Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-03-31

The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.

Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed-in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.

FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Helene Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Hanford Site Composite Analysis Technical Approach Description: Hanford Site Disposition Baseline.

Energy Technology Data Exchange (ETDEWEB)

Cobb, M. A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Dockter, R. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2017-10-02

The permeability of ground surfaces within the U.S. Department of Energy’s (DOE) Hanford Site strongly influences boundary conditions when simulating the movement of groundwater using the Subsurface Transport Over Multiple Phases model. To conduct site-wide modeling of cumulative impacts to groundwater from past, current, and future waste management activities, a site-wide assessment of the permeability of surface conditions is needed. The surface condition of the vast majority of the Hanford Site has been and continues to be native soils vegetated with dryland grasses and shrubs.

Technical baseline description for in situ vitrification laboratory test equipment

International Nuclear Information System (INIS)

Beard, K.V.; Bonnenberg, R.W.; Watson, L.R.

1991-09-01

IN situ vitrification (ISV) has been identified as possible waste treatment technology. ISV was developed by Pacific Northwest Laboratory (PNL), Richland, Washington, as a thermal treatment process to treat contaminated soils in place. The process, which electrically melts and dissolves soils and associated inorganic materials, simultaneously destroys and/or removes organic contaminants while incorporating inorganic contaminants into a stable, glass-like residual product. This Technical Baseline Description has been prepared to provide high level descriptions of the design of the Laboratory Test model, including all design modifications and safety improvements made to data. Furthermore, the Technical Baseline Description provides a basic overview of the interface documents for configuration management, program management interfaces, safety, quality, and security requirements. 8 figs

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

International Nuclear Information System (INIS)

McLaughlin, T.J.

1998-01-01

This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1

International Nuclear Information System (INIS)

1996-01-01

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE's mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Weeks Island brine diffuser site study: baseline conditions and environmental assessment technical report

Energy Technology Data Exchange (ETDEWEB)

None

1980-12-12

This technical report presents the results of a study conducted at two alternative brine diffuser sites (A and B) proposed for the Weeks Island salt dome, together with an analysis of the potential physical, chemical, and biological effects of brine disposal for this area of the Gulf of Mexico. Brine would result from either the leaching of salt domes to form or enlarge oil storage caverns, or the subsequent use of these caverns for crude oil storage in the Strategic Petroleum Reserve (SPR) program. Brine leached from the Weeks Island salt dome would be transported through a pipeline which would extend from the salt dome either 27 nautical miles (32 statute miles) for Site A, or 41 nautical miles (47 statute miles) for Site B, into Gulf waters. The brine would be discharged at these sites through an offshore diffuser at a sustained peak rate of 39 ft/sup 3//sec. The disposal of large quantities of brine in the Gulf could have a significant impact on the biology and water quality of the area. Physical and chemical measurements of the marine environment at Sites A and B were taken between September 1977 and July 1978 to correlate the existing environmental conditions with the estimated physical extent of tthe brine discharge as predicted by the MIT model (US Dept. of Commerce, 1977a). Measurements of wind, tide, waves, currents, and stratification (water column structure) were also obtained since the diffusion and dispersion of the brine plume are a function of the local circulation regime. These data were used to calculate both near- and far-field concentrations of brine, and may also be used in the design criteria for diffuser port configuration and verification of the plume model. Biological samples were taken to characterize the sites and to predict potential areas of impact with regard to the discharge. This sampling focused on benthic organisms and demersal fish. (DMC)

Yucca Mountain Site Characterization Project: Technical Data Catalog (quarterly supplement), June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

The DOE/NRC Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the date, place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994

Baseline and premining geochemical characterization of mined sites

Science.gov (United States)

Nordstrom, D. Kirk

2015-01-01

A rational goal for environmental restoration of new, active, or inactive mine sites would be ‘natural background’ or the environmental conditions that existed before any mining activities or other related anthropogenic activities. In a strictly technical sense, there is no such thing as natural background (or entirely non-anthropogenic) existing today because there is no part of the planet earth that has not had at least some chemical disturbance from anthropogenic activities. Hence, the terms ‘baseline’ and ‘pre-mining’ are preferred to describe these conditions. Baseline conditions are those that existed at the time of the characterization which could be pre-mining, during mining, or post-mining. Protocols for geochemically characterizing pre-mining conditions are not well-documented for sites already mined but there are two approaches that seem most direct and least ambiguous. One is characterization of analog sites along with judicious application of geochemical modeling. The other is reactive-transport modeling (based on careful synoptic sampling with tracer-injection) and subtracting inputs from known mining and mineral processing. Several examples of acidic drainage are described from around the world documenting the range of water compositions produced from pyrite oxidation in the absence of mining. These analog sites provide insight to the processes forming mineralized waters in areas untouched by mining. Natural analog water-chemistry data is compared with the higher metal concentrations, metal fluxes, and weathering rates found in mined areas in the few places where comparisons are possible. The differences are generally 1–3 orders of magnitude higher for acid mine drainage.

Technical Baseline Summary Description for the Tank Farm Contractor

International Nuclear Information System (INIS)

TEDESCHI, A.R.

2000-01-01

This document is a revision of the document titled above, summarizing the technical baseline of the Tank Farm Contractor. It is one of several documents prepared by CH2M HILL Hanford Group, Inc. to support the U.S. Department of Energy Office of River Protection Tank Waste Retrieval and Disposal Mission at Hanford

Technical know-how of site descriptive modeling for site characterization - 59089

International Nuclear Information System (INIS)

Saegusa, Hiromitsu; Onoe, Hironori; Doke, Ryosuke; Niizato, Tadafumi; Yasue, Ken-ichi

2012-01-01

The site descriptive model covering the current status of characteristics of geological environment and the site evolution model for estimation of the long-term evolution of site conditions are used to integrate multi-disciplinary investigation results. It is important to evaluate uncertainties in the models, to specify issues regarding the uncertainties and to prioritize the resolution of specified issues, for the planning of site characterization. There is a large quantity of technical know-how in the modeling process. It is important to record the technical know-how with transparency and traceability, since site characterization projects generally need long duration. The transfer of the technical know-how accumulated in the research and development (R and D) phase to the implementation phase is equally important. The aim of this study is to support the planning of initial surface-based site characterizations based on the technical know-how accumulated from the underground research laboratory projects. These projects are broad scientific studies of the deep geological environment and provide a technical basis for the geological disposal of high-level radioactive wastes. In this study, a comprehensive task flow from acquisition of existing data to planning of field investigations through the modeling has been specified. Specific task flow and decision-making process to perform the tasks have been specified. (authors)

US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

International Nuclear Information System (INIS)

Roach, J.A.; Gombert, D.

1996-01-01

The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

Baseline ecological risk assessment Salmon Site, Lamar County, Mississippi

International Nuclear Information System (INIS)

1995-04-01

The Salmon Site (SS), formerly the Tatum Dome Test Site, located in Mississippi was the site of two nuclear and two gas explosion tests conducted between 1964 and 1970. A consequence of these testing activities is that radionuclides were released into the salt dome, where they are presently contained. During reentry drilling and other site activities, incidental liquid and solid wastes that contained radioactivity were generated, resulting in some soil, ground water and equipment contamination. As part of the remedial investigation effort, a Baseline Ecological Risk Assessment was conducted at the SS. The purpose is to gauge ecological and other environmental impