situ simulation conducted at a labour and delivery unit in response ...

  12. A survey of strippable and tie-down coatings for use in the decommissioning of alpha-active facilities

    International Nuclear Information System (INIS)

    The paper concerns temporary coatings for use in decommissioning operations of alpha-active facilities. The various temporary coating options are described with respect to: decontamination by removal of a previously applied protective coating, and the in-situ application of a coating for tie-down or decontamination duties. The specifications for coating systems to be used in active areas are defined in general terms. A survey of currently available temporary coating material is given, as well as the suitability of commercially available coating systems. (U.K.)

  13. Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    International Nuclear Information System (INIS)

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation

  14. Decommissioning of the Tokamak Fusion Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

  15. Decommissioning of the Tokamak Fusion Test Reactor

    International Nuclear Information System (INIS)

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D and D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D and D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D and D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget

  16. Four Models of In Situ Simulation

    DEFF Research Database (Denmark)

    Musaeus, Peter; Krogh, Kristian; Paltved, Charlotte

    2014-01-01

    that there are four fruitful approaches to in situ simulation: (1) In situ simulation informed by reported critical incidents and adverse events from emergency departments (ED) in which team training is about to be conducted to write scenarios. (2) In situ simulation through ethnographic studies at the ED. (3) Using...... will be illustrated with reference to an empirical pilot project, which has a triple strategy: 1) Literature study 2) Patient safety data analysis 3) Observational study on interprofessional emergency teams, and 4) In situ simulation intervention study with evaluation of interprofessional team training. Perspective...

  17. Decommissioning a tritium glove-box facility

    International Nuclear Information System (INIS)

    A large glove-box facility for handling reactive metal tritides was decommissioned. Major sections of the glove box were decontaminated and disassembled for reuse at another tritium facility. To achieve the desired results, decontamnation required repeated washing, first with organic liquids, then with water and detergents. Worker protection was provided by simple ventilation combined with careful monitoring of the work areas and employees. Several innovative techniques are described

  18. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Since 1973, when the IAEA first introduced the subject of decontamination and decommissioning into its programme, twelve Agency reports reflecting the needs of the Member States on these topics have been published. These reports summarize the work done by various Technical Committees, Advisory Groups, and International Symposia. While the basic technology to accomplish decontamination and decommissioning (D and D) is fairly well developed, the Agency feels that a more rapid exchange of information and co-ordination of work are required to foster technology, reduce duplication of effort, and provide useful results for Member States planning D and D activities. Although the Agency's limited financial resources do not make possible direct support of every research work in this field, the IAEA Co-ordinated Research Programme (CRP) creates a forum for outstanding workers from different Member States brought into closer contact with one another to provide for more effective interaction and, perhaps subsequently, closer collaboration. The first IAEA Co-ordinated Research Programme (CRP) on decontamination and decommissioning was initiated in 1984. Nineteen experts from 11 Member States and two international organizations (CEC, OECD/NEA) took part in the three Research Co-ordination Meetings (RCM) during 1984-87. The final RCM took place in Pittsburgh, USA, in conjunction with the 1987 International Decommissioning Symposium (sponsored by the US DOE and organized in co-operation with the IAEA and OECD/NEA). The present document summarizes the salient features and achievements of the co-ordinated research work performed during the 1984-87 programme period. The document consists of two parts: Part 1, Summary of the three research co-ordination meetings and Part 2, Final submissions by participants on the research work performed during 1984-1987. A separate abstract was prepared for each of the 7 reports presented. Refs, figs and tabs

  19. Decommissioning a tritium glove-box facility

    Energy Technology Data Exchange (ETDEWEB)

    Folkers, C.L.; Homann, S.G.; Nicolosi, A.S.; Hanel, S.L.; King, W.C.

    1979-08-08

    A large glove-box facility for handling reactive metal tritides was decommissioned. Major sections of the glove box were decontaminated and disassembled for reuse at another tritium facility. To achieve the desired results, decontamnation required repeated washing, first with organic liquids, then with water and detergents. Worker protection was provided by simple ventilation combined with careful monitoring of the work areas and employees. Several innovative techniques are described.

  20. The U.S. Nuclear Regulatory Commission's decommissioning process

    International Nuclear Information System (INIS)

    The term 'Decommission' is defined in the U.S.. Nuclear Regulatory Commission's (USNRC's) regulations at 10 CFR 20.1003 as to remove a facility or site safely from service and reduce residual radioactivity to a level that permits 1) release of the property for unrestricted use and termination of the license; or, 2) release of the property under restricted conditions and the termination of the license. USNRC's decommissioning program encompasses the decommissioning of all NRC licensed facilities, ranging from routine license terminations for sealed source users, to the oversight of complex sites and those on the Site Decommissioning Management Plan (SDMP), as well as power and non-power reactors. This paper describes the USNRC's decommissioning process for materials and reactor facilities and presents an overview of USNRC's decommissioning program activities. (author)

  1. The regulatory challenges of decommissioning nuclear reactors

    International Nuclear Information System (INIS)

    Each nuclear power plant, fuel cycle facility and nuclear research and test facility that is operating today will eventually reach the end of its useful life and cease operation. During the period of its decommissioning, it is important to properly manage the health and environmental hazards and physical protection measures of the shutdown facility in order to protect the health and safety of the public and workers and to safeguard any nuclear materials. In this regard, the nuclear safety regulatory body is responsible for independently assuring that decommissioning activities are conducted safely, that radioactive materials and spent nuclear fuel are disposed of properly and that the site is in an acceptable end state. The purpose of this report is to describe the broad range of safety, environmental, organisational, human factors and public policy issues that may arise during the decommissioning of nuclear reactors and that the regulatory body should be prepared to deal with in the framework of its national regulatory system. The intended audience is primarily nuclear regulators, although the information and ideas may also be of interest to government authorities, environmental regulators, nuclear operating organisations, technical expert organisations and the general public. (author)

  2. New technologies in decommissioning and remediation

    International Nuclear Information System (INIS)

    New and emerging technologies are making decommissioning and remediation more cost effective, faster and safer. From planning to execution and control, the use of new technologies is on the rise. Before starting decommissioning or environmental remediation, experts need to plan each step of the process, and to do that, they first need a clear idea of the characteristics of the structure and the level of radiation that they can expect to encounter. While characterization for planning purposes can be done using manual approaches, such as drawing up blueprints and taking measurements and photos, laser scanning technologies are now allowing decommissioning teams to more quickly and accurately map out the physical characteristics of a facility’s structures, systems and components. This is complemented by highly sensitive measurements taken with high-tech devices, such as remotely operated gamma cameras that can precisely and efficiently measure the radiological characteristics of the facility, including the amount and type of radiation. Similar measurements are needed once the contamination has been removed, to verify that any residual radiation levels are indeed insignificant

  3. Decommissioning of the Salaspils Research Reactor

    Directory of Open Access Journals (Sweden)

    Abramenkovs Andris

    2011-01-01

    Full Text Available In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning and dismantling plan was carried out from 2003-2004, resulting in a change of the primary goal of decommissioning. Collecting and conditioning of “historical” radioactive wastes from different storages outside and inside the reactor hall became the primary goal. All radioactive materials (more than 96 tons were conditioned for disposal in concrete containers at the radioactive wastes depository “Radons” at the Baldone site. Protective and radiation measurement equipment of the personnel was upgraded significantly. All non-radioactive equipment and materials outside the reactor buildings were released for clearance and dismantled for reuse or conventional disposal. Contaminated materials from the reactor hall were collected and removed for clearance measurements on a weekly basis.

  4. Initial decommissioning planning for the Budapest research reactor

    OpenAIRE

    Toth Gabor

    2011-01-01

    The Budapest Research Reactor is the first nuclear research facility in Hungary. The reactor is to remain in operation for at least another 13 years. At the same time, the development of a decommissioning plan is a mandatory requirement under national legislation. The present paper describes the current status of decommissioning planning which is aimed at a timely preparation for the forthcoming decommissioning of the reactor.

  5. Initial decommissioning planning for the Budapest research reactor

    Directory of Open Access Journals (Sweden)

    Toth Gabor

    2011-01-01

    Full Text Available The Budapest Research Reactor is the first nuclear research facility in Hungary. The reactor is to remain in operation for at least another 13 years. At the same time, the development of a decommissioning plan is a mandatory requirement under national legislation. The present paper describes the current status of decommissioning planning which is aimed at a timely preparation for the forthcoming decommissioning of the reactor.

  6. Training practices to support decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as

  7. Unrestricted re-use of decommissioned nuclear laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cornelissen, R.; Noynaert, L.; Harnie, S.; Marien, J.

    1996-09-18

    A decommissioning strategy was developed by the Belgian Nuclear Research Centre SCK/CEN. In this strategy decommissioning works are limited to the radioactive parts of the nuclear installation. After obtaining an attestation for unrestricted reuse of the building after removal of all radioactivity, the building can be used for new industrial purposes outside the nuclear field. The decommissioning activities according to this strategy have been applied in four buildings. The results are described.

  8. Conclusions and theses relating to the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Most of the problems encountered in decommissioning are due to deficiencies on the side of the laws. Items of controversy revealed at the meeting are: -content covered by the term decommissioning; - definition of decommissioning stages and their hierarchy in schedule; - subject matter of decommissioning; -interfaces between operation and decommissioning processes; - substantive requirements to be met; - formal requirements to be met. The meaning of the term 'nuclear installation' used in paragraph 7 sub-sec. (3), 1st sentence Atomic Energy Act corresponds to the meaning of the term used in paragraph 7 sub-sec. 1 Atomic Energy Act. However, the licensee is free to proceed with the decommissioning of individual components of an installation that can be disconnected from the safety programme of decommissioning activities. Those measures in the post-shutdown phase under regulatory control under the operating licence or the surveillance programme do not require to be licensed anew. All other measures require a licence for decommissioning ('as far as'). Decommissioning cannot be 'directed' by orders under the surveillance programme. The (unlawful) nuclear power phaseout cannot be imposed on the basis of paragraph 7 sub-sec. 3 Atomic Energy Act. (orig./HSCH)

  9. Funding nuclear-power-plant decommissioning. Final report

    International Nuclear Information System (INIS)

    The report is organized according to the steps that one might go through when analyzing funding of decommissioning costs. The first step in analyzing decommissioning costs might be to review the present regulatory framework within which decommissioning cost decisions must be made. A description is presented of the present NRC regulations that address the decommissioning of a nuclear power plant. A description is also presented of recent public utility commission activities concerning funding the costs of decommissioning. Possible future trends in NRC regulation are also discussed. The estimation of decommmissioning costs is analyzed. A description of each of the possible decommissoining options is presented. The options of decommissioning include immediate dismantlement, various types of safe storage, and entombment. A discussion is presented of cost estimations for each decommissioning option for nuclear units containing pressurized water reactors and boiling water reactors. A description is included of the various methods of collecting funds for decommissioning as well as a discussion of their possible regulatory treatment. Material is presented which will provide the reader with background information that might assist state utility commissioners or their staffs in choosing or evaluating one of the financial mechanisms for covering decommissioning costs

  10. Decommissioning of fuel cycle facilities in South Africa

    International Nuclear Information System (INIS)

    Experience gained in South Africa on the decommissioning of uranium conversion, enrichment and fuel fabrication facilities is briefly summarized with emphasis on the lessons learned. The South African Nuclear Energy Corporation (Necsa) has consolidated its nuclear decommissioning and waste management activities at Pelindaba and introduced a comprehensive, all-embracing nuclear liability management approach. The paper describes the experience gained on various aspects of decommissioning and waste management including the social impacts of the decommissioning and waste related activities during the decade from 1995 to 2005. Certain technological difficulties arose during this period and the approaches adopted to resolve these difficulties are also addressed. (author)

  11. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    International Nuclear Information System (INIS)

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

  12. Decommissioning of nuclear facilities in Korea

    International Nuclear Information System (INIS)

    In 1996, it was concluded that the first Korea research reactor (KRR-1) and the second Korea research reactor (KRR-2) would be shut down and decommissioned. The main reason for the decommissioning was that the facilities became old and has become surrounded by the urbanised community. And many difficulties, including the higher cost, were faced according to the enhanced regulations. Another reason was the introduction of a new research reactor 'HANARO' in 1995. A project to decommission the reactors was launched on January of 1997 with a goal of release of the site and buildings for unrestricted use by 2008. All the radioactive wastes generated are to be transported to the national repository, planned by the Korea Hydro and Nuclear Power Company (KHNP), and the final evaluation of the residual radioactivity will be made before the clearance of the site. As a first step of the project, a decommissioning plan, including the assessment of the environmental impact and the quality assurance program, was prepared and submitted to the government in 1998. It was approved, after its safety evaluation, by the Korea Institute of Nuclear Safety (KINS) in November of 2000. After some preparative works such as documentation of procedures, the decontamination and dismantling works for the laboratories and hot cells of KRR-2 were started in September, 2001 and finished in December, 2002. The spent fuels that had been generated from the reactors were transferred to the United States in 1998 and no spent fuel remained at the site. All the liquid waste, both operational and decommissioning, was very low in its radioactivity and was treated in a natural evaporation facility of 200 m3/year capacity, developed by KAERI. Especially the laundry waste was treated in a membrane filtering unit for the removal of surfactants before being introduced to the natural evaporator. The solid wastes were segregated and packed in the container of 4 m3, designed according to the ISO-1496, and also in

  13. In situ vitrification: A review

    International Nuclear Information System (INIS)

    The in situ vitrification process (ISV) converts contaminated soils and sludges to a glass and crystalline product. The process appears to be ideally suited for on site treatment of both wet and dry wastes. Basically, the system requires four molybdenum electrodes, an electrical power system for vitrifying the soil, a hood to trap gaseous effluents, an off-gas treatment system, an off-gas cooling system, and a process control station. Mounted in three transportable trailers, the ISV process can be moved from site to site. The process has the potential for treating contaminated soils at most 13 m deep. The ISV project has won a number of outstanding achievement awards. The process has also been patented with exclusive worldwide rights being granted to Battelle Memorial Institute for nonradioactive applications. While federal applications still belong to the Department of Energy, Battelle transferred the rights of ISV for non-federal government, chemical hazardous wastes to a separate corporation in 1989 called Geosafe. This report gives a review of the process including current operational behavior and applications

  14. Enhanced in situ aerobic bioremediation

    Energy Technology Data Exchange (ETDEWEB)

    Sharfe, K. [CleanEARTH Solutions Ltd., Concord, ON (Canada)

    2007-07-01

    An enhanced in situ aerobic bioremediation process was described. The process used microbe supporting emulsifications to enhance bioavailability as well as to attenuate microbe competition and boost microbial production. Microbes were added prior to application and rapidly initiated bioremediation once applied to impacted areas. The microbe supporting emulsifiers were metabolically active. The study showed that exposed surface areas increased as hydrocarbon masses were divided, which in turn increased the water/substrate interface where microbial action occurred. Nutrients were used to ensure that crowding and waste accumulation were attenuated in order to ensure that the speed of growth and reproduction progressed exponentially. Water-carrying bacteria, enzymes and nutrients were adsorbed to the soil's particle surface and then diffused between particles. The sequestered hydrocarbons were then emulsified and removed in order to be bioremediated. It was concluded that biological catalysts were used to increase microbial activity and to trigger anabolic responses in microbes. Details of a biocatalyst laboratory solution analysis were also included. tabs., figs.

  15. Chemically enhanced in situ recovery

    Energy Technology Data Exchange (ETDEWEB)

    Sale, T. [CH2M Hill, Denver, CO (United States); Pitts, M.; Wyatt, K. [Surtek, Inc., Golden, CO (United States)] [and others

    1996-08-01

    Chemically enhanced recovery is a promising alternative to current technologies for management of subsurface releases of organic liquids. Through the inclusion of surfactants, solvents, polymers, and/or alkaline agents to a waterflood, the transport of targeted organic compounds can be increased and rates of recovery enhanced. By far, the vast majority of work done in the field of chemically enhanced recovery has been at a laboratory scale. The following text focuses on chemically enhanced recovery from a field application perspective with emphasis given to chlorinated solvents in a low permeability setting. While chlorinated solvents are emphasized, issues discussed are also relevant to organic liquids less dense than water such as petroleum products. Topics reviewed include: (1) Description of technology; (2) General technology considerations; (3) Low permeability media considerations; (4) Cost and reliability considerations; (5) Commercial availability; and (6) Case histories. Through this paper an appreciation is developed of both the potential and limitations of chemically enhanced recovery. Excluded from the scope of this paper is the in situ destruction of organic compounds through processes such as chemical or biological oxidation, chemically enhanced recovery of inorganic compounds, and ex situ soil treatment processes. 11 refs., 2 figs., 1 tab.

  16. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    Directory of Open Access Journals (Sweden)

    Dragusin Mitica

    2011-01-01

    Full Text Available The VVR-S Nuclear Research Reactor at the “Horia Hulubei” National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper.

  17. Decommissioning of nuclear power plants: policies, strategies and costs

    International Nuclear Information System (INIS)

    As many nuclear power plants will reach the end of their lifetime during the next 20 years or so, decommissioning is an increasingly important topic for governments, regulators and industries. From a governmental viewpoint, particularly in a deregulated market, one essential aspect is to ensure that money for the decommissioning of nuclear installations will be available at the time it is needed, and that no 'stranded' liabilities will be left to be financed by the taxpayers rather than by the electricity consumers. For this reason, there is governmental interest in understanding decommissioning costs, and in periodically reviewing decommissioning cost estimates from nuclear installation owners. Robust cost estimates are key elements in designing and implementing a coherent and comprehensive national decommissioning policy including the legal and regulatory bases for the collection, saving and use of decommissioning funds. From the industry viewpoint, it is essential to assess and monitor decommissioning costs in order to develop a coherent decommissioning strategy that reflects national policy and assures worker and public safety, whilst also being cost effective. For these reasons, nuclear power plant owners are interested in understanding decommissioning costs as best as possible and in identifying major cost drivers, whether they be policy, strategy or 'physical' in nature. National policy considerations will guide the development of national regulations that are relevant for decommissioning activities. Following these policies and regulations, industrial managers responsible for decommissioning activities will develop strategies which best suit their needs, while appropriately meeting all government requirements. Decommissioning costs will be determined by technical and economic conditions, as well as by the strategy adopted. Against this backdrop, the study analyses the relationships among decommissioning policy as developed by governments, decommissioning

  18. Technology, safety and costs of decommissioning a refernce boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    International Nuclear Information System (INIS)

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation

  19. Optimization of Decommission Strategy for Offshore Wind Farms

    DEFF Research Database (Denmark)

    Hou, Peng; Hu, Weihao; Soltani, Mohsen;

    2016-01-01

    The life time of offshore wind farm is around 20 years. After that, the whole farm should be decommissioned which is also one of the main factors that contribute to the high investment. In order to make a costeffective wind farm, a novel optimization method for decommission is addressed in this p...

  20. Decontamination and decommissioning project for the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. (and others)

    2007-02-15

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future.

  1. Optimising waste management performance - The key to successful decommissioning

    International Nuclear Information System (INIS)

    Available in abstract form only. Full text of publication follows: On the 1. of April 2005 the United Kingdom's Nuclear Decommissioning Authority became responsible for the enormous task of decommissioning the UK's civilian nuclear liabilities. The success of the NDA in delivering its key objectives of safer, cheaper and faster decommissioning depends on a wide range factors. It is self-evident, however, that the development of robust waste management practices by those charged with decommissioning liability will be at the heart of the NDA's business. In addition, the implementation of rigorous waste minimisation techniques throughout decommissioning will deliver tangible environmental benefits as well as better value for money and release funds to accelerate the decommissioning program. There are mixed views as to whether waste minimisation can be achieved during decommissioning. There are those that argue that the radioactive inventory already exists, that the amount of radioactivity cannot be minimised and that the focus of activities should be focused on waste management rather than waste minimisation. Others argue that the management and decommissioning of the UK's civilian nuclear liability will generate significant volumes of additional radioactive waste and it is in this area where the opportunities for waste minimisation can be realised. (author)

  2. Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

    Science.gov (United States)

    Pollock, Cynthia

    The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

  3. 10 CFR 72.130 - Criteria for decommissioning.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for decommissioning. 72.130 Section 72.130 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT... Criteria § 72.130 Criteria for decommissioning. The ISFSI or MRS must be designed for...

  4. Decommissioning of nuclear facilities: Decontamination, disassembly and waste management

    International Nuclear Information System (INIS)

    The term 'decommissioning', as used within the nuclear industry, means the actions taken at the end of a facility's useful life to retire the facility from service in a manner that provides adequate protection for the health and safety of the decommissioning workers, the general public, and for the environment. These actions can range from merely closing down the facility and a minimal removal of radioactive material coupled with continuing maintenance and surveillance, to a complete removal of residual radioactivity in excess of levels acceptable for unrestricted use of the facility and its site. This latter condition, unrestricted use, is the ultimate goal of all decommissioning actions at retired nuclear facilities. The purpose of this report is to provide an information base on the considerations important to decommissioning, the methods available for decontamination and disassembly of a nuclear facility, the management of the resulting radioactive wastes, and the areas of decommissioning methodology where improvements might be made. Specific sections are devoted to each of these topics, and conclusions are presented concerning the present status of each topic. A summary of past decommissioning experience in Member States is presented in the Appendix. The report, with its discussions of necessary considerations, available operational methods, and waste management practices, together with supporting references, provides an appreciation of the activities that comprise decommissioning of nuclear facilities. It is anticipated that the information presented in the report should prove useful to persons concerned with the development of plans for the decommissioning of retired nuclear facilities

  5. Decommissioning and material recycling. Radiation risk management issues

    Energy Technology Data Exchange (ETDEWEB)

    Dodd, D.H.

    1996-09-01

    Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.).

  6. Decommissioning and material recycling. Radiation risk management issues

    International Nuclear Information System (INIS)

    Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.)

  7. Modern practice of cost estimates for the NPP units decommissioning

    International Nuclear Information System (INIS)

    The results of analysis of current practices of cost estimates for decommissioning of nuclear power units with different reactor types present is reviewed. Cost estimates intervals are shown for decommissioning of units with PWR,BWR and AP1000 reactors and the main factors influencing the cost amount are analyzed

  8. Decommissioning cost evaluation for Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    A systematic study was performed to develop decommissioning cost evaluation technology and to establish optimum decommissioning plan for Korean nuclear power plants. Eight decommissioning options for Kori unit I including DECON, SAFSTOR and ENTOMB were considered for detailed cost analysis. Immediate and delayed dismantling scenarios were compared each other in regards to economic, technical and social aspects. Fourteen decommissioning unit activities were considered in estimating unit cost factors including labor cost, consumables cost and equipment cost. The decommissioning cost for Kori unit 1 was lowest for DECON option and highest for ENTOMB-3 option in which the site recovery was made after entombment of 300 years. The main cost of the SAFSTOR option resulted from the dismantling and extended safe storage. For a long decommissioning period, the discount rate is crucial in estimating the decommissioning cost. The difference among decommissioning options was negligible in cost if a discount rate of 2% was assumed. The long-term safe storage option also became advantageous relative to the immediate dismantling option as the discount rate increased. (author)

  9. Decontamination and decommissioning project for the nuclear facilities

    International Nuclear Information System (INIS)

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future

  10. Decommissioning of surplus facilities at ORNL

    International Nuclear Information System (INIS)

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of certain DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 75 facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. This paper describes the scope of the ORNL program and outlines the decommissioning activities currently underway, including a brief description of the decontamination techniques being utilized. 4 refs., 3 figs., 2 tabs

  11. Allocation of Decommissioning and Waste Liabilities

    International Nuclear Information System (INIS)

    The work demonstrates that there are a number of methods available for cost allocation, the pros and cons of which are examined. The study investigates potential proportional and incremental methods in some depth. A recommendation in principle to use the latter methodology is given. It is concluded that a 'fair assumption' is that the potential allocation of costs for 'the RMA Leaching Hall' probably is small, in relation to the total costs, and estimated to be not more than about 175 kSEK, plus any costs associated with decommissioning/ disposal of a number of small pieces of equipment added by the current operator

  12. Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

    International Nuclear Information System (INIS)

    The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

  13. Standard Guide for Radiation Protection Program for Decommissioning Operations

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

  14. Financial aspects of decommissioning. Report by an expert group

    International Nuclear Information System (INIS)

    Estimating decommissioning costs and collecting funds for eventual decommissioning of facilities that have used radioactive material is a prerequisite for safe, timely and cost effective decommissioning. A comprehensive overview of decommissioning costs and funding mechanisms was missing in the IAEA literature although the subject had been marginally dealt with in a few IAEA publications. Costing and funding issues were partially addressed by other international organizations, but there is a need to address the subject from the standpoint of the diverse social, economic and cultural environments that constitute IAEA membership. In its role of an international expert committee assisting the IAEA, the Technical Group on Decommissioning (TEGDE) debates and draws conclusions on topics omitted from general guidance. TEGDE members met in Vienna in 2003, 2004 and 2005 to develop the basis for this publication. The views expressed here reflect those of TEGDE and not necessarily those of the IAEA

  15. Review of decommissioning, spent fuel and radwaste management in Slovakia

    International Nuclear Information System (INIS)

    Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

  16. U.S. experience with organizational issues during decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Durbin, N.E. [MPD Consulting, Kirkland, WA (United States); Harty, R. [Battelle Pacific Northwest National Laboratory, Richland, WA (United States)

    1998-01-01

    The report provides information from a variety of sources, including interviews with US NRC management and staff, interviews and discussions with former employees of a decommissioned plant, discussions with subject matter experts, and relevant published documents. The NRC has modified its rule regarding decommissioning requirements. Two key reasons for these modifications are that plants have been decommissioning early and for economic reasons instead of at the end of their license period and, a desire for a more efficient rule that would more effectively use NRC staff. NRC management and staff expressed the opinion that resource requirements for the regulatory have been higher than anticipated. Key observations about decommissioning included that: The regulator faces new challenges to regulatory authority and performance during decommissioning. The public concern over decommissioning activities can be very high. There are changes in the types of safety concerns during decommissioning. It is important to balance planning and the review of plans with verification of activities. There are important changes in the organizational context at the plant during decommissioning. Retention of key staff is important. In particular, the organizational memory about the plant that is in the staff should not be lost. Six key areas of risk during decommissioning are fuel storage, potential accidents that could cause an offsite release, inappropriate release of contaminated material, radiation protection of workers, industrial accidents, and shipment of hazardous materials. Deconstruction of one unit while a co-located unit is still operating could create risks with regard to shared systems, specific risks of dismantling activities and coordination and management. Experience with co-located units at one site in the US was that there was a lack of attention to the decommissioning plant.

  17. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle; Determinacion de Uranio en Muestras Procedentes del Desmantelamiento de Instalaciones de la Primera Parte del Cielo del Combustible Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A.; Correa, E.; Navarro, N.; Sancho, C. [Ciemat, Madrid (Spain); Angeles, A.

    2000-07-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  18. Occupational exposure monitoring during the decommissioning of a phosphoric acid production unit

    International Nuclear Information System (INIS)

    Full text: The enhanced concentration of natural radionuclides in the raw material of fertilizer plants, leads to increased levels of natural radioactivity in the by-products, wastes, equipment and residuals, as well as to the phosphoric acid production unit and its surroundings. The radiological survey and the implementation of the radiation protection system, during the site remediation and decommissioning of an old and abandoned phosphate fertilizer Greek industry, was one of GAEC's projects during last year. For the preliminary radiological characterization of the area, in situ and laboratory measurements were performed. During the in situ measurements, enhanced levels of natural radioactivity were detected; the measured gamma dose rate was up to 60μSv/h. The specific activity of the collected scale samples varied from 1 Bq/g up to 50Bq/g for Ra-226, and from 0.1 Bq/g up to 5Bq/g U-238 for U-238. Based on gamma and alpha spectrometric measurements of collected samples from raw materials such sludge, dust and air filters, and taking into account parameters proposed at the EC publication: Radiation Protection 107 'Establishment of reference levels for regulatory control of workplaces where materials are processed which contain enhanced levels of naturally-occurring radionuclides', the initial estimation of the total effective dose to workers involved in the decommissioning and decontamination process, following the worst case scenario was estimated up to 9mSv. Consequently, radiation protection measures had to be applied to the workers involved in the decommissioning and decontamination process, since there was a risk for external exposure as well as a risk for internal exposure resulting from the inhalation during mechanical operations such as sawing, cutting, grinding and polishing on scale contaminated components. Protective actions were taken, in order to minimize the radiological hazard. The six workers involved were submitted in a radiation protection

  19. Scientific rationale of Saturn's in situ exploration

    CERN Document Server

    Mousis, O; Lebreton, J -P; Wurz, P; Cavalié, T; Coustenis, A; Courtin, R; Gautier, D; Helled, R; Irwin, P G J; Morse, A D; Nettelmann, N; Marty, B; Rousselot, P; Venot, O; Atkinson, D H; Waite, J H; Reh, K R; Simon-Miller, A; Atreya, S; André, N; Blanc, M; Daglis, I A; Fischer, G; Geppert, W D; Guillot, T; Hedman, M M; Hueso, R; Lellouch, E; Lunine, J I; Murray, C D; O'Donoghue, J; Rengel, M; Sanchez-Lavega, A; Schmider, F -X; Spiga, A; Spilker, T; Petit, J -M; Tiscareno, M S; Ali-Dib, M; Altwegg, K; Bouquet, A; Briois, C; Fouchet, T; Guerlet, S; Kostiuk, T; Lebleu, D; Moreno, R; Orton, G S; Poncy, J

    2014-01-01

    Remote sensing observations meet some limitations when used to study the bulk atmospheric composition of the giant planets of our solar system. A remarkable example of the superiority of in situ probe measurements is illustrated by the exploration of Jupiter, where key measurements such as the determination of the noble gases abundances and the precise measurement of the helium mixing ratio have only been made available through in situ measurements by the Galileo probe. This paper describes the main scientific goals to be addressed by the future in situ exploration of Saturn placing the Galileo probe exploration of Jupiter in a broader context and before the future probe exploration of the more remote ice giants. In situ exploration of Saturn's atmosphere addresses two broad themes that are discussed throughout this paper: first, the formation history of our solar system and second, the processes at play in planetary atmospheres. In this context, we detail the reasons why measurements of Saturn's bulk element...

  20. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

  1. Decommissioning plan depleted uranium manufacturing facility

    International Nuclear Information System (INIS)

    Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

  2. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  3. Lessons learnt from Ignalina NPP decommissioning project

    International Nuclear Information System (INIS)

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  4. Decommissioning plan for TRIGA Mark-3

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Kook; Jung, Ki Jung

    1999-04-01

    TRIGA Mark-3(KRR-2) is the second research reactor in Korea. Construction of KRR-2 was started in 1969 and first criticality was achieved in 1972. After 24 years operation, KRR-2 has stopped its operation at the end of 1995 due to normal operation of HANARO. KRR-2 was then decided to decommission in 1996 by government. Decontamination and decommissioning(D and D) will be conducted in accordance with domestic laws and international regulations. Selected method of D and D will be devoted to protect workers and environment and to minimize radioactive wastes produced. The major D and D work will be conducted safely by using conventional industrial equipment because of relatively low radioactivity and contamination in the facility. When removing activated concrete from reactor pool, it will be installed a temporary containment and ventilation system. In this paper, structure of KRR-2 and method of D and D in each step are presented and discussed. (author). 12 refs., 8 tabs., 12 figs.

  5. The Decommissioning Facility Characterization DB System (DEFACS)

    International Nuclear Information System (INIS)

    The computer system for the characterization on the nuclear facilities is established as the name of the DEFACS (DEcommissioning FAcility Characterization DB System). his system is consist of the four main part with the grouping of the items and it's code creation and management system, data input system, data processing and data out put system. All the data was processed by a simplified and formatted manner to provide useful information to the decommissioning planner. The four nuclear facilities are objected for the system; the KRR-1 and 2 (Research reactor), Uranium conversion plant (Nuclear chemical plant), UF4 pilot plant and the North Korea nuclear facility (5MWe Research Reactor). All the data from a nuclear facility was categorized and inputted into the several data fields in the input system, which were chosen by considering the facility characteristics. All the hardware is workstation for Web and DB server and PC grade computers for the users and the software 'ORACLE, RDBMS 11g' operated on the WINDOW 2008 O/S, was selected

  6. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  7. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

  8. A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

    International Nuclear Information System (INIS)

    Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown

  9. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    International Nuclear Information System (INIS)

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of 3H-labeled compounds; a laboratory for the manufacture of 14C-labeled compounds; a laboratory for the manufacture of 123I-labeled compounds; a laboratory for the manufacture of 137Cs sealed sources; a laboratory for the manufacture of 241Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that

  10. In-situ characterization of heterogeneous catalysts

    CERN Document Server

    Rodriguez, Jose A; Chupas, Peter J

    2013-01-01

    Helps researchers develop new catalysts for sustainable fuel and chemical production Reviewing the latest developments in the field, this book explores the in-situ characterization of heterogeneous catalysts, enabling readers to take full advantage of the sophisticated techniques used to study heterogeneous catalysts and reaction mechanisms. In using these techniques, readers can learn to improve the selectivity and the performance of catalysts and how to prepare catalysts as efficiently as possible, with minimum waste. In-situ Characterization of Heterogeneous Catalysts feat

  11. In-situ tests in the JMTR

    International Nuclear Information System (INIS)

    The JMTR project has been developing various kind of irradiation rigs and instrumentation techniques for irradiation tests according to needs of users of JMTR. Currently, the needs for in-situ irradiation tests in research reactors are increasing in such fields as mechanical tests of reactor construction materials, measurement of physical/chemical/thermal property changes during irradiation, and examination of performance of fuels and materials. This paper describes some in-situ tests in the JMTR. (author)

  12. A miniaturized sensor system for in situ robotic characterization of hazardous waste

    International Nuclear Information System (INIS)

    This paper describes current research and development on miniaturized sensing systems for use during in situ characterization of nuclear waste storage tanks, buried waste sites, and decommissioned production facilities. Each miniaturized sensor system will consist of a suite of chemical, radiological, and physical properties sensors integrated into a compact package which will be mounted on the end of a robotic arm and/or vehicle. While the specific size of this remote sensor head and the types of sensors included will depend on site needs, the supporting generic computing system may be used for other waste characterization applications. This computing system will contain all necessary hardware and software to acquire, combine, interpret, display, and archive a wide range of sensor data. This paper describes the present status of the project, the lessons learned from the first prototype, and planned future designs of the next generation system. 7 refs

  13. In-situ gamma-PHA measurements to support unconditional release of 235-F chiller units

    International Nuclear Information System (INIS)

    The Analytical Development Section of Savannah River Technology Center (SRTC) was requested by the Facility Decommission Division (FDD) to conduct in-situ gamma-ray pulse height analysis measurements to support the unconditional release of 235-F chiller units. The chiller units were used to cool process water in the 235-F facility. The measurements' main goal is to confirm that there is no process-related contaminants present on the chillers. For each of the two F-area clean water chillers, the authors have acquired ten gamma-ray pulse height analysis spectra. This report will discuss the purpose of the measurements, the experimental setup, data acquisition, calculations and results, and a conclusion of the study

  14. Decommissioning and transport of teletherapy machines and irradiators

    International Nuclear Information System (INIS)

    Full text: The management and control of high activity gamma sources in non-power applications is a particular challenge for regulators of health and safety and the environment, throughout Member States. These sources (typically 60Co or 137Cs) are used in medical, educational or industrial applications, to benefit the health and quality of life of the general public. They do however present a significant risk to both people and the environment if not maintained, managed and controlled in accordance with radiation safety principals and the relevant legislation. This is particularly pertinent as these machines come to the end of their working lives and require decommissioning. Teletherapy machines are those which have been used for patient cancer treatment. These units are almost always found in radiotherapy departments in hospitals, although a few have been used in industrial non-destructive testing (NDT) applications, or for calibration. They are 'mass produced' and designed to be re-sourced in-situ and therefore have proven and documented load/unload procedures. The sources in these units are usually held in a shielded 'head', often containing depleted uranium. Due to its own radioactive properties, the depleted uranium shielding presents at least as much of a disposal challenge as the source itself. In the majority of cases, purpose designed mating plates exist for transferring sources from these units into approved transport containers. Irradiators present different challenges and often require a novel approach due to age of sources and mass of inherent shielding. Many of the units now destined for decommissioning were originally constructed in the sixties and have often been customised to meet customers' specific requirements, or even home-made by the physicists. There are therefore many variations, for which there is little or no information available and rarely any detail on how or if the source(s) can be extracted. Many of these units date back to an era

  15. 26 CFR 1.468A-4T - Treatment of nuclear decommissioning fund (temporary).

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Treatment of nuclear decommissioning fund...-4T Treatment of nuclear decommissioning fund (temporary). (a) In general. A nuclear decommissioning... income earned by the assets of the nuclear decommissioning fund. (b) Modified gross income. For...

  16. Combining Space-Based and In-Situ Measurements to Track Flooding in Thailand

    Science.gov (United States)

    Chien, Steve; Doubleday, Joshua; Mclaren, David; Tran, Daniel; Tanpipat, Veerachai; Chitradon, Royal; Boonya-aaroonnet, Surajate; Thanapakpawin, Porranee; Khunboa, Chatchai; Leelapatra, Watis; Plermkamon, Vichian; Raghavendra, Cauligi; Mandl, Daniel

    2011-01-01

    We describe efforts to integrate in-situ sensing, space-borne sensing, hydrological modeling, active control of sensing, and automatic data product generation to enhance monitoring and management of flooding. In our approach, broad coverage sensors and missions such as MODIS, TRMM, and weather satellite information and in-situ weather and river gauging information are all inputs to track flooding via river basin and sub-basin hydrological models. While these inputs can provide significant information as to the major flooding, targetable space measurements can provide better spatial resolution measurements of flooding extent. In order to leverage such assets we automatically task observations in response to automated analysis indications of major flooding. These new measurements are automatically processed and assimilated with the other flooding data. We describe our ongoing efforts to deploy this system to track major flooding events in Thailand.

  17. In situ microcosms in aquifer bioremediation studies.

    Science.gov (United States)

    Mandelbaum, R T; Shati, M R; Ronen, D

    1997-07-01

    The extent to which aquifer microbiota can be studied under laboratory or simulated conditions is limited by our inability to authentically duplicate natural conditions in the laboratory. Therefore, extrapolation of laboratory results to real aquifer situations is often criticized, unless validation of the data is performed in situ. Reliable data acquisition is critical for the estimation of chemical and biological reaction rates of biodegradation processes in groundwater and as input data for mathematical models. Typically, in situ geobiochemical studies relied on the injection of groundwater spiked with compounds or bacteria of interest into the aquifer, followed by monitoring the changes over time and space. In situ microcosms provide a more confined study site for measurements of microbial reactions, yet closer to natural conditions than laboratory microcosms. Two basic types of in situ aquifer microcosm have been described in recent years, and both originated from in situ instruments initially designed for geochemical measurements. Gillham et al. [Ground Water 28 (1990) 858-862] constructed an instrument that isolates a portion of an aquifer for in situ biochemical rate measurements. More recently Shati et al. [Environ. Sci. Technol. 30 (1996) 2646-2653] modified a multilayer sampler for studying the activity of inoculated bacteria in a contaminated aquifer Keeping in mind recent advances in environmental microbiology methodologies such as immunofluorescence direct counts, oligonucleotide and PCR probes, fatty acid methyl esther analysis for the detection and characterization of bacterial communities, measurement of mRNA and expression of proteins, it is evident that much new information can now be gained from in situ work. Using in situ microcosms to study bioremediation efficiencies, the fate of introduced microorganisms and general geobiochemical aquifer processes can shed more realistic light on the microbial underworld. The aim of this paper is to

  18. Decommissioning planning for the Joint European Torus Fusion Reactor

    International Nuclear Information System (INIS)

    The Joint European Torus (JET) machine is an experimental nuclear fusion device built in the United Kingdom by a European consortium. Tritium was first introduced into the Torus as a fuel in 1991 and it is estimated that at the end of operations and following a period of tritium recovery there will be 2 grams of tritium in the vacuum circuit. All in-vessel items are also contaminated with beryllium and the structure of the machine is neutron activated. Decommissioning of the facility will commence immediately JET operations cease and the UKAEA's plan is to remove all the facilities and to landscape the site within 10 years. The decommissioning plan has been through a number of revisions since 1995 that have refined the detail, timescales and costs. The latest 2005 revision of the decommissioning plan highlighted the need to clarify the size reduction and packaging requirements for the ILW and LLW. Following a competitive tender exercise, a contract was placed by UKAEA with NUKEM Limited to undertake a review of the waste estimates and to produce a concept design for the planned size reduction and packaging facilities. The study demonstrated the benefit of refining decommissioning planning by increasing the detail as the decommissioning date approaches. It also showed how a review of decommissioning plans by independent personnel can explore alternative strategies and result in improved methodologies and estimates of cost and time. This paper aims to describe this part of the decommissioning planning process and draw technical and procedural conclusions. (authors)

  19. Education and Training in Decommissioning Needs, Opportunities and Challenges

    International Nuclear Information System (INIS)

    The decommissioning of nuclear facilities is an industrial activity that is growing worldwide, creating job opportunities at all educational levels. Over the last decades, European companies have been involved in decommissioning projects that are targeted at delivering an environmentally friendly end-product, in line with the 'circular economy', as promoted by EU and national policies. European industry has acquired know-how and today Europe can position itself at the top level in the world decommissioning market. However, in view of the preparation of future decommissioning programmes, efforts are necessary to ensure and share the underpinning knowledge, skills and competences. In this perspective, the University of Birmingham in association with the European Commission's Joint Research Centre have organised a joint seminar to address the following questions in relation to education and training in nuclear decommissioning: - What are the competence needs for the future? - What are the education and training opportunities? - How can we stimulate interest and future talent? In answering these questions a report has been published which provides suggestions for helping the development, coordination and promotion of adequate education and training programmes at EU level in nuclear decommissioning. It highlights, in particular, the necessity to improve the long term planning of the resources and competences, addressing the specifics of decommissioning activities, to give more visibility to the career possibilities in the sector, and to enhance the cooperation between the existing education and training programmes, providing also more clarity in the learning outcomes. (authors)

  20. Factors influencing the decommissioning of large-scale nuclear plants

    International Nuclear Information System (INIS)

    The decision-making process involving the decommissioning of the UK graphite moderated, gas-cooled nuclear power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors to consider and the overall decision of when and how to proceed with decommissioning may include political and public tolerance dimensions. For the final stage of decommissioning the nuclear industry could either completely dismantle the reactor island leaving a green-field site or, alternatively, the reactor island could be maintained indefinitely with additional super- and substructure containment. At this time the first of these options, or deferred decommissioning, prevails and with this the nuclear industry has expressed considerable confidence that the technology required will become available with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint. If the deferred decommissioning strategy is wrong and it is not possible to completely dismantle the reactor islands a century into the future, then it may be too late to effect sufficient longer term containment to maintain the reactor hulks in a reliable condition. With respect to the final decommissioning of large-scale nuclear plant, it is concluded that the nuclear industry does not know quite how to do it, when it will be attempted and when it will be completed, and they do not know how much it will eventually cost. (author)

  1. Decommissioning Experience: Magnox Reactors in the United Kingdom

    International Nuclear Information System (INIS)

    There are ten Magnox sites in the United Kingdom, nine of which are shut down and are defuelling and decommissioning. The Wylfa facility, in Wales, was due to shut down in 2014 but has been delayed. Magnox ponds are reinforced poured concrete structures with an epoxy paint coating. The decommissioning of Magnox ponds takes place once defuelling has been completed and is subject to an overarching fleet plan called the Magnox optimized decommissioning programme (MODP). The MODP has been determined to enable the most cost effective hazard reduction across the Magnox sites and to enable learning to be gained and transferred through delivering decommissioning as consistent programmes across all sites. For pond decommissioning, this involves the movement of experienced staff between sites to integrate with site teams and deliver the decommissioning of the ponds to a consistent methodology. Magnox has a decommissioning and radioactive waste management strategy that indicates full decontamination and removal and backfill of ponds and reflects lessons being learned from work completed to establish the most practicable means of risk reduction for each site. A summary of current Magnox experience is given below. An up to date overview of pond programme experiences across the Magnox sites is available on the Magnox web site

  2. Procedures and Practices - Challenges for Decommissioning Management and Teamwork

    International Nuclear Information System (INIS)

    The mental and practical approach to a decommissioning project is often not the same at all levels of an organization. Studies indicate that the early establishment of a decommissioning mindset throughout an organization is an important and frequently overlooked process. It is not enough to establish procedures, if practices and mental approaches are overlooked; and for decommissioning projects that are more often than not dominated by one of a kind problem solving, procedure design is challenging, and new requirements are put on communication. Our research considers stakeholder involvement in these processes in the wider sense of the term; however the main stakeholders in focus are regulators and the work force that will perform or lead the tasks related to decommissioning. Issues here treated include: Decommissioning mindset and the manifestation of mindset issues in decommissioning projects, including challenges and prospective solutions; trust building and trust breaking factors in communication and collaboration relevant to transition and decommissioning; new technologies for collaboration and communication and how these may impair or empower participants - experiences from several domains. This paper is based on work done in collaboration with the OECD NEA Halden Reactor Project. (author)

  3. DECOMMISSIONING OF A CAESIUM-137 SEALED SOURCE PRODUCTION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Murray, A.; Abbott, H.

    2003-02-27

    Amersham owns a former Caesium-137 sealed source production facility. They commissioned RWE NUKEM to carry out an Option Study to determine a strategy for the management of this facility and then the subsequent decommissioning of it. The decommissioning was carried out in two sequential phases. Firstly robotic decommissioning followed by a phase of manual decommissioning. This paper describes the remote equipment designed built and operated, the robotic and manual decommissioning operations performed, the Safety Management arrangements and summarizes the lessons learned. Using the equipment described the facility was dismantled and decontaminated robotically. Some 2300kg of Intermediate Level Waste containing in the order of 4000Ci were removed robotically from the facility. Ambient dose rates were reduced from 100's of R per hour {gamma} to 100's of mR per hour {gamma}. The Telerobotic System was then removed to allow man access to complete the decommissioning. Manual decommissioning reduced ambient dose rates further to less than 1mR per hour {gamma} and loose contamination levels to less than 0.25Bq/cm2. This allowed access to the facility without respiratory protection.

  4. The effect of wind, ice and waves on the in-situ burning of emulsions and aged oils

    International Nuclear Information System (INIS)

    A series of small- and meso-scale in-situ burning tests was conducted on Spitsbergen to define the limitations and burn effectiveness of in-situ burning of water-in-oil emulsions in terms of water content, degree of evaporation, and film thickness; and to study how the presence of ice, waves, and wind affect in-situ burning. The tests were conducted in basins cut into the ice on a fjord. The size of the basins ranged from 4 to 300 m2. The largest basin was fitted with a wavemaker. Evaporated water-free oil was found to be easily ignited and to burn with high efficiency. The burn efficiency was not affected by waves. Highly evaporated oil with 25% water was hard to ignite with gelled gasoline. In the presence of waves, it was not possible to ignite a 12.5% stable water-in-oil emulsion. The presence of waves reduced the burn efficiency for emulsion with a low water content. The main problem with in-situ burning of emulsions is flame spreading; emulsions require a large initial burn area for the burn to be self-sustaining. Small ice floes and slush did not influence burn efficiency in a negative way. In-situ burning could not be accomplished in wind speeds above 10 m/s. 2 refs., 5 figs., 5 tabs

  5. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    International Nuclear Information System (INIS)

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

  6. When a plant shuts down: The psychology of decommissioning

    International Nuclear Information System (INIS)

    Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant after a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine

  7. Radiological planning and implementation for nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures

  8. Decommissioning health physics a handbook for MARSSIM users

    CERN Document Server

    Abelquist, Eric W

    2001-01-01

    Decommissioning Health Physics presents many of the technical issues and challenges that arise during the planning and implementation of decommissioning and decontamination (D&D) projects. The focus is on the final status survey performed during the later stages of decommissioning projects. It expands upon and provides greater technical detail than Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) in areas of survey design strategies.Featuring a number of completely worked examples of final status survey strategies, the book prepares the reader for the real-world ap

  9. Nuclear reactor decommissioning: an analysis of the regulatory environments

    International Nuclear Information System (INIS)

    The purpose of this study is to highlight some of the current and likely regulations that will significantly affect the costs, technical alternatives and financing schemes for reactor decommissioning encountered by electric utilities and their customers. The paper includes a general review of the decommissioning literature, as well as information on specific regulations at the federal, state, and utility levels. Available estimated costs for the decommissioning of individual reactors are also presented. Finally, classification of the specific policies into common trends and practices among the various regulatory bodies is used to examine more general regulatory environments and their potential financial implications

  10. A study on the decommissioning of research reactor

    International Nuclear Information System (INIS)

    As the result of study on decommissioning, discussion has made and data have been collected about experiences, plannings, and techniques for decommissioning through visit to GA and JAERI. GA supplied our Research Reactor No. 1 and No. 2, and JAERI made a memorial museum after dicommissioning of JRR-1 and is dismentling JPDR now. Also many kinds of documents are collected and arranged such as documents related to TRIGA reactor dicommissioning, 30 kinds of documents including decommissioning plan, technical criteria and related regulatory, and 1,200 kinds of facility description data. (Author)

  11. Decontamination and Decommissioned Small Nuclear AIP Hybrid Systems Submarines

    Directory of Open Access Journals (Sweden)

    Guangya Liu

    2013-11-01

    Full Text Available Being equipped with small reactor AIP is the trend of conventional submarine power in 21st century as well as a real power revolution in conventional submarine. Thus, the quantity of small reactor AIP Submarines is on the increase, and its decommissioning and decontamination will also become a significant international issue. However, decommissioning the small reactor AIP submarines is not only a problem that appears beyond the lifetime of the small reactor nuclear devices, but the problem involving the entire process of design, construction, running and closure. In the paper, the problem is explored based on the conception and the feasible decommissioning and decontamination means are supplied to choose from.

  12. KIT competence center for decommissioning. Innovation and promotion of trainees

    International Nuclear Information System (INIS)

    The safe decommissioning of nuclear installations is technically feasible, but is also still a challenge for science, technology and industry. The expertise and know how for decommissioning must be ensured because it will be needed for further decades. Already in 2008 the Karlsruhe Institute of Technology (KIT) had identified this challenge that later emerged through the closure of nuclear power plants in Germany. The KIT opened the professorship Technology and Management of the Decommissioning of Nuclear Installations. In 2014, this section was extended through the dismantling of conventional installations.

  13. R and D and Innovation Needs for Decommissioning Nuclear Facilities

    International Nuclear Information System (INIS)

    Nuclear decommissioning activities can greatly benefit from research and development (R and D) projects. This report examines applicable emergent technologies, current research efforts and innovation needs to build a base of knowledge regarding the status of decommissioning technology and R and D. This base knowledge can be used to obtain consensus on future R and D that is worth funding. It can also assist in deciding how to collaborate and optimise the limited pool of financial resources available among NEA member countries for nuclear decommissioning R and D. (authors)

  14. Design features facilitating the decommissioning of advanced gas-cooled reactors

    International Nuclear Information System (INIS)

    The design of the advanced gas-cooled reactors is discussed as is the proposed decommissioning plan for delayed decommissioning. The special features which assist in decommissioning are presented. As a result of the study a catalogue of design features which will facilitate decommissioning is given. In addition to the catalogue of design features, the radioactive inventory 10 years after shutdown and 100 years after shutdown has been calculated. From this a provisional operator dose from activities associated with decommissioning has been assessed

  15. Estimated decommissioning cost for the 23 operating nuclear power reactors in Korea

    International Nuclear Information System (INIS)

    The decommissioning of nuclear power reactors requires considerable funds and is carried out over a long period. In order to forecast the total decommissioning funds needed by the licensee as well as provide a basis for industrial strategy and decommissioning activity planning, hence, this paper estimates the annual costs for decommissioning the 23 nuclear power plants in Korea between 2014 and 2083. For this estimation, 4 scenarios for decommissioning the 23 nuclear power reactors were developed and evaluated. (orig.)

  16. FLUOR HANFORD DECOMMISSIONING UPDATE: SPRING 2008

    International Nuclear Information System (INIS)

    Fluor Hanford is completing D and D of the K East Basin at the U.S. Department of Energy's (DOE's) Hanford Site in southeastern Washington State this spring, with demolition expected to begin in June. Located about 400 yards from the Columbia River, the K East Basin is one of two indoor pools that formerly contained irradiated nuclear fuel, radioactive sludge and tons of contaminated debris. In unique and path-breaking work, workers finished removing the spent fuel from the K Basins in 2004. In May 2007, workers completed vacuuming the sludge into containers in the K East Basin, and transferring it into containers in the K West Basin. In December, they finished vacuuming the remainder of K West Basin sludge into these containers. The K East Basin was emptied of its radioactive inventory first because it was more contaminated than the K West Basin, and had leaked in the past. In October 2007, Fluor Hanford began physical D and D of the 8,400-square foot K East Basin by pouring approximately 14-inches of grout into the bottom of it. Grout is a type of special cement used for encasing waste. Two months later, Fluor Hanford workers completed sluicing contaminated sand from the large filter that had sieved contaminants from the basin water for more than 50 years. Next, they poured grout into the filter housing and the vault that surrounds the filter, as well as into ion exchange columns that also helped filter basin water. For a six-week period in February and March, personnel drained the approximately one million gallons of contaminated water from the K East Basin. The effort required more than 200 tanker truck loads that transported the water to an effluent treatment facility for treatment and then release. A thin fixative was also applied to the basin walls as the water was removed to hold residual contamination in place. As soon as the water was out of the basin, Fluor pumped in approximately 18 feet of 'controlled density fill' material (somewhat similar to sand

  17. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    Energy Technology Data Exchange (ETDEWEB)

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  18. Remote control: Decommissioning RTGs [radioisotope theromelectric generators

    International Nuclear Information System (INIS)

    Several hundred radioisotope thermoelectric generators (RTGs) are deployed along the Russian Federation's Arctic coast to power remote lighthouses and navigation beacons. Similar RTGs were also used as power sources in other remote locations in the Russian Federation and elsewhere in the former Soviet Union. All Russian RTG's have out-lived their lifespan and are in need of decommissioning. The RTGs typically contain one or more radionuclide heat sources (RHS) each with an activity of thousands of TBq of strontium-90. This means that they are Category 1 sources as defined in the IAEA international 'Code of Conduct on the Safety and Security of Radioactive Sources'. According to the Federal Atomic Energy Agency of the Russian Federation (Rosatom), there are 651 RTGs at various locations in the Russian Federation which are subject to decommissioning or replacement with alternative sources of energy. The Norwegian Government has played a significant role in international efforts, fully cooperating with Russian authorities to safely decommission RTGs and provide alternative power sources. Norway has actively supported improvement of nuclear safety and security in northwest Russia for more then ten years. Over this period, the Norwegian Government has spent approximately $150 million on a variety of industrial projects, including specific improvements in radioactive waste treatment and storage, physical security, and infrastructure support. The national authority, the Norwegian Radiation Protection Authority (NRPA), takes an active part advising the Government regarding prioritization and quality assurance of all these activities. In addition, the Plan of Action places great emphasis on adequate regulatory supervision. Accordingly, the NRPA programme includes a variety of regulatory support projects. These are designed to assist the Russian authorities in ensuring that work is properly carried out within the framework of Russian law, taking into account international

  19. Large packages for reactor decommissioning waste

    International Nuclear Information System (INIS)

    This study was carried out jointly by the Atomic Energy Establishment at Winfrith (now called the Winfrith Technology Centre), Windscale Laboratory and Ove Arup and Partners. The work involved the investigation of the design of large transport containers for intermediate level reactor decommissioning waste, ie waste which requires shielding, and is aimed at European requirements (ie for both LWR and gas cooled reactors). It proposes a design methodology for such containers covering the whole lifetime of a waste disposal package. The design methodology presented takes account of various relevant constraints. Both large self shielded and returnable shielded concepts were developed. The work was generic, rather than specific; the results obtained, and the lessons learned, remain to be applied in practice

  20. Decommissioning and deactivation of nuclear facilities

    International Nuclear Information System (INIS)

    The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

  1. In-situ bioremediation via horizontal wells

    International Nuclear Information System (INIS)

    This project is designed to demonstrate in situ bioremediation of groundwater and sediment contaminated with chlorinated solvents. Indigenous microorganisms were stimulated to degrade TCE, PCE and their daughter products in situ by addition of nutrients to the contaminated zone. In situ biodegradation is a highly attractive technology for remediation because contaminants are destroyed, not simply moved to another location or immobilized, thus decreasing costs, risks, and time, while increasing efficiency and public and regulatory acceptability. Bioremediation has been found to be among the least costly technologies in applications where it will work (Radian 1989). Subsurface soils and water adjacent to an abandoned process sewer line at the SRS have been found to have elevated levels of TCE (Marine and Bledsoe 1984). This area of subsurface and groundwater contamination is the focus of a current integrated demonstration of new remediation technologies utilizing horizontal wells. Bioremediation has the potential to enhance the performance of in situ air stripping as well as offering stand-alone remediation of this and other contaminated sites (Looney et al. 1991). Horizontal wells could also be used to enhance the recovery of groundwater contaminants for bioreactor conversions from deep or inaccessible areas (e.g., under buildings) and to enhance the distribution of nutrient or microbe additions in an in situ bioremediation

  2. Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

    Science.gov (United States)

    2010-01-01

    NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

  3. Construction times and the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The construction and the decommissioning periods of nuclear power plants (NPP), are studied, due to their importance in the generation costs. With reference to the construction periods of these plants, a review is made of the situation and technical improvements made in different countries, with the purpose of shortening them. In regard to the decommissioning of NPP, the present and future situations are reviewed in connection with different stages of decommissioning and their related problems, as the residual radioactivity of different components, and the size of the final wastes to be disposed of. The possibilities of plant life extensions are also revised in connection with these problems. Finally, the expected decommissioning costs are analyzed. (Author)

  4. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  5. Current status and future plan of decommissioning in JAPCO

    International Nuclear Information System (INIS)

    The Tokai Nuclear Power Plant (NPP), the Japan first commercial nuclear power reactor, has already started decommissioning in December, 2001. The Japan Atomic Power Company (JAPCO) has conducted this 'Tokai project'. And the JAPCO submitted an application for disposal planning of very-low-level radioactive waste arising from the project in July, 2015. Furthermore, the JAPCO has continued to perform preparatory tasks for decommissioning of the Tsuruga NPP Unit 1 (TS-1), the Japan first LWR. An announcement of permanent shutdown of the Unit was released in March 2015. This report describes an experience of the Tokai decommissioning project, our practice of the preparatory tasks for TS-1 project and future plants for these decommissioning projects. (author)

  6. Developing Integrated Decommissioning Information Management System (IDIMS) of nuclear facilities

    International Nuclear Information System (INIS)

    In Taiwan, the Taiwan Research Reactor (TRR) was shut down in January 1988, and a few nuclear facilities were accompanied to stop operation within Institute of Nuclear Energy Research (INER). For public health and safety reasons, INER dismantled step by step its expired nuclear facilities. Integrated Decommissioning Information Management System (IDIMS) was developed to ensure safety of dismantling and to record all activity data during the decommissioning project. These recorded activity data range from data of planning, licensing, post-operation to those of radioactive waste management and storage. In addition, IDIMS was expected to preserve decommissioning knowledge using information technology from practical data and problem solving. It also is anticipated that IDIMS will be an important knowledge repository and design base for decommissioning projects of nuclear power plants in Taiwan. (author)

  7. Decommissioning of the ICI TRIGA Mark I reactor

    Energy Technology Data Exchange (ETDEWEB)

    Parry, D.R.; England, M.R.; Ward, A. [BNFL, Sellafield (United Kingdom); Green, D. [ICI Chemical Polymers Ltd, Billingham (United Kingdom)

    2000-07-01

    This paper considers the fuel removal, transportation and subsequent decommissioning of the ICI TRIGA Mark I Reactor at Billingham, UK. BNFL Waste Management and Decommissioning carried out this work on behalf of ICI. The decommissioning methodology was considered in the four stages to be described, namely Preparatory Works, Reactor Defueling, Intermediate Level Waste Removal and Low Level Waste Removal. This paper describes the principal methodologies involved in the defueling of the reactor and subsequent decommissioning operations, highlighting in particular the design and safety case methodologies used in order to achieve a solution which was completed without incident or accident and resulted in a cumulative radiation dose to personnel of only 1.57 mSv. (author)

  8. Decommissioning of the Wuergassen nuclear power plant, a commercial challenge

    International Nuclear Information System (INIS)

    In response to the inspection results which detected cracks in the core shroud, economic aspects have induced PreussenElektra to opt for decommissioning and dismantling of the Wuergassen reactor. As this shutdown of the nuclear power plant is not a planned shutdown, costs arising in addition to the original decommissioning framework studies have to be assessed, especially the expenditure for the adjusted plant manpower requirements, and the additional operating and phase-out costs. Experience has shown that the decommissioning of a nuclear power plants does not pose problems in terms of safety or technology, but still is a commercial challenge. Expense forecasts have to be adjusted in response to the unplanned shutdown. PreussenElektra therefore has set up a modified project and operating structure. The analysis and evaluation of the first decommissioning phase will show whether the cost assessment approaches are in agreement with reality. (orig.)

  9. DECOST: computer routine for decommissioning cost and funding analysis

    International Nuclear Information System (INIS)

    One of the major controversies surrounding the decommissioning of nuclear facilities is the lack of financial information on just what the eventual costs will be. The Nuclear Regulatory Commission has studies underway to analyze the costs of decommissioning of nuclear fuel cycle facilities and some other similar studies have also been done by other groups. These studies all deal only with the final cost outlays needed to finance decommissioning in an unchangeable set of circumstances. Funding methods and planning to reduce the costs and financial risks are usually not attempted. The DECOST program package is intended to fill this void and allow wide-ranging study of the various options available when planning for the decommissioning of nuclear facilities

  10. Development of decontamination, decommissioning and environmental restoration technology

    International Nuclear Information System (INIS)

    Through the project of Development of decontamination, decommissioning and environmental restoration technology, the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

  11. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

  12. The Decommissioning of the Trino Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise

  13. Progress in Decommissioning of Ignalina NPP Unit 1

    International Nuclear Information System (INIS)

    The aim of the paper is to present the Lithuanian legal framework regarding the nuclear safety in Decommissioning and Waste Management, and the progress in the Decommissioning Programme of the unit 1 of Ignalina Nuclear Power Plant (INPP). INPP is the only nuclear plant in Lithuania. It comprises two RBMK-1500 reactors. After Lithuania has restored its independence, responsibility for Ignalina NPP was transferred to the Republic of Lithuania. To ensure the control of the Nuclear Safety in Lithuania, The State Nuclear Power Safety Inspectorate (VATESI) was created on 18 October 1991, by a resolution of the Lithuanian Government. Significant work has been performed over the last decade, aiming at upgrading the safety level of the Ignalina NPP with reference to the International standards. On 5 October 1999 the Seimas (Parliament) adopted the National Energy Strategy: It has been decided that unit 1 of Ignalina NPP will be closed down before 2005, The conditions and precise final date of the decommissioning of Unit 2 will be stated in the updated National Energy strategy in 2004. On 20-21 June 2000, the International Donors' Conference for the Decommissioning of Ignalina NPP took place in Vilnius. More than 200 Millions Euro were pledged of which 165 M funded directly from the European Union's budget, as financial support to the Decommissioning projects. The Decommissioning Program encompasses legal, organizational, financial and technical means including the social and economical impacts in the region of Ignalina. The Program is financed from International Support Fund, State budget, National Decommissioning Fund of Ignalina NPP and other funds. Decommissioning of Ignalina NPP is subject to VATESI license according to the Law on Nuclear Energy. The Government established the licensing procedure in the so-called 'Procedure for licensing of Nuclear Activities'; and the document 'General Requirements for Decommissioning of the Ignalina NPP' has been issued by VATESI. A

  14. Preliminary decommissioning plan of the reactor IPEN-MB01

    International Nuclear Information System (INIS)

    Around the world, many nuclear plants were built and need to be turned off at a certain time because they are close to their recommended time of use is approximately 50 years. So the IAEA (International Atomic Energy Agency), seeks to guide and recommend a set of guidelines for the conduct of activities of nuclear facilities, with special attention to countries that do not have a framework regulatory Legal that sustain the activities of decommissioning. Brazil, so far, does not have a specific standard to guide the steps of the guidelines regarding decommissioning research reactors. However, in March 2011 a study committee was formed with the main task facing the issues of decommissioning of nuclear installations in Brazil, culminating in Resolution 133 of November 8, 2012, a standard project that treat about the Decommissioning of nucleoelectric plants. O Instituto de Pesquisas Energeticas e Nucleares (IPEN) has two research reactors one being the reactor IPEN/MB-01. The purpose of this master dissertation is to develop a preliminary plan for decommissioning this research reactor, considering the technical documentation of the facility (RAS-Safety Analysis Report), the existing standards of CNEN (National Nuclear Energy Commission), as well as IAEA recommendations. In terms of procedures for decommissioning research reactors, this work was based on what is most modern in experiences, strategies and lessons learned performed and documented in IAEA publications covering techniques and technologies for decommissioning. Considering these technical knowledge and due to the peculiarities of the facility, was selected to immediate dismantling strategy, which corresponds to the start of decommissioning activities once the installation is switched off, dividing it into work sectors. As a resource for monitoring and project management of reactor decommissioning and maintenance of records, we developed a database using Microsoft Access 2007, which contain all the items and

  15. IAEA/CRP for decommissioning techniques for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H

    2001-03-01

    The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities.

  16. Knowledge management for the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    This paper describes background, objectives and select conceptual components of knowledge management for the decommissioning of nuclear power plants. The concept focuses on the transfer of personal practice experience within and between nuclear power plants. The conceptual insights embrace aspects of knowledge content, structure, KM processes, organization, cooperation, culture, persuasion, leadership, technology, infrastructure, business impact and resilience. Key challenges are discussed, and related advice is provided for KM practitioners with similar endeavours in the field of nuclear power plant decommissioning. (author)

  17. Decommissioning of the Loviisa NPP; Loviisan ydinvoimalaitoksen kaeytoestaepoisto

    Energy Technology Data Exchange (ETDEWEB)

    Kallonen, I.; Eurajoki, T.; Mayer, E. [IVO Power Engineering Oy, Vantaa (Finland)

    1998-12-31

    Imatran Voima Oy has revised the decommissioning plan for the Loviisa Nuclear Power Plant (Loviisa 1 and Loviisa 2) by the end of the year 1998. The thermal power of the power plant has been increased to 2x1500 MW{sub th}, and the life time has been designed to be extended to 45 years in the decommissioning plan. The decommissioning of the power plant is designed to begin in 2022 and it will be finished in 2048. The plan is based on immediate dismantlement (i.e. DECON) after the shut down of the power plant. Experienced plant personnel will still be available to lead the decommissioning work. Only the radioactive plant systems, components and structures will be dismantled and disposed of. Decommissioning wastes will be disposed into the underground disposal tunnels situating at the site in the depth of about 110 m. These tunnels are already partly ready for power plant wastes. The big and heavy reactor components, e.g. pressure vessels and steam generators, will be disposed of as such, without cutting them into smaller parts. This saves time and radiation doses. The total volume of decommissioning wastes is 14 800 m{sup 3}, when packed in boxes. The manpower needed for decommissioning is about 2 800 manyears. The collective radiation dose for personnel is estimated to be about 9.2 manSv. The cost estimate of the decommissioning is about 1 117 million FIM. The spent fuel will be stored at the plant for 20 years after the shut down of the power plant. After that it will be transported from the site to the encapsulation plant for final disposal. (orig.) 15 refs.

  18. Decommissioning the Los Alamos Molten Plutonium Reactor Experiment (LAMPRE I)

    International Nuclear Information System (INIS)

    The Los Alamos Molten Plutonium Reactor Experiment (LAMPRE I) was decommissioned at the Los Alamos National Laboratory, Los Alamos, New Mexico, in 1980. The LAMPRE I was a sodium-cooled reactor built to develop plutonium fuels for fast breeder applications. It was retired in the mid-1960s. This report describes the decommissioning procedures, the health physics programs, the waste management, and the costs for the operation

  19. The 'old and the new' of decommissioning Dounreay

    International Nuclear Information System (INIS)

    The Dounreay site is situated on the north coast of Scotland, mainland United Kingdom, and since the 1950s it has been instrumental in fast breeder research and fuel reprocessing plant development. The work programme on the site has changed, and is now one of safe decommissioning and site restoration. Previous papers have discussed and reviewed progress during the very early stages of the decommissioning programme and this paper provides an update on the work programme from a primarily radiation protection perspective. This paper discusses progress in decommissioning the Dounreay site and the adoption of 'tried and tested', as well as innovative techniques to achieve this decommissioning safely. This includes detailed discussion of the radiation protection aspects of decommissioning, and the consideration and implementation of various radiological protection controls within varying decommissioning environments, such as: a) Remote operations; b) Robotics; c) Shielding; d) Remote readout dosimetry (during personnel entry into elevated dose rate areas). The change from an operational to a decommissioning work programme at Dounreay, created a requirement to modify the type and variety of radiological personal protective equipment (PPE) available. The selection of appropriate PPE, utilised following exhaustion of the hierarchy of controls, to remove the residual radiological risk to personnel is discussed within the paper. The benefit of developing this PPE, as well as other controls, in collaboration with the operatives performing the work, is clearly obvious. The paper concludes with a review of the relative merits and success of the decommissioning techniques that have been adopted, from a radiological protection perspective, together with a summary of lessons learnt. (author)

  20. Legal and Regulatory Frameworks for Decommissioning and Waste Management

    International Nuclear Information System (INIS)

    Safe and efficient decommissioning and waste management requires clear structures for allocating responsibility and funding. Organisation of decommissioning and waste management activities and the regulatory environment within which those activities are undertaken should also allow the supply chain to prosper and, wherever possible, reduce barriers to international availability of resources and waste facilities. Radioactive waste treatment and disposal in particular raises both legal and political challenges to effective international co-operation, yet options for decommissioning and waste management are maximised where international barriers can be minimised. Added to this, international nuclear liabilities issues must be managed so as to avoid unnecessary deterrents to international mobility of capability within the decommissioning market. Contractual terms and insurance arrangements for international shipments of nuclear waste and materials will also need to take into account imminent changes to liabilities conventions, ensuring compliance and management of compliance costs (of both insurance and management time). This paper explores legal and commercial structures intended to support effective decommissioning and waste management and examines regulatory and commercial factors affecting the ability of facility operators to utilise internationally available capability. It focusses on: - strategic approaches developed in the UK to address decommissioning and waste management liabilities associated with the UK's first and second generation civil nuclear sites and comparison of those approaches with other jurisdictions with significant decommissioning liabilities; - liability and compliance risks associated with navigating international nuclear liabilities regimes in context of both mobility of decommissioning capability and international waste shipment; and - regulatory issues affecting international availability of waste treatment facilities, including

  1. Optimization of costs versus radiation exposures in decommissioning

    International Nuclear Information System (INIS)

    The estimated worth of decommissioning optimization planning during each phase of the reactor's life cycle is dependent on many variables. The major variables are tabulated and relatively ranked. For each phase, optimization qualitative values (i.e., cost, safety, maintainability, ALARA, and decommissioning considerations) are estimated and ranked according to their short-term and long-term potential benefits. These estimates depend on the quality of the input data, interpretation of that data, and engineering judgment. Once identified and ranked, these considerations form an integral part of the information data base from which estimates, decisions, and alternatives are derived. The optimization of costs and the amount of occupational radiation exposure reductions are strongly interrelated during decommissioning. Realizing that building the necessary infrastructure for decommissioning will take time is an important first step in any decommissioning plan. In addition, the following conclusions are established to achieve optimization of costs and reduced occupational radiation exposures: the assignment of cost versus man-rem is item-specific and sensitive to the expertise of many interrelated disciplines; a commitment to long-term decommissioning planning by management will provide the conditions needed to achieve optimization; and, to be most effective, costs and exposure reduction are sensitive to the nearness of the decommissioning operation. For a new plant, it is best to start at the beginning of the cycle, update continually, consider innovations, and realize full potential and benefits of this concept. For an older plant, the life cycle methodology permits a comprehensive review of the plant history and the formulation of an orderly decommissioning program based on planning, organization, and effort

  2. Decommissioning of Italian nuclear installations: Experience and future plans

    International Nuclear Information System (INIS)

    An overview of decommissioning activities in Italy is presented covering both the Societa Gestione Impianti Nucleari (SOGIN) and ENEA/FN plants.The recent change in decommissioning strategy decided by the Italian Government is presented. Design activities developed to verify the practicability of the new strategy are discussed. The main results of the effort to redefine the national strategy are commented on, and critical items still to be solved are discussed. (author)

  3. Present status of research reactor decommissioning programme in Indonesia

    International Nuclear Information System (INIS)

    At present Indonesia has 3 research reactors, namely the 30 MW MTR-type multipurpose reactor at Serpong Site, two TRIGA-type research reactors, the first one being 1 MW located at Bandung Site and the second one a small reactor of 100 kW at Yogyakarta Site. The TRIGA Reactor at the Bandung Site reached its first criticality at 250 kW in 1964, and then was operated at 1000 kW since 1971. In October 2000 the reactor power was successfully upgraded to 2 MW. This reactor has already been operated for 38 years. There is not yet any decision for the decommissioning of this reactor. However it will surely be an object for the near future decommissioning programme and hence anticipation for the above situation becomes necessary. The regulation on decommissioning of research reactor is already issued by the independent regulatory body (BAPETEN) according to which the decommissioning permit has to be applied by the BATAN. For Indonesia, an early decommissioning strategy for research reactor dictates a restricted re-use of the site for other nuclear installation. This is based on high land price, limited availability of radwaste repository site, and other cost analysis. Spent graphite reflector from the Bandung TRIGA reactor is recommended for a direct disposal after conditioning, without any volume reduction treatment. Development of human resources, technological capability as well as information flow from and exchange with advanced countries are important factors for the future development of research reactor decommissioning programme in Indonesia. (author)

  4. Research and considerations of radiation control in decommissioning

    International Nuclear Information System (INIS)

    In Oarai Engineering Center of Japan Nuclear Cycle Development Institute, decommissioning of nuclear facilities will be expected in future. The results of preceding JPDR decommissioning were researched and the radiation control in decommissioning was examined. The principles and technology necessary for radiation control in decommissioning were arranged. The radiation control in decommissioning seems to be on extension line of daily radiological work control. Noticing points are the control of exposure dose with disassembly of high radiological equipment, the surface contamination measurement of building disassembly waste which large arises and the radioactivity measurement of activated material. When high radiological equipment is disassembled, the measures which reduce the exposure in the remote manipulation are taken. The total radiation protection program including the control of exposure dose in preparedness stage must be decided. Much time and personnel are required, when surface contamination of waste arisen in the building disassembly was measured by surveymeters. Therefore, it is necessary to rationalize the measurement using automatic inspection equipment with large detection area. This type equipment has results which effectively fulfilled the function in the decommissioning of JPDR. It is possible to product the equipment in the combination of existing technology. (author)

  5. 2010 Status of Uranium Conversion Plant Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, D. S.; Lee, K. I.; Choi, Y. D.; Chung, U. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    The Uranium Conversion Plant (UCP) was used to manufacture 100 tons of UO{sub 2}. This paper introduced briefly decommissioning activities in the first half year of 2010. powder for the Wolsong-1 CANDU reactor. The conversion plant has been shut down and minimally maintained for the prevention of a contamination by a deterioration of the equipment. The conversion plant has building area of 2916 m2 and two main conversion processes. ADU (Ammonium Di-Uranate) and AUC (Ammonium Uranyl Carbonate) process are installed in the backside and the front side of the building, respectively. Conversion plant has two lagoons, which is to store all wastes generated from the plant operation. Sludge wastes stored 150m3 and 100m3 in Lagoon 1 and 2, respectively. Main compounds of sludge are ammonium nitrate, sodium nitrate, calcium nitrate, and calcium carbonate. In 2000, the decommissioning of the plant was finally decided upon and a decommissioning program was launched to complete by 2010. In the middle of 2004, decommissioning program obtained the approval of regulatory body and decommissioning activities started. The scope of the project includes the removal of all equipment and the release of the building for re-use. The project is scheduled to be completed at the end of 2010 with a total budget of 10.9 billion This paper introduced briefly decommissioning activities in the first half year of 2010

  6. BCD: a wiki-based decommissioning knowledge management tool

    International Nuclear Information System (INIS)

    Knowledge management allows decommissioning stakeholders to take advantage of past experience (in terms of efficiency, quality, safety, cost, etc.), avoid repeating previous errors, and identify good ideas and practices. It is usually broken down into three processes: collecting information, supplementing and enriching it, and making it available to all decommissioning stakeholders. The CEA has been collecting and centralizing data for many years: the first qualitative assessment of operational experience began in 1991. However, the documents collected were not always relevant for this assessment and, for lack of enrichment and distribution, were generally not used to a significant extent. In order to take advantage of the existing and future body of knowledge and to share this knowledge among decommissioning stakeholders, the CEA decommissioning review unit decided to develop an intranet site known as BCD (from the French acronym for Central Decommissioning Database) using the same wiki technology as the collaborative web encyclopedia, Wikipedia. The objective of BCD is to develop a decommissioning encyclopedia comprising definitions and terminology, the regulatory framework, the lessons of experience with technical or contractual projects, guidelines, statements of results, etc. This article describes BCD and its potential, together with the results observed to date and its prospects for future development. (authors)

  7. BCD: a wiki-based decommissioning knowledge management tool

    Energy Technology Data Exchange (ETDEWEB)

    Fontaine, V.; Coudouneau, L.; Goursaud, V. [CEA Marcoule (DEN/MAR/DPAD/SECAD), 30 (France)

    2008-07-01

    Knowledge management allows decommissioning stakeholders to take advantage of past experience (in terms of efficiency, quality, safety, cost, etc.), avoid repeating previous errors, and identify good ideas and practices. It is usually broken down into three processes: collecting information, supplementing and enriching it, and making it available to all decommissioning stakeholders. The CEA has been collecting and centralizing data for many years: the first qualitative assessment of operational experience began in 1991. However, the documents collected were not always relevant for this assessment and, for lack of enrichment and distribution, were generally not used to a significant extent. In order to take advantage of the existing and future body of knowledge and to share this knowledge among decommissioning stakeholders, the CEA decommissioning review unit decided to develop an intranet site known as BCD (from the French acronym for Central Decommissioning Database) using the same wiki technology as the collaborative web encyclopedia, Wikipedia. The objective of BCD is to develop a decommissioning encyclopedia comprising definitions and terminology, the regulatory framework, the lessons of experience with technical or contractual projects, guidelines, statements of results, etc. This article describes BCD and its potential, together with the results observed to date and its prospects for future development. (authors)

  8. Final generic environmental impact statement on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

  9. Relationship between characteristics of fan-delta sandstone bodies and in-situ leachable sandstone-type uranium mineralization

    International Nuclear Information System (INIS)

    Like normal deltas, fan-deltas are composed of three parts, i.e., fan-delta plain, fan-delta front and pre-fin-delta, In-situ leachable uranium deposits are commonly distributed along the margins of in-land basins. The author analyzes the possible relationship between the basic characteristics of fan-delta sandstone bodies and uranium mineralization. Two examples, e.g., the fan delta depositional systems in the eastern part of Jungger basin and the southern part of Yili basin, are given to illustrate the fan-delta vertical sequence and planar distribution of sedimentary facies. It has been pointed out that the braided channel sandstone bodies on delta plain, sub-aqueous distributional channel sandstone bodies and delta front sandstone bodies may be the favourable host rocks for in-situ leachable sandstone uranium deposits

  10. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  11. In Situ Flash Pyrolysis of Straw

    DEFF Research Database (Denmark)

    Bech, Niels

    In-Situ Flash Pyrolysis of Straw Ph.D. dissertation by Niels Bech Submitted: April 2007. Supervisors: Professor Kim Dam-Johansen, Associate Professor Peter Arendt Jensen Erfaringerne med forbrænding af halm opnået gennem et årti har vist, at en proces der kan koncentrere energien på marken, fjerne...

  12. In Situ TEM Creation of Nanowire Devices

    DEFF Research Database (Denmark)

    Alam, Sardar Bilal

    Integration of silicon nanowires (SiNWs) as active components in devices requires that desired mechanical, thermal and electrical interfaces can be established between the nanoscale geometry of the SiNW and the microscale architecture of the device. In situ transmission electron microscopy (TEM),...

  13. Carcinoma in situ in the testis

    DEFF Research Database (Denmark)

    Rørth, M; Rajpert-De Meyts, E; Andersson, L;

    2000-01-01

    Carcinoma in situ (CIS) of the testis is a common precursor of germ-cell tumours in adults and adolescents, with the exception of spermatocytic seminoma. This article reviews existing knowledge on the pathobiology, genetic aspects and epidemiology of CIS, discusses current hypotheses concerning...

  14. In situ-toughened silicon carbide

    International Nuclear Information System (INIS)

    A new processing strategy based on atmospheric pressure sintering is presented for obtaining dense SiC-based materials with microstructures consisting of (1) uniformly distributed elongate-shaped α-SiC grains and (2) relatively high amounts (20 vol%) of second-phase yttrium aluminum garnet (YAG). This strategy entails the sintering of β-SiC powder doped with α-SiC, Al2O3, and Y2O3. The Al2O3 and Y2O3 aid in the liquid-phase sintering of SiC and form in situ YAG, which has a significant thermal expansion mismatch with SiC. During a subsequent grain-growth heat treatment, it is postulated that the α-SiC ''seeds'' assist in controlling in situ growth of the elongated α-SiC grains. The fracture pattern in the in situ-toughened SiC is intergranular with evidence of copious crack-wake bridging, akin to toughened Si3N4 ceramics. The elongate nature of the α-SiC grains, together with the high thermal-residual stresses in the microstructure, enhance the observed crack-wake bridging. This bridging accounts for a measured twofold increase in the indentation toughness of this new class of in situ-toughened SiC relative to a commercial SiC

  15. Parametric melting studies for in situ vitrification

    International Nuclear Information System (INIS)

    This report describes a series of simulation studies which examine heat conduction and electric heating during in situ vitrification (ISV). The simulation studies determine the effects of soil parameter changes on the ISV process. Changes in heat capacity, thermal conductivity and electrical conductivity are considered. The results of these studies provide a basis for experimental measurement accuracy requirements

  16. Unannounced in situ simulation of obstetric emergencies

    DEFF Research Database (Denmark)

    Sorensen, Jette Led; Lottrup, Pernille; van der Vleuten, Cees;

    2014-01-01

    AIM: To describe how unannounced in situ simulation (ISS) was perceived by healthcare professionals before and after its implementation, and to describe the organisational impact of ISS. STUDY DESIGN: Ten unannounced ISS involving all staff were scheduled March-August 2007. Questionnaire surveys ...

  17. In situ viscometry by optical trapping interferometry

    DEFF Research Database (Denmark)

    Guzmán, C.; Flyvbjerg, Henrik; Köszali, R.;

    2008-01-01

    We demonstrate quantitative in situ viscosity measurements by tracking the thermal fluctuations of an optically trapped microsphere subjected to a small oscillatory flow. The measured power spectral density of the sphere's positions displays a characteristic peak at the driving frequency of the f...

  18. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    International Nuclear Information System (INIS)

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  19. In Situ Cleanable Alternative HEPA Filter Media

    International Nuclear Information System (INIS)

    The Westinghouse Savannah River Company, located at the Savannah River Site in Aiken, South Carolina, is currently testing two types of filter media for possible deployment as in situ regenerable/cleanable High Efficiency Particulate Air (HEPA) filters. The filters are being investigated to replace conventional, disposable, glass-fiber, HEPA filters that require frequent removal, replacement, and disposal. This is not only costly and subjects site personnel to radiation exposure, but adds to the ever-growing waste disposal problem. The types of filter media being tested, as part of a National Energy Technology Laboratory procurement, are sintered nickel metal and ceramic monolith membrane. These media were subjected to a hostile environment to simulate conditions that challenge the high-level waste tank ventilation systems. The environment promoted rapid filter plugging to maximize the number of filter loading/cleaning cycles that would occur in a specified period of time. The filters were challenged using nonradioactive simulated high-level waste materials and atmospheric dust; materials that cause filter pluggage in the field. The filters are cleaned in situ using an aqueous solution. The study found that both filter media were insensitive to high humidity or moisture conditions and were easily cleaned in situ. The filters regenerated to approximately clean filter status even after numerous plugging and in situ cleaning cycles. Air Techniques International is conducting particle retention testing on the filter media at the Oak Ridge Filter Test Facility. The filters are challenged using 0.3-mm di-octyl phthalate particles. Both the ceramic and sintered media have a particle retention efficiency > 99.97%. The sintered metal and ceramic filters not only can be cleaned in situ, but also hold great potential as a long life alternative to conventional HEPA filters. The Defense Nuclear Facility Safety Board Technical Report, ''HEPA Filters Used in the Department of

  20. The Reuse of Decommissioned Facilities and Sites as an Emerging Means to Alleviate the Decommissioning Burden and its Potential Applications within IAEA's International Decommissioning Network

    International Nuclear Information System (INIS)

    Around the world, but particularly in developing Member States, there are disused nuclear facilities or those approaching the end of their useful lives, for which appropriate decommissioning steps have not been taken, primarily due to limited technical and financial resources or competing priorities. One way of alleviating the financial and social burden associated with the final shutdown and decommissioning of nuclear facilities is the redevelopment of decommissioned facilities and sites for new, productive uses, either nuclear or non-nuclear. Sustainable development implies economic development with maintenance of social and community integrity. This objective can best be served by the sensitive redevelopment of sites to provide continuity of employment and new productive activity. Finally, experience to date with redevelopment both inside and outside the nuclear field suggests that successful engagement of the stakeholders can be a key success factor in promoting outcomes which are both profitable for the operator and recognised as responsible and worthwhile by the wider community. Following a generic discussion on factors and issues inherent to the re-development of decommissioned sites, this paper expands on several examples. It is noted that experience from the non-nuclear industrial sector is much more extensive than from the nuclear sector, and lessons from this sector should not be neglected. Many of world's nuclear facilities are small and widely distributed geographically, e.g. ∼300 aging or shut-down research reactors. Requests for assistance to address this issue from Member States exceed the capability of IAEA (and others) to deliver. However, integrating individual initiative into a designed-for-purpose network may compensate for these limitations. A new IAEA initiative amongst organizations from both potential 'donor' and 'recipient' Member States has taken the form of an 'International Decommissioning Network (IDN)'. The objectives of the IDN are

  1. Contemporary management of ductal carcinoma in situ and lobular carcinoma in situ.

    Science.gov (United States)

    Obeng-Gyasi, Samilia; Ong, Cecilia; Hwang, E Shelley

    2016-06-01

    The management of in situ lesions ductal carcinoma in situ (DCIS) and lobular carcinoma in situ (LCIS) continues to evolve. These diagnoses now comprise a large burden of mammographically diagnosed cancers, and with a global trend towards more population-based screening, the incidence of these lesions will continue to rise. Because outcomes following treatment for DCIS and LCIS are excellent, there is emerging controversy about what extent of treatment is optimal for both diseases. Here we review the current approaches to the diagnosis and treatment of both DCIS and LCIS. In addition, we will consider potential directions for future management of these lesions. PMID:27197512

  2. In Situ Remediation Integrated Program: Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed.

  3. In Situ Remediation Integrated Program: Technology summary

    International Nuclear Information System (INIS)

    The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed

  4. An overview of U.S. decommissioning experience -- A basic introduction

    International Nuclear Information System (INIS)

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community

  5. An overview of U.S. decommissioning experience -- A basic introduction

    Energy Technology Data Exchange (ETDEWEB)

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  6. Mobile workstation for decontamination and decommissioning operations

    International Nuclear Information System (INIS)

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D ampersand D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D ampersand D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D ampersand D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D ampersand D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility

  7. Decontamination and Decommissioning Equipment Tracking System (DDETS)

    International Nuclear Information System (INIS)

    At the request of the Department of Energy (DOE)(EM-50), the Scientific Computing Unit developed a prototype system to track information and data relevant to equipment and tooling removed during decontamination and decommissioning activities. The DDETS proof-of-concept tracking system utilizes a one-dimensional (1D) and two-dimensional (2D) bar coding technology to retain and track information such as identification number, manufacturer, requisition information, and various contaminant information, etc. The information is encoded in a bar code, printed on a label and can be attached to corresponding equipment. The DDETS was developed using a proven relational database management system which allows the addition, modification, printing, and deletion of data. In addition, communication interfaces with bar code printers and bar code readers were developed. Additional features of the system include: (a) Four different reports available for the user (REAPS, transaction, and two inventory), (b) Remote automated inventory tracking capabilities, (c) Remote automated inventory tracking capability (2D bar codes allow equipment to be scanned/tracked without being linked to the DDETS database), (d) Edit, update, delete, and query capabilities, (e) On-line bar code label printing utility (data from 2D bar codes can be scanned directly into the data base simplifying data entry), and (f) Automated data backup utility. Compatibility with the Reportable Excess Automated Property System (REAPS) to upload data from DDETS is planned

  8. Environmental Development Plant (EDP): decontamination and decommissioning

    International Nuclear Information System (INIS)

    Radioactively contaminated facilities, equipment, materials, and land that are no longer useful or needed for a nuclear purpose are candidates for decontamination and decommissioning (D/D). Following D/D, intrinsic values can be salvaged and land returned to other desired uses. There are several hundred individual facilities which are located on ERDA Reservations or which have been assigned to ERDA for management and D/D action. Included are facilities used for the production of special nuclear materials, for nuclear energy R and D, and for the testing of nuclear devices. Many of the facilities were operated or utilized by ERDA's predecessor agencies. Also included are certain privately-owned sites and tailings of uranium mills previously operated by private enterprise. The scope of this EDP does not include D/D of commercial power reactors but the technology and issues described here may be directly applicable to such privately owned facilities. The numbers of nuclear facilities that are candidates for D/D continue to increase as they become obsolescent; consequently, a rapid expansion in the volume of D/D work is projected. R and D programs are needed to guide decisions on where and when D/D should be done, to facilitate the work, and to minimize the near and long term risks to both workers and the public

  9. The decommissioning guide. A practical help for practice?

    International Nuclear Information System (INIS)

    The States Committee for Atomic Energy decided at the June, 4-5, 1996 meeting of its Central Commission to use the 'Guide for Decommissioning Facilities under Sec. 7 of the German Atomic Energy Act' as a tool representing a collection of legally and technically relevant aspects for planning and executing licensing procedures and government supervisory functions in nuclear decommissioning projects. The test of the Guide was published in the 'Bundesanzeiger', the German Federal Gazette, on November 12, 1996. How this Guide can be of practical help is outlined in the article. Considerable success has been achieved in recent years in decommissioning power reactors and research reactors in the Federal Republic of Germany. This is true both of the technical execution of disassembly and demolition work, and of licensing and supervision under the Atomic Energy Act. The Niederaichbach Nuclear Power Station has been demolished completely, and the site has been cleared for re-use. Decommissioning and disassembly of the Gundremmingen A, MZFR, VAK, FR-2, and KNK II plants proceeds according to schedule. Before the operating permits issued by the authorities of the GDR for the Greifswald and Rheinsberg Nuclear Power Stations expired, the competent authorities in the State of Mecklenburg - Western Pomerania and Brandenburg issued comprehensive decommissioning permits under Sec. 7, Subsec. 3 of the German Atomic Energy Act. Disassembly and dismantling work is in progress. When the Decommissioning Guide was drafted, discussed and written between 1991 and 1996, representatives of all nuclear authorities in those federal states contributed in which the decommissioning projects listed above, and others, were to be regulated. Also the associations of permit holders and operators of nuclear facilities were heard at an early stage. It may be assumed therefore that there has been feedback from practice already in the discussion phase. (orig.)

  10. Development of decommissioning, decontamination and reuse technology for nuclear facilities

    International Nuclear Information System (INIS)

    In this project, the foundation of decommissioning technology through the development of core technologies applied to maintenance and decommissioning of nuclear facility was established. First of all, we developed the key technology such as safety assessment technology for decommissioning work needed at the preparatory stage of decommissioning of the highly contaminated facilities and simultaneous measurement technology of the high-level alpha/beta contamination applicable to the operation and decommissioning of the nuclear facilities. Second, we developed a remotely controlled laser ablation decontamination system which is useful for a removal of fixed contaminants and developed a chemical gel decontamination technology for a removal of non-fixed contaminants during the maintenance and decommissioning works of high radiation hot cells which have been used for a recycling or treatment of spent fuels. Third, we developed a volume reduction and self-disposal technology for dismantled concrete wastes. Also, the technology for volume reduction and stabilization of the peculiar wastes(HEPA filter and organic mixed wastes), which have been known to be very difficult to treat and manage, generated from the high radioactive facilities in operation, improvement and repair and under decommissioning was developed. Finally, this research project was developed a system for the reduction of radiotoxicity of several uranium mixtures generated in the front- and back-end nuclear fuel cycles with characteristics of highly enhanced proliferation-resistance and more environmental friendliness, which can make the uranium to be recovered or separated from the mixtures with a high purity level enough for the uranium to be reused and to be classified as C-class level for burial near the surface, and then which result in the much reduction in volume of the uranium mixture wastes

  11. The Practice of Cost Estimation for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. Several approaches are currently being used for decommissioning cost estimations, with an international culture developing in the field. The present cost estimation practice guide was prepared in order to offer international actors specific guidance in preparing quality cost and schedule estimates to support detailed budgeting for the preparation of decommissioning plans, for the securing of funds and for decommissioning implementation. This guide is based on current practices and standards in a number of NEA member countries and aims to help consolidate the practice and process of decommissioning cost estimation so as to make it more widely understood. It offers a useful reference for the practitioner and for training programmes. The remainder of report is divided into the following chapters: - Chapter 2 covers the purpose and nature of decommissioning cost estimates, approaches to cost estimation and the major elements of a cost estimate. - Chapter 3 examines the development of the integrated schedule of the activity-dependent work scope and the determination of the project critical path. - Chapter 4 describes the attributes of a quality assurance programme applicable to cost estimation and the use and cautions of benchmarking the estimate from other estimates or actual costs. - Chapter 5 describes the pyramidal structure of the report, and the scope and content that should be included in the cost study report to ensure consistency and transparency in the estimate underpinnings. - Chapter 6 provides some observations, conclusions and recommendations on the use of this guide

  12. Decontamination and Decommissioning Project for the Nuclear Facilities

    International Nuclear Information System (INIS)

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities

  13. Development of Safety Assessment Code for Decommissioning of Nuclear Facilities

    Science.gov (United States)

    Shimada, Taro; Ohshima, Soichiro; Sukegawa, Takenori

    A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (currently JAEA). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning, and also evaluates the public dose at accidental situations including fire and explosion. As for the public, both the internal and the external doses are calculated by considering inhalation, ingestion, direct radiation from radioactive aerosols and radioactive depositions, and skyshine radiation from waste containers. For external dose for workers, the dose rate from contaminated components and structures to be dismantled is calculated. Internal dose for workers is calculated by considering dismantling conditions, e.g. cutting speed, cutting length of the components and exhaust velocity. Estimation models for dose rate and staying time were verified by comparison with the actual external dose of workers which were acquired during JPDR decommissioning project. DecDose code is expected to contribute the safety assessment for decommissioning of nuclear facilities.

  14. Decommissioning Combustible Waste Treatment using Oxygen-Enriched Incinerator

    International Nuclear Information System (INIS)

    The aim of the paper is current status of treatment for the decommissioning combustible waste in KAERI and for the purpose of the volume reduction and clearance for decommissioning combustible wastes generated by the decommissioning projects. The incineration technology has been selected for the treatment of combustible wastes. About 34 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. Temperature, pressure of major components, stack gas concentration, i. e., SOx, NOx, CO, CO2 and HCl, and the residual oxygen were measured. Measured major parameters during normal operation were sustained on a stable status within a criteria operation condition. Oxygen enriched air, 22vol. % (dry basis) was used for stable incineration. The volume reduction ratio has achieved about 1/117. The incineration with decommissioning radioactive combustible waste is possible with moderate oxygen enrichment of 22 vol.% (dry basis) into the supply air. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas. The pressure, off-gas flow and temperature of major components remained constant within the range specified. The measures gases and particulate materials in stack were considerably below the regulatory limits. The achieved volume reduction ratio through incineration is about 1/117

  15. Estimation and comparability of nuclear facility decommissioning costs

    International Nuclear Information System (INIS)

    Most countries have established requirements for cost estimates and reporting. For nuclear power plants and other commercial facilities, legal requirements include the preparation of a decommissioning plan and associated cost estimates, with periodic updates every three to five years. The most important considerations in ensuring stable and more accurate decommissioning cost estimates include: avoiding changes in project scope, fixing regulatory standards during the planning phase to avoid delays during active decommissioning and ensuring the accurate characterisation of materials and soil. Ultimately, it is difficult to compare cost estimates for entire projects, and the proposed figures should not be taken at face value unless all boundary conditions and assumptions have been made clear; in the end, it would appear that benchmarking the costs of specific activities is preferable to benchmarking those of entire projects. An International Structure for Decommissioning Costing (ISDC) of Nuclear Installations is now available and allows for better comparability of the costs of specific activities. Industry, governments and regulators are invited to make use of the ISDC and to participate in improving guidelines, for example, through the activities of the NEA Working Party on Decommissioning and Dismantling

  16. General Approach and Element for Estimating Decommissioning Cost

    International Nuclear Information System (INIS)

    This paper will briefly introduce the general approach and element for developing the decommissioning cost. The ultimate objective of the estimate is to assure adequate funding for decommissioning. The decommissioning cost estimating is highly dependent on the strategies and cost methodologies. The method most widely adopted internationally in estimating is the bottom-up technique, based on a building block approach known as the WBS. Therefore, cost estimator should consider various approaches and elements of cost estimation to achieve the ascension of accuracy. Cost estimation for the decommissioning of nuclear facilities has tended to vary considerably in format and content reflecting a variety of approaches both within and between countries. These differences do not facilitate the process of reviewing estimates and make comparisons between different estimates more complicated. The joint study of OECD/NEA, IAEA and EU was undertaken to propose a standard itemization of decommissioning costs either directly for the production of cost estimates or for mapping estimates onto a standard, common structure for purposes of comparison

  17. Decommissioning nuclear power plants: a case for external funding

    International Nuclear Information System (INIS)

    In deciding how to finance the decommissioning of nuclear power plants, there are five basic criteria for choosing between internal and external funding methods: (1) the desire for financial assurance, (2) the cost of the assurance, (3) the degree of equity in the recovery program, (4) the program's ability to respond to changes, and (5) the program's adaptability to different utilities. To fulfill its obligations to protect long-term public interests, the Missouri Public Service Commission decided it had to assure, to the maximum extent possible, that sufficient decommissioning funds were available when needed. For this reason, it chose the external funding method. In an external fund, the money currently collected from ratepayers to cover decommissioning costs is placed in an independent trust fund comprised of low-risk investments. The funds and the interest they accrue are available to the utility only at the time of decommissioning (and only for that purpose), thus assuring a certain amount of money will be on-hand to cover decommissioning costs as they arise. Such a fund may prove critical to the financial well-being of the utility, particularly if one considers that the utility would need additional generating facilities to replace the capacity lost through the retirement of its nuclear plant. 3 references

  18. In situ remediation of uranium contaminated groundwater

    International Nuclear Information System (INIS)

    In an effort to develop cost-efficient techniques for remediating uranium contaminated groundwater at DOE Uranium Mill Tailing Remedial Action (UMTRA) sites nationwide, Sandia National Laboratories (SNL) deployed a pilot scale research project at an UMTRA site in Durango, CO. Implementation included design, construction, and subsequent monitoring of an in situ passive reactive barrier to remove Uranium from the tailings pile effluent. A reactive subsurface barrier is produced by emplacing a reactant material (in this experiment - various forms of metallic iron) in the flow path of the contaminated groundwater. Conceptually the iron media reduces and/or adsorbs uranium in situ to acceptable regulatory levels. In addition, other metals such as Se, Mo, and As have been removed by the reductive/adsorptive process. The primary objective of the experiment was to eliminate the need for surface treatment of tailing pile effluent. Experimental design, and laboratory and field preliminary results are discussed with regard to other potential contaminated groundwater treatment applications

  19. Inherently safe in situ uranium recovery

    Science.gov (United States)

    Krumhansl, James L; Brady, Patrick V

    2014-04-29

    An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

  20. In situ health monitoring of piezoelectric sensors

    Science.gov (United States)

    Jensen, Scott L. (Inventor); Drouant, George J. (Inventor)

    2013-01-01

    An in situ health monitoring apparatus may include an exciter circuit that applies a pulse to a piezoelectric transducer and a data processing system that determines the piezoelectric transducer's dynamic response to the first pulse. The dynamic response can be used to evaluate the operating range, health, and as-mounted resonance frequency of the transducer, as well as the strength of a coupling between the transducer and a structure and the health of the structure.

  1. Femtosecond laser in laser in situ keratomileusis

    OpenAIRE

    Salomão, Marcella Q.; Wilson, Steven E.

    2010-01-01

    Flap creation is a critical step in laser in situ keratomileusis (LASIK). Efforts to improve the safety and predictability of the lamellar incision have fostered the development of femtosecond lasers. Several advantages of the femtosecond laser over mechanical microkeratomes have been reported in LASIK surgery. In this article, we review common considerations in management and complications of this step in femtosecond laser–LASIK and concentrate primarily on the IntraLase laser because most p...

  2. In situ determination of salinity by PGNAA.

    Science.gov (United States)

    Borsaru, M; Smith, C; Merritt, J; Aizawa, T; Rojc, A

    2006-05-01

    Salinity is a very important environmental issue all around the world. In many cases salinity was produced from human activities like farming and mining. Different soluble salts contribute to salinity, however, NaCl is the most common salt producing salinity. This work deals with the application of the prompt gamma neutron activation analysis (PGNAA) technique for in situ determination of salinity. The technique is based on the measurement of chlorine, a component of the common salt, by PGNAA. PMID:16448819

  3. In situ determination of salinity by PGNAA

    Energy Technology Data Exchange (ETDEWEB)

    Borsaru, M. [CSIRO Exploration and Mining, P.O. Box 883, Kenmore, Qld. 4069 (Australia)]. E-mail: mihai.borsaru@csiro.au; Smith, C. [CSIRO Exploration and Mining, P.O. Box 883, Kenmore, Qld. 4069 (Australia); Merritt, J. [Anglo Coal (Capcoal Management) Pty. Ltd., PMB, Middlemount. Qld. 4746 (Australia); Aizawa, T. [Suncoh Consultants Co., Ltd, 1-8-9, Kameido, Koto-Ku, Tokyo, 136-8522 (Japan); Rojc, A. [CSIRO Exploration and Mining, P.O. Box 883, Kenmore, Qld. 4069 (Australia)

    2006-05-15

    Salinity is a very important environmental issue all around the world. In many cases salinity was produced from human activities like farming and mining. Different soluble salts contribute to salinity, however, NaCl is the most common salt producing salinity. This work deals with the application of the prompt gamma neutron activation analysis (PGNAA) technique for in situ determination of salinity. The technique is based on the measurement of chlorine, a component of the common salt, by PGNAA.

  4. In situ determination of salinity by PGNAA

    International Nuclear Information System (INIS)

    Salinity is a very important environmental issue all around the world. In many cases salinity was produced from human activities like farming and mining. Different soluble salts contribute to salinity, however, NaCl is the most common salt producing salinity. This work deals with the application of the prompt gamma neutron activation analysis (PGNAA) technique for in situ determination of salinity. The technique is based on the measurement of chlorine, a component of the common salt, by PGNAA

  5. 78 FR 19540 - Dominion Energy Kewaunee, Inc., Kewaunee Power Station Post-Shutdown Decommissioning Activities...

    Science.gov (United States)

    2013-04-01

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Dominion Energy Kewaunee, Inc., Kewaunee Power Station Post- Shutdown Decommissioning Activities... comments on the Kewaunee Power Station (KPS) Post-Shutdown Decommissioning Activities Report...

  6. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Volume 2 comprises six appendices on: facility description; residual radioactivity inventory estimates; description and contamination levels of reference site; derivation of residual contamination levels; decommissioning mode detail; and decommissioning safety assessment details

  7. Assessment methodology applicable to safe decommissioning of Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    The paper contains the results of research activity performed by CITON specialists regarding the assessment methodology intended to be applied to safe decommissioning of the research reactors, developed taking into account specific conditions of the Romanian VVR-S Research Reactor. The Romanian VVR-S Research Reactor is an old reactor (1957) and its Decommissioning Plan is under study. The main topics of paper are as follows: Safety approach of nuclear facilities decommissioning. Applicable safety principles; Main steps of the proposed assessment methodology; Generic content of Decommissioning Plan. Main decommissioning activities. Discussion about the proposed Decommissioning Plan for Romanian Research Reactor; Safety risks which may occur during decommissioning activities. Normal decommissioning operations. Fault conditions. Internal and external hazards; Typical development of a scenario. Features, Events and Processes List. Exposure pathways. Calculation methodology. (author)

  8. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant. [Appendices only

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Volume 2 comprises six appendices on: facility description; residual radioactivity inventory estimates; description and contamination levels of reference site; derivation of residual contamination levels; decommissioning mode detail; and decommissioning safety assessment details.

  9. Overview of decommissioning activities supported by the IAEA: update April 2010

    International Nuclear Information System (INIS)

    In this work author gives the overview of decommissioning activities supported by the IAEA. Some examples of decommissioning of discarded nuclear facilities as well as overview of projects coordinated by the IAEA are given.

  10. In situ soil water extraction: a review.

    Science.gov (United States)

    Weihermüller, L; Siemens, J; Deurer, M; Knoblauch, S; Rupp, H; Göttlein, A; Pütz, T

    2007-01-01

    The knowledge of the composition and fluxes of vadose zone water is essential for a wide range of scientific and practical fields, including water-use management, pesticide registration, fate of xenobiotics, monitoring of disposal from mining and industries, nutrient management of agricultural and forest ecosystems, ecology, and environmental protection. Nowadays, water and solute flow can be monitored using either in situ methods or minimally invasive geophysical measurements. In situ information, however, is necessary to interpret most geophysical data sets and to determine the chemical composition of seepage water. Therefore, we present a comprehensive review of in situ soil water extraction methods to monitor solute concentration, solute transport, and to calculate mass balances in natural soils. We distinguished six different sampling devices: porous cups, porous plates, capillary wicks, pan lysimeters, resin boxes, and lysimeters. For each of the six sampling devices we discuss the basic principles, the advantages and disadvantages, and limits of data acquisition. We also give decision guidance for the selection of the appropriate sampling system. The choice of material is addressed in terms of potential contamination, filtering, and sorption of the target substances. The information provided in this review will support scientists and professionals in optimizing their experimental set-up for meeting their specific goals. PMID:17965376

  11. Human activity and rest in situ.

    Science.gov (United States)

    Roenneberg, Till; Keller, Lena K; Fischer, Dorothee; Matera, Joana L; Vetter, Céline; Winnebeck, Eva C

    2015-01-01

    Our lives are structured by the daily alternation of activity and rest, of wake and sleep. Despite significant advances in circadian and sleep research, we still lack answers to many of the most fundamental questions about this conspicuous behavioral pattern. We strongly believe that investigating this pattern in entrained conditions, real-life and daily contexts-in situ-will help the field to elucidate some of these central questions. Here, we present two common approaches for in situ investigation of human activity and rest: the Munich ChronoType Questionnaire (MCTQ) and actimetry. In the first half of this chapter, we provide detailed instructions on how to use and interpret the MCTQ. In addition, we give an overview of the main insights gained with this instrument over the past 10 years, including some new findings on the interaction of light and age on sleep timing. In the second half of this chapter, we introduce the reader to the method of actimetry and share our experience in basic analysis techniques, including visualization, smoothing, and cosine model fitting of in situ recorded data. Additionally, we describe our new approach to automatically detect sleep from activity recordings. Our vision is that the broad use of such easy techniques in real-life settings combined with automated analyses will lead to the creation of large databases. The resulting power of big numbers will promote our understanding of such fundamental biological phenomena as sleep. PMID:25707281

  12. In situ ion irradiation of zirconium carbide

    Science.gov (United States)

    Ulmer, Christopher J.; Motta, Arthur T.; Kirk, Mark A.

    2015-11-01

    Zirconium carbide (ZrC) is a candidate material for use in one of the layers of TRISO coated fuel particles to be used in the Generation IV high-temperature, gas-cooled reactor, and thus it is necessary to study the effects of radiation damage on its structure. The microstructural evolution of ZrCx under irradiation was studied in situ using the Intermediate Voltage Electron Microscope (IVEM) at Argonne National Laboratory. Samples of nominal stoichiometries ZrC0.8 and ZrC0.9 were irradiated in situ using 1 MeV Kr2+ ions at various irradiation temperatures (T = 20 K-1073 K). In situ experiments made it possible to continuously follow the evolution of the microstructure during irradiation using diffraction contrast imaging. Images and diffraction patterns were systematically recorded at selected dose points. After a threshold dose during irradiations conducted at room temperature and below, black-dot defects were observed which accumulated until saturation. Once created, the defect clusters did not move or get destroyed during irradiation so that at the final dose the low temperature microstructure consisted only of a saturation density of small defect clusters. No long-range migration of the visible defects or dynamic defect creation and elimination were observed during irradiation, but some coarsening of the microstructure with the formation of dislocation loops was observed at higher temperatures. The irradiated microstructure was found to be only weakly dependent on the stoichiometry.

  13. Utilizing Divers in Support of Spent Fuel Basin Closure Subproject

    International Nuclear Information System (INIS)

    A number of nuclear facilities in the world are aging and with this comes the fact that we have to either keep repairing them or decommission them. At the Department of Energy Idaho Site (DOEID) there are a number of facilities that are being decommissioned, but the facilities that pose the highest risk to the large aquifer that flows under the site are given highest priorities. Aging spent nuclear fuel pools at DOE-ID are among the facilities that pose the highest risk, therefore four pools were targeted for decommissioning in Fiscal Year 2004. To accomplish this task the Idaho Completion Project (ICP) of Bechtel BWXT Idaho, LLC, put together an integrated Basin Closure Subproject team. The team was assigned a goal to look beyond traditional practices at the Idaho National Engineering and Environmental Laboratory (INEEL) to find ways to get the basin closure work done safer and more efficiently. The Idaho Completion Project (ICP) was faced with a major challenge--cleaning and preparing aging spent nuclear fuel basins for closure by removing sludge and debris, as necessary, and removing water to eliminate a potential risk to the Snake River Plain Aquifer. The project included cleaning and removing water from four basins. Two of the main challenges to a project like this is the risk of contamination from the basin walls and floors becoming airborne as the water is removed and keeping personnel exposures ALARA. ICP's baseline plan had workers standing at the edges of the basins and on rafts or bridge cranes and then using long-handled tools to manually scrub the walls of basin surfaces. This plan had significant risk of skin contamination events, workers falling into the water, or workers sustaining injuries from the awkward working position. Analysis of the safety and radiation dose risks presented by this approach drove the team to look for smarter ways to get the work done

  14. DEMONSTRATION BULLETIN: IN SITU ELECTROKINETIC EXTRACTION SYSTEM - SANDIA NATIONAL LABORATORIES

    Science.gov (United States)

    Sandia National Laboratories (SNL) has developed an in situ soil remediation system that uses electrokinetic principles to remediate hexavalent chromium-contaminated unsaturated or partially saturated soils. The technology involves the in situ application of direct current to the...

  15. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  16. Decontamination and decommissioning project for the nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning work which begin in latter half of 2001 was gone well in latter half of 2002. Now, 8 laboratories, 10 lead hot cells, and 2 concrete hot cells was dismantled. Wastes produced by decommissioning process were classified with three category. The decontaminatable wastes in the solid radioactive ones will be changed with free release ones. For this, we developed cylindrical rotating pipe decontamination units, ultrasonic ones, and steam jet ones. Test of these units was started in 2002 and they will be using decontamination work in 2003. According to regulation of atomic act 55, the Decommissioning Plan and Environmental Impact Assessment for uranium conversion plant were written out and presented. Basic research for metal wastes decontamination and research for lagoon sludge treatment was carried out.

  17. Research reactor decommissioning experience - concrete removal and disposal -

    International Nuclear Information System (INIS)

    Removal and disposal of neutron activated concrete from biological shields is the most significant operational task associated with research reactor decommissioning. During the period of 1985 thru 1989 Chem-Nuclear Systems, Inc. was the prime contractor for complete dismantlement and decommissioning of the Northrop TRIGA Mark F, the Virginia Tech Argonaut, and the Michigan State University TRIGA Mark I Reactor Facilities. This paper discusses operational requirements, methods employed, and results of the concrete removal, packaging, transport and disposal operations for these (3) research reactor decommissioning projects. Methods employed for each are compared. Disposal of concrete above and below regulatory release limits for unrestricted use are discussed. This study concludes that activated reactor biological shield concrete can be safely removed and buried under current regulations

  18. 77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2012-02-15

    ... COMMISSION Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors AGENCY... ``Decommissioning of Nuclear Power Reactors.'' This guide describes a method NRC considers acceptable for use in... Revision 1 of Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000....

  19. 77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2012-12-19

    ... COMMISSION Standard Format and Content for Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear... Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method... regarding the submission of a post-shutdown decommissioning activities report (PSDAR). DATES:...

  20. 78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

    Science.gov (United States)

    2013-08-14

    ... COMMISSION Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report AGENCY: Nuclear..., 2013, the GPU Nuclear Inc. (GPUN) submitted its Post Shutdown Decommissioning Activity Report (PSDAR... decommissioning activities, schedule, and costs for TMI-2. The NRC is requesting public comments on the...

  1. 26 CFR 1.468A-0T - Nuclear decommissioning costs; table of contents.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; table of contents... electing taxpayer (temporary). (a) In general. (b) Limitation on payments to a nuclear decommissioning fund... rule permitting payments to a nuclear decommissioning fund before receipt of an initial or...

  2. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  3. Decontamination and its role in the Fort St. Vrain decommissioning

    International Nuclear Information System (INIS)

    The full scale decommissioning of a reactor requires the use of a variety of decontamination processes, techniques and equipment. In August of 1992, the decommissioning of the Fort St. Vrain High Temperature Gas-Cooled Reactor (HTGR) was initiated by Public Service Company of Colorado. The Fort St. Vrain Decommissioning Project is being performed by a team comprised of Westinghouse Electric Corporation, Scientific Ecology Group, and MK Ferguson. This project is the largest decommissioning and early dismantlement of a commercially operated reactor in the United States to date. The scope of the project includes decontamination and dismantlement of the Prestressed Concrete Reactor Vessel (PCRV) and decontamination/removal of contaminated plant systems, site cleanup, and a comprehensive final radiation survey. This paper discusses the various types of decontamination equipment, survey instrumentation and techniques used during the Fort St. Vrain Decommissioning Project. Decontamination techniques range from simple methods such as soapy water, high pressure washing, scabbling, strippable paint; to more complicated methods such as remotely operated grit blast equipment used to decontaminate embedded pipe. The parameters necessary to evaluate the cost effectiveness of various decontamination techniques are discussed. Typically this includes consideration of the type and level of contamination, the substrate and surface to be decontaminated, the type and volume of waste generated from the decontamination process, whether the decon will be performed on site or off site, equipment and labor costs, project schedule impact, and the unconditional release criteria that must be achieved. These factors and costs are then compared to the costs associated with the removal, possible volume reduction and final disposal of a particular component or system. The successes and lessons learned during the Fort St. Vrain Decommissioning Project are presented

  4. Overview of International Research Institute for Nuclear Decommissioning (IRID)

    International Nuclear Information System (INIS)

    The International Research Institute for Nuclear Decommissioning (IRID) is an organization that was created as a matter of urgency to upgrade decommissioning technology for the decommissioning of Fukushima Daiichi Nuclear Power Station or carry out rational and effective development of such technology After the accident, decommissioning of Fukushima Daiichi Nuclear Power Station was originally carried out by TEPCO in a proactive way and at its own responsibility. The Ministry of Economy, Trade and Industry and TEPCO had been developing technology that was necessary for that, depending on the needs of the time, by providing research subsidies and contracting out research to related manufacturers and subcontractors. Two years had been passed since the accident, and people have been expressing their opinions that the research on decommissioning should be carried out for a little more long term.. In addition, they insist that they should be aware of the unity and integrity of each technology to make a system that manages entire research. In order to do so, it was decided that related organizations would continue to strengthen their cooperation that are led by the government. IRID was created by the group of 17 companies and organizations specialized in the research development under the idea of making a group towards the common goal based on the Research and Development Partnerships Act. They made IRID for proceeding on the cross-sectional and integrated management by themselves. In the past, only specific organizations had been conducting research. However, by cooperating with foreign countries and making plans for the participation of groups of domestic and foreign that are currently uninvolved, this organization has been discovering new technology while also aiming to support the development of human resources that are related to decommissioning in the long term. Although the organization is only half a year old since the Minister of Economy, Trade and Industry gave

  5. A costing model for offshore decommissioning in California.

    Science.gov (United States)

    Bressler, Andrew; Bernstein, Brock B

    2015-10-01

    California's 27 offshore oil and gas platforms will reach the end of their useful lifetimes sometime in the near future and will require decommissioning. Although existing leases require complete removal of all platforms and associated infrastructure, the underlying laws and regulations have changed in recent years to allow a number of alternative uses after decommissioning. In particular, AB 2503, signed into law in September 2010, provides for a rigs-to-reefs program that allows the state to accept ownership of decommissioned platforms in federal waters. Decisions about whether to remove platforms completely or leave them in place as artificial reefs will depend in part on the relative cost of the 2 options. In this study, we describe the design and use of a mathematical decision model that provides detailed cost estimates of complete and partial removal (to 85 feet below the water line) for California's offshore platforms. The model, PLATFORM, is loaded with Bureau of Safety and Environmental Enforcement (BSEE) and Bureau of Ocean Energy Management (BOEM) costs for complete removal, along with costs for partial removal calculated for this study and estimates of the uncertainty associated with decommissioning cost estimates. PLATFORM allows users to define a wide range of decommissioning and costing scenarios (e.g., number of platforms, choice of heavy lift vessel, shell mound removal, reef enhancement). As a benchmark cost, complete removal of all 27 offshore platforms, grouped into the 7 decommissioning projects defined by the most recent federal cost estimates produced in 2010, would cost an estimated $1.09 billion, whereas partial removal of these platforms, grouped into the same set of projects, would cost $478 million, with avoided costs of $616 million (with minor rounding). PMID:25914378

  6. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  7. On Cost Estimate for Decommissioning of one Isotope Central

    International Nuclear Information System (INIS)

    The main scope of this study has been to calculate the future cost for decommission and dismantling the Isotope central at the Studsvik site using the OMEGA CODE. Detailed empirical information is used in the study for 'bench-marking' purposes, in such cases when there is a need to supplement and correct field data from the industry. In the present study, data has been retrieved and organized such that the estimated costs for decommissioning of the Isotope Central become transparent and reliable. This approach gives a preliminary qualitative indication about the accuracy of the cost estimate delivered by the industry

  8. Radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

    2010-07-15

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  9. Technology demonstrations in the Decontamination and Decommissioning Focus Area

    International Nuclear Information System (INIS)

    This paper describes three large-scale demonstration projects sponsored jointly by the Decontamination and Decommissioning Focus Area (DDFA), and the three US Department of Energy (DOE) Operations Offices that successfully offered to deactivate or decommission (D ampersand D) one of its facilities using a combination of innovative and commercial D ampersand D technologies. The paper also includes discussions on recent technology demonstrations for an Advanced Worker Protection System, an Electrohydraulic Scabbling System, and a Pipe Explorer trademark. The references at the conclusion of this paper should be consulted for more detailed information about the large-scale demonstration projects and recent technology demonstrations sponsored by the DDFA

  10. Safety analysis for the 233-S decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Decommissioning of the 233-S Plutonium Concentration Facility (REDOX) is a proposed expedited response action that is regulated by the Comprehensive Environmental Response Compensation and Liability Act of 1980 and the Hanford Federal Facility Agreement and Consent Order. Due to progressive physical deterioration of this facility, a decontamination and decommissioning plan is being considered for the immediate future. This safety analysis describes the proposed actions involved in this D ampersand D effort; identifies the radioactive material inventories involved; reviews site specific environmental characteristics and postulates an accident scenario that is evaluated to identify resultant effects

  11. Nuclear submarine prototype post core removal decommissioning and life extension

    International Nuclear Information System (INIS)

    Decommissioning of a nuclear plant normally brings it to the end of its life. This paper describes how the initial decommissioning of a nuclear submarine prototype was undertaken, how it was modified and its useful life extended. The Dounreay Submarine Prototype came to the end of critical operation in 1984. This was followed by defuel, decontamination and modification to convert the plant into a facility for the investigation of loss of coolant accidents. Following completion of this investigation, the plant has been used as a primary coolant pump test facility. (Author)

  12. Bacterial colonization of enamel in situ investigated using fluorescence in situ hybridization.

    Science.gov (United States)

    Al-Ahmad, Ali; Follo, Marie; Selzer, Ann-Carina; Hellwig, Elmar; Hannig, Matthias; Hannig, Christian

    2009-10-01

    Oral biofilms are one of the greatest challenges in dental research. The present study aimed to investigate initial bacterial colonization of enamel surfaces in situ using fluorescence in situ hybridization (FISH) over a 12 h period. For this purpose, bovine enamel slabs were fixed on buccal sites of individual splints worn by six subjects for 2, 6 and 12 h to allow biofilm formation. Specimens were processed for FISH and evaluated with confocal laser-scanning microscopy, using probes for eubacteria, Streptococcus species, Veillonella species, Fusobacterium nucleatum and Actinomyces naeslundii. The number of adherent bacteria increased with time and all tested bacterial species were detected in the biofilm formed in situ. The general percentage composition of the eubacteria did not change over the investigated period, but the number of streptococci, the most frequently detected species, increased significantly with time (2 h: 17.7+/-13.8 %; 6 h: 20.0+/-16.6 %; 12 h: 24.7+/-16.1 %). However, < or =1 % of the surface was covered with bacteria after 12 h of biofilm formation in situ. In conclusion, FISH is an appropriate method for quantifying initial biofilm formation in situ, and the proportion of streptococci increases during the first 12 h of bacterial adherence. PMID:19528150

  13. Role of Slovakia within the IAEA Decommissioning Related Activities

    International Nuclear Information System (INIS)

    Slovakia has a long-term experience with the IAEA decommissioning related activities as a recipient of Agency assistance and then as a country offering assistance to others. Background, short 'history' and current status of Slovakian national technical cooperation (TC) projects SLR/4/008 'Robotic Technologies for Decontamination and Decommissioning of the Bohunice A1 NPP' and SLR/3/002 'Management of Radioactive Waste from the A1 Nuclear Power Plant Decommissioning' will be described in paper. The first TC project SLR/4/008 was solved by the main Slovakian counterpart, company VUJE, Inc., from 2001 to 2006. Second TC project SLR/3/002 is ongoing with extension to 2011. Thanks to the implementation of a long-term large-scale 'Project of the A1 NPP Decommissioning - Stage I' (1996-2007), financed by Slovak National Nuclear Account (decommissioning fund), as well as implementation of the IAEA TC national projects a comprehensive know-how in the field of D and D and RAW management was obtained. Moreover, technologies and facilities necessary for implementation of decommissioning and RAW management projects were developed. Thanks to this development Slovakia offers donor assistance to other countries in subjected fields through IAEA TC program. The type and scope of assistance for Armenia, Bulgaria, Egypt, Latvia, Lithuania and The Ukraine is described in the paper. The above-mentioned national projects are not only activities of Slovakia within the IAEA TC program. Regional TC project RER/3/005 'Support in Planning the Decommissioning of Nuclear Power Plants and Research Reactors' has been ongoing from 2007 with accepted extension to 2011. About nine countries from Eastern and Central Europe participate in the project (for the NPPs part) and Slovakia plays the role of LCC (Leading Country Coordinator). On the basis of suggestion of Nuclear Regulatory Authority of the Slovak Republic, VUJE is the coordinator of the regional project. Moreover, Slovakia would be the

  14. Remediation of Site of Decommissioning Research Reactor

    International Nuclear Information System (INIS)

    In the world the most widespread method of soil decontamination consists of removing the contaminated upper layer and sending it for long-term controlled storage. However, implementation of this soil cleanup method for remediation of large contaminated areas would involve high material and financial expenditures, because it produces large amounts of radioactive waste demanding removal to special storage sites. Contaminated soil extraction and cleanup performed right on the spot of remediation activities represents a more advanced and economically acceptable method. Radiological separation of the radioactive soil allows reducing of amount of radwaste. Studies performed during the liquidation of the Chernobyl accident consequences revealed that a considerable fraction of radioactivity is accumulated in minute soil grains. So, the separation of contaminated soil by size fractions makes it possible to extract and concentrate the major share of radioactivity in the fine fraction. Based on these researches water gravity separation technology was proposed by Bochvar Institute. The method extracts the fine fraction from contaminated soil. Studies carried out by Bochvar Institute experts showed that, together with the fine fraction (amounting to 10-20% of the initial soil), this technology can remove up to 85-90% of contaminating radionuclides. The resulting 'dirty' soil fraction could be packaged into containers and removed as radwaste, and decontaminated fractions returned back to their extraction site. Use of radiological and water gravity separations consequently increases the productivity of decontamination facility. Efficiency of this technology applied for contaminated soil cleanup was confirmed in the course of remediation of the contaminated territories near decommissioning research reactor in the Kurchatov Institute. For soil cleaning purposes, a special facility implementing the technology of water gravity separation and radiometric monitoring of soil

  15. TSSM: The in situ exploration of Titan

    Science.gov (United States)

    Coustenis, A.; Lunine, J. I.; Lebreton, J. P.; Matson, D.; Reh, K.; Beauchamp, P.; Erd, C.

    2008-09-01

    The Titan Saturn System Mission (TSSM) mission was born when NASA and ESA decided to collaborate on two missions independently selected by each agency: the Titan and Enceladus mission (TandEM), and Titan Explorer, a 2007 Flagship study. TandEM, the Titan and Enceladus mission, was proposed as an L-class (large) mission in response to ESA's Cosmic Vision 2015-2025 Call. The mission concept is to perform remote and in situ investigations of Titan primarily, but also of Enceladus and Saturn's magentosphere. The two satellites are tied together by location and properties, whose remarkable natures have been partly revealed by the ongoing Cassini-Huygens mission. These bodies still hold mysteries requiring a complete exploration using a variety of vehicles and instruments. TSSM will study Titan as a system, including its upper atmosphere, the interactions with the magnetosphere, the neutral atmosphere, surface, interior, origin and evolution, as well as the astrobiological potential of Titan. It is an ambitious mission because its targets are two of the most exciting and challenging bodies in the Solar System. It is designed to build on but exceed the scientific and technological accomplishments of the Cassini- Huygens mission, exploring Titan and Enceladus in ways that are not currently possible (full close-up and in situ coverage over long periods of time for Titan, several close flybys of Enceladus). One overarching goal of the TSSM mission is to explore in situ the atmosphere and surface of Titan. In the current mission architecture, TSSM consists of an orbiter (under NASA's responsibility) with a large host of instruments which would perform several Enceladus and Titan flybys before stabilizing in an orbit around Titan alone, therein delivering in situ elements (a Montgolfière, or hot air balloon, and a probe/lander). The latter are being studied by ESA. The balloon will circumnavigate Titan above the equator at an altitude of about 10 km for several months. The

  16. Detection of denitrification genes by in situ rolling circle amplification - fluorescence in situ hybridization (in situ RCA-FISH) to link metabolic potential with identity inside bacterial cells

    DEFF Research Database (Denmark)

    Hoshino, Tatsuhiko; Schramm, Andreas

    2010-01-01

    A target-primed in situ rolling circle amplification (in situ RCA) protocol was developed for detection of single-copy genes inside bacterial cells and optimized with Pseudomonas stutzeri, targeting nitrite and nitrous oxide reductase genes (nirS and nosZ). Two padlock probes were designed per gene...... as Candidatus Accumulibacter phosphatis by combining in situ RCA-FISH with 16S rRNA-targeted FISH. While not suitable for quantification because of its low detection frequency, in situ RCA-FISH will allow to link metabolic potential with 16S rRNA (gene)-based identification of single microbial cells....

  17. Chemical decontamination for decommissioning purposes. (Vigorous decontamination tests of steel samples in a special test loop)

    International Nuclear Information System (INIS)

    The aim of the research activities described was to develop vigorous decontamination techniques for decommissioning purposes, taking into account the cost of treatment of the radwaste, to achieve possibly unrestricted release of the treated components, and to obtain know-how for in situ hard decontamination. The decontamination procedures for strong decontamination have been optimized in static and dynamic tests (DECO-loop). The best values have been found for: (i) hydrochloric acid: 4 to 5% vol. at low temperature, 0.7 to 1% vol. at high temperature (800C); (ii) hydrofluoric plus nitric acid: 1.5% vol. HF + 5% vol. HNO3 at low temperature; 0.3 to 0.5% vol. HF + 2.5 to 5% vol. HNO3 at high temperature. High flow rates are not necessary, but a good re-circulation of the solution is needed. The final contamination levels, after total oxide removal, are in accordance with limits indicated for unrestricted release of materials in some countries. The arising of the secondary waste is estimated. Decontamination of a 10 m2 surface would typically produce 0.5 to 3.0 kg of dry waste, corresponding to 1.6 to 10 kg of concrete conditioned waste

  18. Real-time remote sensing driven river basin modeling using radar altimetry

    DEFF Research Database (Denmark)

    Pereira Cardenal, Silvio Javier; Riegels, Niels; Bauer-Gottwein, Peter;

    2011-01-01

    Many river basins have a weak in-situ hydrometeorological monitoring infrastructure. However, water resources practitioners depend on reliable hydrological models for management purposes. Remote sensing (RS) data have been recognized as an alternative to in-situ hydrometeorological data in remote...

  19. Establishment the code for prediction of waste volume on NPP decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Cho, W. H.; Park, S. K.; Choi, Y. D.; Kim, I. S.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In practice, decommissioning waste volume can be estimated appropriately by finding the differences between prediction and actual operation and considering the operational problem or supplementary matters. So in the nuclear developed countries such as U.S. or Japan, the decommissioning waste volume is predicted on the basis of the experience in their own decommissioning projects. Because of the contamination caused by radioactive material, decontamination activity and management of radio-active waste should be considered in decommissioning of nuclear facility unlike the usual plant or facility. As the decommissioning activity is performed repeatedly, data for similar activities are accumulated, and optimal strategy can be achieved by comparison with the predicted strategy. Therefore, a variety of decommissioning experiences are the most important. In Korea, there is no data on the decommissioning of commercial nuclear power plants yet. However, KAERI has accumulated the basis decommissioning data of nuclear facility through decommissioning of research reactor (KRR-2) and uranium conversion plant (UCP). And DECOMMIS(DECOMMissioning Information Management System) was developed to provide and manage the whole data of decommissioning project. Two codes, FAC code and WBS code, were established in this process. FAC code is the one which is classified by decommissioning target of nuclear facility, and WBS code is classified by each decommissioning activity. The reason why two codes where created is that the codes used in DEFACS (Decommissioning Facility Characterization management System) and DEWOCS (Decommissioning Work-unit productivity Calculation System) are different from each other, and they were classified each purpose. DEFACS which manages the facility needs the code that categorizes facility characteristics, and DEWOCS which calculates unit productivity needs the code that categorizes decommissioning waste volume. KAERI has accumulated decommissioning data of KRR

  20. Computer Aided in situ Cognitive Behavioral Therapy

    DEFF Research Database (Denmark)

    Chongtay, Rocio A.; Hansen, John Paulin; Decker, Lone

    2006-01-01

    . One of the most common and successfully used treatments for phobic conditions has been Cognitive Behavioral Therapy (CBT), which helps people learn to detect thinking patterns that trigger the irrational fear and to replace them with more realistic ideas. The health and financial impacts in society...... presented here is being designed in a modular and scalable fashion. The web-based module can be accessed anywhere any time from a PC connected to the internet and can be used alone or as supplement for a location-based module for in situ gradual exposure therapy....

  1. Ekstrauterin graviditet med gestagenspiral in situ

    DEFF Research Database (Denmark)

    Mikkelsen, Mette Schou; Bor, Isil Pinar; Højgaard, Astrid Ditte

    2010-01-01

    The levonorgestrel-releasing intrauterine device (IUD) (Mirena) is a frequently used and effective method of contraception, with a Pearl index of 0.1. The ectopic pregnancy rate is 0.02 per 100 woman-years. Special attention is needed in situations where pregnancy is detected with a levonorgestrel......-releasing IUD in situ, because almost two thirds of these pregnancies are ectopic. We describe one of these rare cases of ectopic pregnancy in a woman aged 37 years, who was admitted to hospital with abdominal pain and vaginal bleeding....

  2. Polypropylene/graphite nanocomposites by in situ polymerization; Nanocompositos polipropileno/grafite via polimerizacao in situ

    Energy Technology Data Exchange (ETDEWEB)

    Milani, Marceo A.; Galland, Giselda B., E-mail: griselda@iq.ufrgs.br [Instituto de Quimica, UFRGS, Porto Alegre, RS (Brazil); Quijada, Raul [Universidade de Chile, Santiago (Chile). Centro de Ciencias de los Materiales; Basso, Nara R.S. [Fac. de Quimica, PUCRS, Porto Alegre, RS (Brazil)

    2011-07-01

    This work presents the synthesis of nanocomposites of polypropylene/graphite by in situ polymerization using metallocene catalyst and graphene nanosheets. Initially was analyzed which of the metallocene catalysts rac-Et(Ind){sub 2}ZrCl{sub 2} or rac-Me{sub 2}Si(Ind){sub 2}ZrCl{sub 2} produces polypropylene with mechanical properties more relevant. Then it were performed the in situ polymerization reactions to obtain the nanocomposites. The polymeric materials were characterized by XRD, DSC, GPC and DMTA. (author)

  3. Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

    International Nuclear Information System (INIS)

    This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90Sr followed by long-lived nuclides 129I and 108mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

  4. Design Lessons Drawn from the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    This report provides an updated compilation incorporating the most recent lessons learned from decommissioning and remediation projects. It is intended as a 'road map' to those seeking to apply these lessons. The report presents the issues in a concise and systematic manner, along with practical, thought-provoking examples. The most important lessons learned in recent years are organized and examined to enable the intended audience to gauge the importance of this aspect of the planning for new nuclear facilities. These will be of special interest to those seeking to construct nuclear facilities for the first time. In Sections 1 and 2, the current situation in the field of decommissioning is reviewed and the relevance and importance of beneficial design features is introduced. A more detailed review of previous and current lessons learned from decommissioning is given in Section 3 where different aspects of the decommissioning process are analysed. From this analysis beneficial design features have been extracted and identified in Section 4 which includes two comprehensive tables where brief descriptions of the features are summarized and responsibilities are identified. Conclusions and key design features and key recommendations are given in Section 5. Two Annexes are included to provide lessons from past projects and past experience and to record notes and extracts taken from a comprehensive list of publications listed in the References on page 47.

  5. Review of decontamination techniques in relation to decommissioning

    International Nuclear Information System (INIS)

    A review is presented of decontamination procedures currently in use in relation to the decommissioning of nuclear plant. Contributions were invited from Canada, France, Japan, Sweden, USA and the UK and are appended. They present an overview of the techniques employed in each country and identify areas of future development. (author)

  6. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    Energy Technology Data Exchange (ETDEWEB)

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  7. Decommissioning: a success story in quest of new achievements

    International Nuclear Information System (INIS)

    Full text: Since 1999 we see that the emphasis has shifted to provide increased attention to the general governance of decommissioning. The inventorying of liabilities, the establishment and running of funds, the formulation of proportionate regulation have taken a more central stage. There has been much talk about strategy as well, with some nations like Italy and France changing their stance and opting for prompt decommissioning. The NEA, IAEA, and EC have overlapping membership but distinct mandates. Our programmes do receive a certain amount of co-ordination - through agreements and discussion amongst secretariats and through participation in each other activities. Co-ordination, however, starts at home, in the member countries, and in the end it is also in the hands of many in this audience. NEA is open for suggestions. Overall we can conclude that much has been done in the field of decommissioning, especially in terms of techniques and in setting up institutional frameworks, and especially so in the more mature nuclear programmes. Depending on national circumstances both fine and less-fine tuning may be needed, however, in preparing for the bigger challenges that lie ahead due to the number of projects to be taken on and the magnitude of those projects in terms of both size and time. We do start on the solid footing provided by the work carried out so far, but the quest for new decommissioning achievements is still on. (authors)

  8. Applying laser technology to decommissioning for nuclear power plant

    Science.gov (United States)

    Saishu, Sadanori; Abe, Seiji; Inoue, T.

    2000-01-01

    Laser technology has much possibility to accomplish nuclear facility decommissioning effective and the laser application to cutting technique and decontamination technique is considered in Japan. Nuclear Power Engineering Corporation had developed CO laser for cutting technique, and had developed YAG laser for decontamination.

  9. Decommissioning of nuclear reactor fuel channels using laser technology

    Science.gov (United States)

    Panchenko, Vladislav Y.; Zabelin, Alexandre M.; Slepokon, Yu. I.; Ryahin, V. M.; Kuznetsov, P. P.; Panasyuk, V. F.; Korotchenko, A. V.; Kislov, V. S.; Loktev, S. V.

    2000-07-01

    Decommissioning of nuclear reactors using laser remote dismounting and welding was experimentally proved at a nuclear reactor of Kursk Nuclear Power Plant. The main reason of laser beam application in this case is the marked decrease of radioactive exposure of the service personnel. The use of a high-power laser beam provided for laser cutting and welding processes realization at a distance up to 35 m between the laser and the workstation placed behind a radiation shield. By application of laser cutting gas and dust contamination is ten-fold decreased. Some results of decommissioning application of a stationary laser workstation based upon a 5 kW fast-transverse-flow discharge CW CO2 laser TL-5M installed at a nuclear reactor site are presented. A special high-beam- quality model of the laser was developed to satisfy the needs of decommissioning. Laser cutting process was applied to decommissioning of fuel channels (FC) of RBMK-1000 reactor, after their extractor from the reactor active zone during the procedure of channels replacement.

  10. Using virtual reality technology for decommissioning and outage planning

    International Nuclear Information System (INIS)

    The VR Decom. Tool is a decommissioning, planning, and training tool. It is not yet in use, but appropriate technology has been identified to develop such a tool The tool is intended to be used as an interactive virtual mock-up of a process plant to plan and practice decommissioning activities. The tool will be able to create or import existing CAD drawing to be visualised in an interactive Virtual Reality (VR) environment, with links to data bases containing useful information about all the process components for planning the decommissioning. The most use of the tool is foreseen to be in areas that have limited access, such as, radioactive or hazardous. The main advantages are summarised below: (1) virtual mock-up for visualisation of non-accessible areas to plan and provide training for decommissioning procedures, (2) visualisation of three dimensional radiation maps for As Low As Reasonably Achievable (A.L.A.R.A.) staff dose management, (3) raining of special tele-operations procedures, (4) special tools prototyping and testing, (5) information access and team vision sharing. (author)

  11. Development of decontamination, decommissioning and environmental restoration technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Jik; Kwon, H. S.; Kim, G. N. and others

    1999-03-01

    Through the project of 'Development of decontamination, decommissioning and environmental restoration technology', the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

  12. Economic consequences of premature decommissioning of a nuclear power plant

    International Nuclear Information System (INIS)

    Models of the fuel and energy system and the unified electric power system are used to predict the economic consequences of the premature decommissioning of nuclear power plants in Russia. The components of the expenditures considered were capital investments for converting heat and power plants, additional capital investments for development of a fuel base and transportation of fuel and electricity, expenditures for improving the safety of nuclear power plants, and additional expenditures on fossil fuel. After model calculations were completed, results were compared for accelerated decommissioning and base variants and the difference of the indicators and additional expenditures were found. Conclusions drawn from the modeling results were: (1) premature decommissioning of BBER-440 and RBMK-1000 reactors will require capital investments and fuel expenditures which exceed estimates made by the European and World Banks; and (2) program implementation may be economically unfeasible; it may be more realistic to decommission separate nuclear power plants with the least reliable reactors and upgrade safety of the remaining plants. 9 refs., 5 tabs

  13. From planning to decommissioning: Life of a nuclear power plant

    International Nuclear Information System (INIS)

    When a facility no longer serves a useful social or economic purpose, it needs to be dismantled and the site made available for other uses. The six phases (Planning; Physical & Radiological Characterization; Decontamination; Dismantling & Demolition; Preparation for Reuse; Final Survey & Release from Regulatory Control) of steps in the decommissioning process are highlighted

  14. Evolution or revolution? Dismantling the FASB standard on decommissioning costs

    International Nuclear Information System (INIS)

    The Financial Standards and Accounting Board has issued for comment a draft of proposed financial accounting standards pertaining to nuclear plant decommissioning. This article examines the proposed rules and discusses alternate approaches in those areas in which the author takes issue with the FASB draft

  15. Experience Review on Dismantling Procedure for American Decommissioned NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyosub; Son, Daesun; Lee, Jaeyong; Kim, Kyungmin; Kim, Yong-soo [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    According to IAEA, the number of shutdown NPPs is totally 150 globally. In Korea, there are 23 operating NPPs and 5 NPPs under construction. But Korea has no shutdown NPP and has no experience on decommissioning commercial reactor so far except for decommissioning research reactor, TRIGA MARK-3. Based on the NPP lifetime as a 45 years, it is expected that 440 NPPs in the world and 16 NPPs in Korea will come to an end of their lifetime until 2060. In this study, decontamination and decommissioning (D and D) procedure of shutdown NPPs in US concentrated on dismantling of reactor vessel and its internals is investigated. Detailed activation analysis on primary system should be followed for safe D and D activities. However many US decommissioning projects encountered that collection and removal of irradiated small and scattered debris from segmentation were challenging issues. That's why cutting enclosure was implemented to restrict the spread of debris to other area of refueling cavity. Furthermore lifting of total weight (apx. 1,000,000 kg) on primary system including RPV, RVI and interior low-density concrete was extremely heavy.

  16. Lessons learned from the decommissioning of destroyed nuclear facilities and sites in Iraq

    International Nuclear Information System (INIS)

    There are many lessons to be learned from the decommissioning experience of destroyed nuclear facilities and sites in Iraq which has been used for nuclear activities and contain significant amounts of radioactive waste. The decommissioning of bombed nuclear facilities needs detailed civil engineering assessments and careful decommissioning planning to remove the potential hazards in effective and safe manner. A master decommissioning plan has been developed to decommission all destroyed nuclear facilities and sites in Iraq. The decommissioning programme started in July 2008 and it will continue till December 2025. The plan consists of 3 phases : the first phase (2008-2010) to decommission 3 low radiological risk facilities - the intent of this phase is to build the staff capacity and their decommissioning capabilities and experience, the second phase (2011-2015) to decommission 5 high radiological risk facilities using the experience gained in phase 1 and third phase (2016-2025) to decommission the remaining nuclear facilities and sites based on radiological risk prioritization scheme. The radioactive waste resulted from decommissioning of phase 1 has been stored in cargo container placed at Al- Tuwaitha site as a temporary solution until the rehabilitation of the damaged radioactive waste treatment facility and building a waste disposal facility similar to that of ANDRA France concrete cells for intermediate and low level waste. (author)

  17. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  18. The Financing of Decommissioning - A View on Legal Aspects in the European Union

    International Nuclear Information System (INIS)

    In the future, an increasing number of nuclear power plants will be definitively closed and undergoing decommissioning. Realising the inseparable connection between the safe performance of decommissioning activities and its financing, the European Union is concerned about the availability of sufficient financial means for carrying out the decommissioning process by the time they are needed. Analysing which measures have been taken by the EU to ensure and harmonise the financing of decommissioning, the author illustrates the draft directives of the European Commission known as the 'nuclear package', which contain rules regarding the funding of decommissioning. In this context, he also descends to the envisaged Commission's analysis about the various concepts established in the Member States with respect to financing the decommissioning of nuclear facilities. The author comes to the conclusion that the EU has taken first initiatives to promote a transparent and harmonised system of regulations and standards concerning the financing of decommissioning across the Union. (author)

  19. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  20. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    Energy Technology Data Exchange (ETDEWEB)

    Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  1. GAS TURBINE REHEAT USING IN SITU COMBUSTION

    Energy Technology Data Exchange (ETDEWEB)

    D.M. Bachovchin; T.E. Lippert; R.A. Newby P.G.A. Cizmas

    2004-05-17

    In situ reheat is an alternative to traditional gas turbine reheat design in which fuel is fed through airfoils rather than in a bulky discrete combustor separating HP and LP turbines. The goals are to achieve increased power output and/or efficiency without higher emissions. In this program the scientific basis for achieving burnout with low emissions has been explored. In Task 1, Blade Path Aerodynamics, design options were evaluated using CFD in terms of burnout, increase of power output, and possible hot streaking. It was concluded that Vane 1 injection in a conventional 4-stage turbine was preferred. Vane 2 injection after vane 1 injection was possible, but of marginal benefit. In Task 2, Combustion and Emissions, detailed chemical kinetics modeling, validated by Task 3, Sub-Scale Testing, experiments, resulted in the same conclusions, with the added conclusion that some increase in emissions was expected. In Task 4, Conceptual Design and Development Plan, Siemens Westinghouse power cycle analysis software was used to evaluate alternative in situ reheat design options. Only single stage reheat, via vane 1, was found to have merit, consistent with prior Tasks. Unifying the results of all the tasks, a conceptual design for single stage reheat utilizing 24 holes, 1.8 mm diameter, at the trailing edge of vane 1 is presented. A development plan is presented.

  2. Biophotonic in situ sensor for plant leaves

    Energy Technology Data Exchange (ETDEWEB)

    Conejo, Elian; Frangi, Jean-Pierre; Rosny, Gilles de

    2010-04-01

    Knowledge of the water concentration of plants can be helpful in several environmental and agricultural domains. There are many methods for the determination of water content in plant leaves; however, most of them give a relative moisture level or an analytical measure after a previous calibration procedure. Even for other biochemical compounds such as dry matter or chlorophyll, the measurement techniques could be destructive. For this reason, a nondestructive method has been developed to measure the biochemical compounds of a plant leaf, using an infrared spectroscopy technique. One important advantage is the simplicity of the device (RAdiometre portatif de Mesure In Situ, RAMIS) and its capability to perform measurements in situ. The prototype is a leaf-clip configuration and is made of LEDs at five wavelengths (656, 721, 843, 937, and 1550 nm), and a silicon/germanium photosensor. To compute the water content of vegetative leaves, the radiative transfer model PROSPECT was implemented. This model can accurately predict spectral transmittances in the 400 nm to 2500 nm spectral region as a function of the principal leaf biochemical contents: water, dry matter, and chlorophyll. Using the transmittance measured by RAMIS into an inversion procedure of PROSPECT: A Model of Leaf Optical Properties Spectra, we are able to compute the values of water contents that show an agreement with the water contents measured directly using dry weight procedures. This method is presented as a possibility to estimate other leaf biochemical compounds using appropriate wavelengths.

  3. In situ SU-8 silver nanocomposites

    Directory of Open Access Journals (Sweden)

    Søren V. Fischer

    2015-07-01

    Full Text Available Nanocomposite materials containing metal nanoparticles are of considerable interest in photonics and optoelectronics applications. However, device fabrication of such materials always encounters the challenge of incorporation of preformed nanoparticles into photoresist materials. As a solution to this problem, an easy new method of fabricating silver nanocomposites by an in situ reduction of precursors within the epoxy-based photoresist SU-8 has been developed. AgNO3 dissolved in acetonitrile and mixed with the epoxy-based photoresist SU-8 forms silver nanoparticles primarily during the pre- and post-exposure soft bake steps at 95 °C. A further high-temperature treatment at 300 °C resulted in the formation of densely homogeneously distributed silver nanoparticles in the photoresist matrix. No particle growth or agglomeration of nanoparticles is observed at this point. The reported new in situ silver nanocomposite materials can be spin coated as homogeneous thin films and structured by using UV lithography. A resolution of 5 µm is achieved in the lithographic process. The UV exposure time is found to be independent of the nanoparticle concentration. The fabricated silver nanocomposites exhibit high plasmonic responses suitable for the development of new optoelectronic and optical sensing devices.

  4. Inherently safe in situ uranium recovery.

    Energy Technology Data Exchange (ETDEWEB)

    Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

    2009-05-01

    Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

  5. Molecular cytogenetics using fluorescence in situ hybridization

    Energy Technology Data Exchange (ETDEWEB)

    Gray, J.W.; Kuo, Wen-Lin; Lucas, J.; Pinkel, D.; Weier, H-U.; Yu, Loh-Chung.

    1990-12-07

    Fluorescence in situ hybridization (FISH) with chromosome-specific probes enables several new areas of cytogenetic investigation by allowing visual determination of the presence and normality of specific genetic sequences in single metaphase or interphase cells. in this approach, termed molecular cytogenetics, the genetic loci to be analyzed are made microscopically visible in single cells using in situ hybridization with nucleic acid probes specific to these loci. To accomplish this, the DNA in the target cells is made single stranded by thermal denaturation and incubated with single-stranded, chemically modified probe under conditions where the probe will anneal only with DNA sequences to which it has high DNA sequence homology. The bound probe is then made visible by treatment with a fluorescent reagent such as fluorescein that binds to the chemical modification carried by the probe. The DNA to which the probe does not bind is made visible by staining with a dye such as propidium iodide that fluoresces at a wavelength different from that of the reagent used for probe visualization. We show in this report that probes are now available that make this technique useful for biological dosimetry, prenatal diagnosis and cancer biology. 31 refs., 3 figs.

  6. Stakeholder involvement in decommissioning in Slovakia. Annex I.F

    International Nuclear Information System (INIS)

    The Czechoslovak atomic energy history started in the 1950s with the construction of the pilot plant NPP A1 with HWGCR at Jaslovske Bohunice. This nuclear power plant was commissioned at the end of 1972 and shut down after the accident (IAEA accident scale - level 4) in 1977. The final decision to decommission this plant was issued by the Czechoslovak Government in 1979. So Czechoslovakia was one of the first countries facing decommissioning of large nuclear installations. As the shut down was not anticipated and the Soviet design of the NPP assumed that waste management should be conducted only at the end of the NPP's life cycle, the State was not prepared for decommissioning including all its aspects- funding, waste management, infrastructure and technologies. Later NPP V1 and NPP V2 - both PWR with WWER 440 were commissioned at the Jaslovske Bohunice site and another NPP with WWER 440 at the Mochovce site. NPP V1 will shortly reach its planned 30 years of operation and although successfully refurbished recently, it is in the process of final shutdown on the basis of a political decision (in 2006 - 1st unit and 2008 - 2nd unit). The list of stakeholders involved in the decommissioning, originally very short at the beginning of the nuclear era, is under continuous change with the increase of the 'decommissioning industry' and the pressures of new economic and political conditions. The history of stakeholders is described in the following chapters, more from the point of view of problems faced and solved in Slovakia than from the point of view of international progress and changes occurring in other nuclear countries. In general, it is possible to divide Slovak decommissioning stakeholders into the following categories: - Owner, operator and licensee; -Public; - Government and Regulatory Bodies, European Union (article No. 37 of EURATOM); -Contractors; - Media; - Environmental organizations; - Public opinion movements; - International organizations as IAEA, OECD

  7. Decommissioning strategy for NPPs and other nuclear facilities in Italy

    International Nuclear Information System (INIS)

    In Italy the issue of decommissioning become real suddenly when, after a Government decision, all operating NPPs have been definitely shutdown in 1987. At that time, in the absence of a Government policy, the Italian electric utility ENEL decided to proceed on the basis of the Safe Storage strategy. Several reasons were behind the decision. Among them the unavailability of a national repository, the potential reduction in occupational doses and the financial advantage in delaying major costs. Therefore, the programs considered the completion of all decommissioning activities and the elimination of all radiological constraints on the sites around the year 2050. Decommissioning activities for Safe Storage, however, did not start at the pace that was initially planned, since many other boundary conditions continued to be not fully clarified (regulatory, financial, technical, etc.). In addition the main mission of ENEL was to generate and sell electrical energy and there was no real pressure to start the activities before the situation was totally clear. In parallel to the partial privatization of ENEL, in this climate of slow progress in the way to Safe Storage, SOGIN was created in 1999 as a separate share Company in the ENEL holding to carry out the decommissioning of the NPP's. In 2000 SOGIN became property of the Ministry of Treasury and was completely separated from ENEL. Therefore, SOGIN became the reference company in Italy for decommissioning. It was also decided, since 2000, that SOGIN should take the responsibility for the decommissioning of other nuclear installations in Italy, namely those of the Nuclear Fuel Cycle operated by ENEA, the state owned R and D organization, and Fabbricazioni Nucleari (FN), an industrial fuel fabrication plant, formerly owned by AGIP Nucleare. In August 2003 all licenses of the Fuel Cycle facilities were transferred to SOGIN, which became responsible for their decommissioning. At the same time was also defined the financial

  8. Decommissioning of U.S. uranium production facilities

    Energy Technology Data Exchange (ETDEWEB)

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

  9. Education in nuclear decommissioning in the north of Scotland

    International Nuclear Information System (INIS)

    This paper describes the work covered and experience gained in the first two years of operation of DERC, a Centre for Decommissioning and Environmental Remediation in the Highlands of Scotland. The Centre is a unique development which was set up to teach nuclear decommissioning as a separate discipline, address the problem of a declining skills base in the field of nuclear technologies and to take advantage of the unique and exceptional innovative, technical and research opportunities offered through the decommissioning of Britain's fast reactor site at Dounreay. The Centre is an offshoot from North Highland College which is a member of UHI, the University in embryo of the Highlands and Islands. The Centre currently supports ten PhD students completing various diverse projects mainly in the field of nuclear environmental remediation. In addition there area number of full and part time MSc students who participate in NTEC (Nuclear Technology Education Consortium) a consortium of British Universities set up specifically to engender interest and skills in nuclear technology at postgraduate level. At undergraduate level, courses are offered in Nuclear Decommissioning and related subjects as part of Electrical and Mechanical degree courses. In addition to our relationship with the United Kingdom Atomic Energy Authority (UKAEA) the Dounreay site licensee, we have links with Rolls-Royce and the Ministry of Defence who also share the Dounreay site and with other stakeholders such as, the UK regulator (HSE/NII), the Scottish Environmental Protection Agency (SEPA), local and international contractors and we liaise with the newly formed Nuclear Decommissioning Authority (NDA), who provide some sponsorship and support. We possess our own equipment and laboratories for taking and analysing soil samples and for conducting environmental surveys. Recently we commissioned an aerial survey of contamination in the locality from natural sources, other background levels such as

  10. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by Kernkraftwerke RWE Bayernwerk GmbH (KRB) and the CEC at Gundremmingen-Guenzburg (D), where the former KRB-A BWR is presently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, the results and conclusions on techniques and procedures presently applied in the dismantling of large-scale nuclear installations in the European Community. Besides the four pilot dismantling projects of the presently running third R and D programme (1989-93) of the European Community on decommissioning of nuclear installations (WAGR, BR-3 PWR, KRB-A BWR and AT-1 FBR fuel reprocessing), the organizers selected the presentation of topics on the following facilities which have a significant scale and/or representative features and are presently being dismantled: the Magnox reprocessing pilot plant at Sellafield, the HWGCR EL4 at Monts d'Arree, the operation of an on-site melting furnace for G2/G3 GCR dismantling waste at Marcoule, an EdF confinement conception of shut-down LWRs for deferred dismantling, and the technical aspects of the Greifswald WWER type NPPs decommissioning. This was completed by a presentation on the decommissioning of material testing reactors in the United Kingdom and by an overview on the conception and implementation of two EC databases on tools, costs and job doses. The seminar concluded with a guided visit of the KRB-A dismantling site. This meeting was attended by managers concerned by the decommissioning of nuclear installations within the European Community, either by practical dismantling work or by decision-making functions. Thereby, the organizers expect to have contributed to the achievement of decommissioning tasks under optimal conditions - with respect to safety and economics - by making available a complete and updated insight into on-going dismantling projects and by

  11. Reasons for inconsistencies between estimated and actual decommissioning costs

    International Nuclear Information System (INIS)

    Reliable cost estimating is one of the most important elements of decommissioning planning. Alternative technologies may be evaluated and compared based on their efficiency and effectiveness, and measured against a baseline cost as to the feasibility and benefits derived from the technology. When the plan is complete, those cost considerations ensure that it is economically sound and practical for funding.Estimates of decommissioning costs have been performed and published by many organizations for many different applications. The results often vary because of differences in the work scope. Labour force costs, monetary considerations, oversight costs, the specific contaminated materials involved, the waste stream and peripheral costs associated with that type of waste, or applicable environmental compliance requirements. Many of the differences in cost estimates are unavoidable since a reasonable degree of reliability and accuracy can only be achieved by developing decommissioning cost estimates on a case-by- case site-specific basis. The paper describes the estimating methodology and process applied to develop decommissioning cost estimates. A major effort has been made to standardize methodologies, and to understand the assumptions and bases that drive the costs. However, estimates are only as accurate as the information available from which to derive the costs. This information includes the assumptions of scope of the work, labour cost inputs, inflationary effects, and financial analyses that project these costs to year of expenditure. Attempts at comparison of estimates for two facilities of similar design and size must clearly identify the assumptions used in developing the estimate, and comparison of actual costs versus estimated costs must reflect these same assumptions. For the nuclear industry to grow, decommissioning estimating tools must improve to keep pace with changing technology, regulations and stakeholder issues. (author)

  12. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  13. Decommissioning and demolition in the European Union. Current status

    International Nuclear Information System (INIS)

    The European Commission pursues the environmental and energy policy goals of limiting global warming to a maximum of 2 C and, therefore, reducing CO2 emissions by at least 20%. Nuclear power, with its present 30% contribution to the Community's electricity supply and the low CO2 emissions of the entire fuel cycle, makes an important contribution to an energy mix matching the 3 factors of competitiveness, security of supply, and sustainability. The decision to use nuclear power plants in their respective countries for electricity production is left to each member state. As of mid-2008, 146 nuclear power plants were in operation in the European Union, while 74 had been shut down permanently. Two nuclear power plants had been demolished completely, showing that the European Community is just at the beginning of the learning curve in this field. The importance of nuclear power plant decommissioning and demolition will increase in the future as replacement capacity in nuclear power generation will become necessary. The European Commission's activities in decommissioning and demolition date from the 1990s: The provisions about environmental impact assessment and the recommendations to apply Article 37 (potential impacts on water, soil and air) of the Euratom Treaty demand a description of decommissioning and demolition of nuclear power plants. In a ruling of 2002, the European Court of Justice assigns to the Community the required competences in the fields of nuclear safety and, consequently, also decommissioning and demolition. The financial provisions necessary for these activities are covered in the Electricity Directive within the framework of the rules for a common single market in 2003. After a first status report, the Commission published recommendations about financing decommissioning and demolition in 2006. (orig.)

  14. Technology and costs for decommissioning of Swedish nuclear power plants

    International Nuclear Information System (INIS)

    The decommissioning study for the Swedish nuclear power plants has been carried out during 1992 to 1994 and the work has been led by a steering group consisting of people from the nuclear utilities and SKB. The study has been focused on two reference plants, Oskarshamn 3 and Ringhals 2. Oskarshamn 3 is a boiling water reactor (BWR) and Ringhals 2 is a pressurized water reactor (PWR). Subsequently, the result from these plants have been translated to the other Swedish plants. The study gives an account of the procedures, costs, waste quantities and occupational doses associated with decommissioning of the Swedish nuclear power plants. Dismantling is assumed to start immediately after removal of the spent fuel. No attempts at optimization, in terms of technology or costs, have been made. The nuclear power plant site is restored after decommissioning so that it can be released for use without restriction for other industrial activities. The study shows that a reactor can be dismantled in about five years, with an average labour force of about 150 persons. The maximum labour force required for Oskarshamn 3 has been estimated to about 300 persons. This peak load occurred the first years but is reduced to about 50 persons during the demolishing of the buildings. The cost of decommissioning Oskarshamn 3 has been estimated to be about MSEK 940 in January 1994 prices. The decommissioning of Ringhals 2 has been estimated to be MSEK 640. The costs for the other Swedish nuclear power plants lie in the range MSEK 590-960. 17 refs, 21 figs, 15 tabs

  15. Alternatieve in situ bodemsaneringstechnieken; literatuuronderzoek bij het project "In Situ Biorestauratie" Asten

    NARCIS (Netherlands)

    Scheuter AJ; LBG

    1997-01-01

    In developing in situ remediation most of the focus used to be on techniques using infiltration water to supply oxygen to the location. Later, techniques were developed in which soil was flushed with air to enhance the oxygen availability to microorganisms. The aim of the study reported here was to

  16. Upper Arctic Ocean velocity structure from in-situ observations

    Science.gov (United States)

    Recinos, Beatriz; Rabe, Benjamin; Schauer, Ursula

    2016-04-01

    The gross circulation of the upper and intermediate layers of the Arctic Ocean has been inferred from water mass properties: the mixed layer, containing fresh water from the shelf seas, travels from Siberia towards the Atlantic sector, and the saline and warm layer of Atlantic origin below, follows cyclonic pathways along topographic features. Direct observations of the flow below the sea ice are, however, sparse and difficult to obtain. This research presents the analysis of a unique time series/section of in situ velocity measurements obtained by a drifting ice-tethered platform in the Transpolar Drift near the North Pole. Two instruments were used to obtain in situ measurements of velocity, temperature, salinity and pressure: an Ice-tethered Acoustic Current profiler (ITAC) and an Ice-tethered Profiler (ITP). Both systems were deployed in the Amundsen basin, during the Arctic Ocean expedition ARK XXII/2 of the German Research Vessel Polarstern in September 2007. The systems transmitted profile data from the 14th of September to the 29th of November 2007 and covered a maximum depth range of 23 to 400 m. The results are compared to observations by a shipboard Acoustic Doppler Current Profiler (ADCP) from the 2011 Polarstern expedition ARK-XXVI/3, and wind and ice concentration from satellite reanalysis products. The data set allows an overview of the upper and intermediate circulation along the Lomonosov Ridge. Near-surface velocity and ice drift obtained by the ITAC unit are consistent with the Transpolar Drift Current. Ekman transports calculated from the observed ice drift and assumed ice-ocean drag behaviour suggest that Ekman dynamics influenced velocities at depths greater than the Ekman layer. Direct velocity observations in combination with water mass analyses from the temperature and salinity data, suggest the existence of a current along the Eurasian side of the Lomonosov Ridge within the warm Atlantic layer below the cold halocline. At those depths

  17. Offshore Oil and Gas Installations Decommissioning in the North Sea. An Assessment of Decommissioning Options & the Market Outlook

    NARCIS (Netherlands)

    Yunyi Chen, Connie

    2012-01-01

    Summary The decommissioning of offshore oil and gas installations is becoming an increasingly crucial issue to the oil and gas industry as a large number of assets within the sector are approaching the end of their economic life. Globally, there are over

  18. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 6 - PRESENTATION OF THE DECOMMISSIONING DEVICE

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2015-05-01

    Full Text Available The objective of this paper is to present a possible solution for the designing of a device for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The decommissioning activities are dismantling, demolition, controlled removal of equipment, components, conventional or hazardous waste (radioactive, toxic in compliance with the international basic safety standards on radiation protection. One as the most important operation in the final phase of the nuclear reactor dismantling is the decommissioning of fuel channels. For the fuel channels decommissioning should be taken into account the detailed description of the fuel channel and its components, the installation documents history, adequate radiological criteria for decommissioning guidance, safety and environmental impact assessment, including radiological and non-radiological analysis of the risks that can occur for workers, public and environment, the description of the proposed program for decommissioning the fuel channel and its components, the description of the quality assurance program and of the monitoring program, the equipments and methods used to verify the compliance with the decommissioning criteria, the planning of performing the final radiological assessment at the end of the fuel channel decommissioning. These will include also, a description of the proposed radiation protection procedures to be used during decommissioning. The dismantling of the fuel channel is performed by one device which shall provide radiation protection during the stages of decommissioning, ensuring radiation protection of the workers. The device shall be designed according to the radiation protection procedures. The decommissioning device assembly of the fuel channel components is composed of the device itself and moving platform support for coupling of the selected channel to be dismantled. The fuel channel decommissioning device is an autonomous device designed for

  19. IN SITU URANIUM STABILIZATION BY MICROBIAL METABOLITES

    Energy Technology Data Exchange (ETDEWEB)

    Turick, C; Anna Knox, A; Chad L Leverette,C; Yianne Kritzas, Y

    2006-11-29

    Soil contaminated with U was the focus of this study in order to develop in-situ, U bio-immobilization technology. We have demonstrated microbial production of a metal chelating biopolymer, pyomelanin, in U contaminated soil from the Tims Branch area of the Department of Energy (DOE) Savannah River Site (SRS) as a result of tyrosine amendments. Bacterial densities of pyomelanin producers were >106 cells/g wet soil. Pyomelanin demonstrated U chelating and mineral binding capacities at pH 4 and 7. In laboratory studies, in the presence of goethite or illite, pyomelanin enhanced U sequestration by these minerals. Tyrosine amended soils in field tests demonstrated increased U sequestration capacity following pyomelanin production up to 13 months after tyrosine treatments.

  20. In situ erosion of cohesive sediment

    International Nuclear Information System (INIS)

    There has been increasing interest in tidal power schemes and the effect of a tidal energy barrage on the environment. A large man-made environmental change, such as a barrage, would be expected to have significant effects on the sediment distribution and stability of an estuary and these effects need to be assessed when considering a tidal barrage project. This report describes the development of apparatus for in-situ measurements of cohesive sediment erosion on inter-tidal mudflats. Development of the prototype field erosion bell and field testing was commissioned on behalf of the Department of Trade and Industry by the Energy Technology Support Unit (ETSU). This later work commenced in August 1991 and was completed in September 1992. (Author)

  1. Overview of In - Situ Biodegradation and Enhancement

    Institute of Scientific and Technical Information of China (English)

    DONG Jun; Anthony ADZOMANI; ZHAO Yongsheng

    2002-01-01

    Microbial degradation technologies have been developed to restore ground water quality in aquifers polluted by organic contaminants effectively in recent years. However, in course of the degradation, the formation of biofilms in ground water remediation technology can be detrimental to the effectiveness of a ground water remediation project. Several alternatives are available to a remedial design engineer, such as Permeable Reactive Barriers (PRBs) and in -situ bioremediation, Hydrogen Releasing Compounds (HRCs) barrier, Oxygen Releasing Compounds (ORCs) barrier etc. which are efficient and cost- effective technologies. Excessive biomass formation renders a barrier ineffective in degrading the contaminants, Efforts are made to develop kinetics models which accurately determine bio - fouling and bio - filn formation and to control excessive biomass formation.

  2. Treatment options for carcinoma in situ testis

    DEFF Research Database (Denmark)

    Mortensen, M S; Gundgaard, M.G.; Daugaard, G

    2011-01-01

    Carcinoma in situ testis (CIS) is known as the precursor of germ cell cancer of the testis. International guidelines on diagnosis and treatment are inconsistent. Some countries offer routine biopsies of the contralateral testicle in relation to orchidectomy for testicular cancer, whereas other...... been treated in the dose range of 16-20 Gy. Higher doses involve a higher risk of androgen insufficiency. Radiotherapy is recommended in patients with contralateral CIS. Orchidectomy should be offered in extragonadal germ cell cancer and CIS in one testicle, whereas patients with bilateral CIS should...... be offered radiation therapy. Patients who have undergone chemotherapy for testicular cancer are still at risk of developing CIS and we also recommend radiotherapy to the affected testicle in these patients. Cryopreservation should be offered before treatment is initiated and all patients should have...

  3. Cryogenic in situ microcompression testing of Sn

    International Nuclear Information System (INIS)

    Characterizing plasticity mechanisms below the ductile-to-brittle transition temperature is traditionally difficult to accomplish in a systematic fashion. Here, we use a new experimental setup to perform in situ cryogenic mechanical testing of pure Sn micropillars at room temperature and at −142 °C. Subsequent electron microscopy characterization of the micropillars shows a clear difference in the deformation mechanisms at room temperature and at cryogenic temperatures. At room temperature, the Sn micropillars deformed through dislocation plasticity, while at −142 °C they exhibited both higher strength and deformation twinning. Two different orientations were tested, a symmetric (1 0 0) orientation and a non-symmetric (4 5¯ 1) orientation. The deformation mechanisms were found to be the same for both orientations

  4. Support Routines for In Situ Image Processing

    Science.gov (United States)

    Deen, Robert G.; Pariser, Oleg; Yeates, Matthew C.; Lee, Hyun H.; Lorre, Jean

    2013-01-01

    This software consists of a set of application programs that support ground-based image processing for in situ missions. These programs represent a collection of utility routines that perform miscellaneous functions in the context of the ground data system. Each one fulfills some specific need as determined via operational experience. The most unique aspect to these programs is that they are integrated into the large, in situ image processing system via the PIG (Planetary Image Geometry) library. They work directly with space in situ data, understanding the appropriate image meta-data fields and updating them properly. The programs themselves are completely multimission; all mission dependencies are handled by PIG. This suite of programs consists of: (1)marscahv: Generates a linearized, epi-polar aligned image given a stereo pair of images. These images are optimized for 1-D stereo correlations, (2) marscheckcm: Compares the camera model in an image label with one derived via kinematics modeling on the ground, (3) marschkovl: Checks the overlaps between a list of images in order to determine which might be stereo pairs. This is useful for non-traditional stereo images like long-baseline or those from an articulating arm camera, (4) marscoordtrans: Translates mosaic coordinates from one form into another, (5) marsdispcompare: Checks a Left Right stereo disparity image against a Right Left disparity image to ensure they are consistent with each other, (6) marsdispwarp: Takes one image of a stereo pair and warps it through a disparity map to create a synthetic opposite- eye image. For example, a right eye image could be transformed to look like it was taken from the left eye via this program, (7) marsfidfinder: Finds fiducial markers in an image by projecting their approximate location and then using correlation to locate the markers to subpixel accuracy. These fiducial markets are small targets attached to the spacecraft surface. This helps verify, or improve, the

  5. In situ studies of fracture in solids

    International Nuclear Information System (INIS)

    Electron microscope studies were made of the propagation of microcracks during in situ tensile deformation of stainless steel, molybdenum and magnesium oxide representing ductile, semi-brittle and brittle solids. As the stress is applied, the cracks are initiated at the edge of holes in the thinned foils. The extent of plastic activity around the cracks is measured in terms of the density and the distribution of dislocations and is sensitive to the ductile/brittle nature of the solid. The slip systems of the dislocations are determined by contrast analysis and stereoscopic observation. In stainless steel and magnesium oxide, the dislocations are relatively straight and they lie nearly perpendicular to the direction of the crack propagation, whereas in molybdenum the dislocations are in the form of irregular tangles which are stretched along the direction of the crack propagation. These observations are discussed in terms of the model of Dugdale concerning the formation of plastic zones under uniaxial loading in plane stress conditions

  6. In situ Fabrication of Monolithic Copper Azide

    Science.gov (United States)

    Li, Bing; Li, Mingyu; Zeng, Qingxuan; Wu, Xingyu

    2016-04-01

    Fabrication and characterization of monolithic copper azide were performed. The monolithic nanoporous copper (NPC) with interconnected pores and nanoparticles was prepared by decomposition and sintering of the ultrafine copper oxalate. The preferable monolithic NPC can be obtained through decomposition and sintering at 400°C for 30 min. Then, the available monolithic NPC was in situ reacted with the gaseous HN3 for 24 h and the monolithic NPC was transformed into monolithic copper azide. Additionally, the copper particles prepared by electrodeposition were also reacted with the gaseous HN3 under uniform conditions as a comparison. The fabricated monolithic copper azide was characterized by Fourier transform infrared (FTIR), inductively coupled plasma-optical emission spectrometry (ICP-OES), and differential scanning calorimetry (DSC).

  7. In situ SU-8 silver nanocomposites

    DEFF Research Database (Denmark)

    Fischer, Søren Vang; Uthuppu, Basil; Jakobsen, Mogens Havsteen

    2015-01-01

    Nanocomposite materials containing metal nanoparticles are of considerable interest in photonics and optoelectronics applications. However, device fabrication of such materials always encounters the challenge of incorporation of preformed nanoparticles into photoresist materials. As a solution...... to this problem, an easy new method of fabricating silver nanocomposites by an in situ reduction of precursors within the epoxy-based photoresist SU-8 has been developed. AgNO3 dissolved in acetonitrile and mixed with the epoxy-based photoresist SU-8 forms silver nanoparticles primarily during the pre- and post...... silver nanocomposite materials can be spin coated as homogeneous thin films and structured by using UV lithography. A resolution of 5 mu m is achieved in the lithographic process. The UV exposure time is found to be independent of the nanoparticle concentration. The fabricated silver nanocomposites...

  8. DUCTAL CARCINOMA IN SITU OF THE BREAST

    Institute of Scientific and Technical Information of China (English)

    2000-01-01

    Objective: To investigate the clinical characteristics, treatment and prognosis of ductal carcinoma in situ (DCIS) of the breast. Methods: Clinicopathological and follow-up data were collected in 52 patients with DCIS. Results: The clinic data showed that 50 patients had signs of breast lumps or/and nipple discharges, 2 patients presented abnormal mammography; 2 patients had lymph node involved; and 14 patients were accompanied with intraductal papillomatosis. All patients were Received surgical therapy. The follow-up data showed 1 patient locally recurred after lumpectomy, and was underwent mastectomy again, then cured. There were no patients died of DCIS. Conclusion: Mastectomy should be a standard surgical mode, and the prognosis of DCIS was favorable, but mammography for screening of asymptomatic women should be strengthened to find DCIS.

  9. PERFORMANCE CONFIRMATION IN-SITU INSTRUMENTATION

    International Nuclear Information System (INIS)

    The purpose of this document is to identify and analyze the types of in-situ instruments and methods that could be used in support of the data acquisition portion of the Performance Confirmation (PC) program at the potential nuclear waste repository at Yucca Mountain. The PC program will require geomechanical , geophysical, thermal, and hydrologic instrumentation of several kinds. This analysis is being prepared to document the technical issues associated with each type of measurement during the PC period. This analysis utilizes the ''Performance Confirmation Input Criteria'' (CRWMS M andO 1999a) as its starting point. The scope of this analysis is primarily on the period after the start of waste package emplacement and before permanent closure of the repository, a period lasting between 15 and 300 years after last package emplacement (Stroupe 2000, Attachment 1, p. 1). The primary objectives of this analysis are to: (1) Review the design criteria as presented in the ''Performance Confirmation Input Criteria'' (CRWMS M andO 1999a). The scope of this analysis will be limited to the instrumentation related to parameters that require continuous monitoring of the conditions underground. (2) Preliminary identification and listing of the data requirements and parameters as related to the current repository layout in support of PC monitoring. (3) Preliminary identification of methods and instrumentation for the acquisition of the required data. Although the ''Performance Confirmation Input Criteria'' (CRWMS M andO 1999a) defines a broad range of data that must be obtained from a variety of methods, the focus of this analysis is on instrumentation related to the performance of the rock mass and the formation of water in the repository environment, that is obtainable from in-situ observation, testing, and monitoring

  10. PERFORMANCE CONFIRMATION IN-SITU INSTRUMENTATION

    Energy Technology Data Exchange (ETDEWEB)

    N.T. Raczka

    2000-05-23

    The purpose of this document is to identify and analyze the types of in-situ instruments and methods that could be used in support of the data acquisition portion of the Performance Confirmation (PC) program at the potential nuclear waste repository at Yucca Mountain. The PC program will require geomechanical , geophysical, thermal, and hydrologic instrumentation of several kinds. This analysis is being prepared to document the technical issues associated with each type of measurement during the PC period. This analysis utilizes the ''Performance Confirmation Input Criteria'' (CRWMS M&O 1999a) as its starting point. The scope of this analysis is primarily on the period after the start of waste package emplacement and before permanent closure of the repository, a period lasting between 15 and 300 years after last package emplacement (Stroupe 2000, Attachment 1, p. 1). The primary objectives of this analysis are to: (1) Review the design criteria as presented in the ''Performance Confirmation Input Criteria'' (CRWMS M&O 1999a). The scope of this analysis will be limited to the instrumentation related to parameters that require continuous monitoring of the conditions underground. (2) Preliminary identification and listing of the data requirements and parameters as related to the current repository layout in support of PC monitoring. (3) Preliminary identification of methods and instrumentation for the acquisition of the required data. Although the ''Performance Confirmation Input Criteria'' (CRWMS M&O 1999a) defines a broad range of data that must be obtained from a variety of methods, the focus of this analysis is on instrumentation related to the performance of the rock mass and the formation of water in the repository environment, that is obtainable from in-situ observation, testing, and monitoring.

  11. In Situ Field Testing of Processes

    Energy Technology Data Exchange (ETDEWEB)

    J. Wang

    2001-12-14

    The purpose of this Analysis/Model Report (AMR) is to update and document the data and subsequent analyses from ambient field-testing activities performed in underground drifts of the Yucca Mountain Site Characterization Project (YMP). This revision updates data and analyses presented in the initial issue of this AMR. This AMR was developed in accordance with the ''Technical Work Plan for Unsaturated Zone (UZ) Flow and Transport Process Model Report'' and ''Technical Work Plan for UZ Flow, Transport, and Coupled Processes Process Model Report. These activities were performed to investigate in situ flow and transport processes. The evaluations provide the necessary framework to: (1) refine and confirm the conceptual model of matrix and fracture processes in the unsaturated zone (UZ) and (2) analyze the impact of excavation (including use of construction water and effect of ventilation) on the UZ flow and transport processes. This AMR is intended to support revisions to ''Conceptual and Numerical Models for UZ Flow and Transport'' and ''Unsaturated Zone Flow and Transport Model Process Model Report''. In general, the results discussed in this AMR are from studies conducted using a combination or a subset of the following three approaches: (1) air-injection tests, (2) liquid-release tests, and (3) moisture monitoring using in-drift sensors or in-borehole sensors, to evaluate the impact of excavation, ventilation, and construction-water usage on the surrounding rocks. The liquid-release tests and air-injection tests provide an evaluation of in situ fracture flow and the competing processes of matrix imbibition. Only the findings from testing and data not covered in the ''Seepage Calibration Model and Seepage Testing Data'' are analyzed in detail in the AMR.

  12. In Situ Field Testing of Processes

    International Nuclear Information System (INIS)

    The purpose of this Analysis/Model Report (AMR) is to update and document the data and subsequent analyses from ambient field-testing activities performed in underground drifts of the Yucca Mountain Site Characterization Project (YMP). This revision updates data and analyses presented in the initial issue of this AMR. This AMR was developed in accordance with the ''Technical Work Plan for Unsaturated Zone (UZ) Flow and Transport Process Model Report'' and ''Technical Work Plan for UZ Flow, Transport, and Coupled Processes Process Model Report. These activities were performed to investigate in situ flow and transport processes. The evaluations provide the necessary framework to: (1) refine and confirm the conceptual model of matrix and fracture processes in the unsaturated zone (UZ) and (2) analyze the impact of excavation (including use of construction water and effect of ventilation) on the UZ flow and transport processes. This AMR is intended to support revisions to ''Conceptual and Numerical Models for UZ Flow and Transport'' and ''Unsaturated Zone Flow and Transport Model Process Model Report''. In general, the results discussed in this AMR are from studies conducted using a combination or a subset of the following three approaches: (1) air-injection tests, (2) liquid-release tests, and (3) moisture monitoring using in-drift sensors or in-borehole sensors, to evaluate the impact of excavation, ventilation, and construction-water usage on the surrounding rocks. The liquid-release tests and air-injection tests provide an evaluation of in situ fracture flow and the competing processes of matrix imbibition. Only the findings from testing and data not covered in the ''Seepage Calibration Model and Seepage Testing Data'' are analyzed in detail in the AMR

  13. Environmental impact assessment for uranium mine, mill and in situ leach projects

    International Nuclear Information System (INIS)

    Environmental impact assessments and/or statements are an inherent part of any uranium mining project and are a prerequisite for the future opening of an exploitation and its final closure and decommissioning. Since they contain all information related to the physical, biological, chemical and economic condition of the areas where industrial projects are proposed or planned, they present invaluable guidance for the planning and implementation of environmental mitigation as well as environmental restoration after the mine is closed. They further yield relevant data on the socio-economic impacts of a project. The present report provides guidance on the environmental impact assessment of uranium mining and milling projects, including in situ leach projects which will be useful for companies in the process of planning uranium developments as well as for the regional or national authorities who will assess such developments. Additional information and advice is given through environmental case histories from five different countries. Those case histories are not meant to be prescriptions for conducting assessments nor even firm recommendations, but should serve as examples for the type and extent of work involved in assessments. A model assessment and licensing process is recommended based on the experience of the five countries

  14. MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Langton, C.; Stefanko, D.

    2011-01-05

    The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere. Fresh and cured properties were measured for: (1) commercially blended magnesium mono potassium phosphate packaged grouts, (2) commercially available binders blended with inert fillers at SRNL, (3) grouts prepared from technical grade MgO and KH{sub 2}PO{sub 4} and inert fillers (quartz sands, Class F fly ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

  15. Magnesium Mono Potassium Phosphate Grout For P-Reactor Vessel In-Situ Decomissioning

    International Nuclear Information System (INIS)

    The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material (≤ 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere. Fresh and cured properties were measured for: (1) commercially blended magnesium mono potassium phosphate packaged grouts, (2) commercially available binders blended with inert fillers at SRNL, (3) grouts prepared from technical grade MgO and KH2PO4 and inert fillers (quartz sands, Class F fly ash), and (4) Ceramicrete(regsign) magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

  16. Weak-aeromagnetic anomaly and in-situ leachable sandstone-type uranium deposit

    International Nuclear Information System (INIS)

    Anomaly the information over in-situ leachable sandstone type uranium deposit appears rather weak due to the thick cover, therefore, prospecting in this area is extremely difficult. The purpose of this paper is to search the aerogeophysical prospecting information relative to the formation of in-situ leachable sandstone-type uranium deposit. After careful study of aeromagnetic data of three known deposits No. 510, 511 and 512 in the southern rim of Yili Basin, this paper discovers that there are weak-aeromagnetic anomalies over this deposits, and makes further discussion on the forming mechanism of weak-aeromagnetic anomaly according to the metallogenetic geochemical mechanism of this type uranium deposit. Combining with the practical predictions, it concludes that there are weak-micromagnetic anomalies over in-situ leachable sandstone type uranium deposits related to redox transitional zone, and high precision aeromagnetic survey can detect these anomalies, so weak-aeromagnetic anomaly can be regarded as one of characteristic anomalies for this type deposit and can act as a kind of direct guiding information in the pre-phase metallogenetic prediction. (authors)

  17. Current status of decommissioning projects and their strategies in advanced countries

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Park, J. H.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-06-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The number of nuclear facilities to be dismantled will be much increased in future and the decommissioning industries will be enlarged. Keeping pace with this increasing tendency, each country formulated their own strategies and regulation systems, and applied their own technologies. The international organizations such as the IAEA and the OECD/NEA also prepared standards in technologies and regulation upon decommissioning and recommended to adopt them to the decommissioning projects. These strategies and technologies are very different country by country due to the different site dependent conditions and it will not be reasonable to evaluate their merits and weakness. The world wide status of the decommissioning, highlighted on that of 5 countries of USA, UK, France, Germany and Japan because they are advanced counties in nuclear industries, are summarized and their site specific conditions are evaluated. The scopes of the evaluation are decommissioning strategies, licensing procedures and requirements focused on decommissioning plan, waste management, technology development and so on. The detailed decommissioning progresses of several typical example sites were introduced. The activities on decommissioning field of the international organization, increased according to the enlarged decommissioning industries, are also summarized.

  18. Current status of decommissioning projects and their strategies in advanced countries

    International Nuclear Information System (INIS)

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The number of nuclear facilities to be dismantled will be much increased in future and the decommissioning industries will be enlarged. Keeping pace with this increasing tendency, each country formulated their own strategies and regulation systems, and applied their own technologies. The international organizations such as the IAEA and the OECD/NEA also prepared standards in technologies and regulation upon decommissioning and recommended to adopt them to the decommissioning projects. These strategies and technologies are very different country by country due to the different site dependent conditions and it will not be reasonable to evaluate their merits and weakness. The world wide status of the decommissioning, highlighted on that of 5 countries of USA, UK, France, Germany and Japan because they are advanced counties in nuclear industries, are summarized and their site specific conditions are evaluated. The scopes of the evaluation are decommissioning strategies, licensing procedures and requirements focused on decommissioning plan, waste management, technology development and so on. The detailed decommissioning progresses of several typical example sites were introduced. The activities on decommissioning field of the international organization, increased according to the enlarged decommissioning industries, are also summarized

  19. Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-04-01

    In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

  20. How utilities can achieve more accurate decommissioning cost estimates

    International Nuclear Information System (INIS)

    The number of commercial nuclear power plants that are undergoing decommissioning coupled with the economic pressure of deregulation has increased the focus on adequate funding for decommissioning. The introduction of spent-fuel storage and disposal of low-level radioactive waste into the cost analysis places even greater concern as to the accuracy of the fund calculation basis. The size and adequacy of the decommissioning fund have also played a major part in the negotiations for transfer of plant ownership. For all of these reasons, it is important that the operating plant owner reduce the margin of error in the preparation of decommissioning cost estimates. To data, all of these estimates have been prepared via the building block method. That is, numerous individual calculations defining the planning, engineering, removal, and disposal of plant systems and structures are performed. These activity costs are supplemented by the period-dependent costs reflecting the administration, control, licensing, and permitting of the program. This method will continue to be used in the foreseeable future until adequate performance data are available. The accuracy of the activity cost calculation is directly related to the accuracy of the inventory of plant system component, piping and equipment, and plant structural composition. Typically, it is left up to the cost-estimating contractor to develop this plant inventory. The data are generated by searching and analyzing property asset records, plant databases, piping and instrumentation drawings, piping system isometric drawings, and component assembly drawings. However, experience has shown that these sources may not be up to date, discrepancies may exist, there may be missing data, and the level of detail may not be sufficient. Again, typically, the time constraints associated with the development of the cost estimate preclude perfect resolution of the inventory questions. Another problem area in achieving accurate cost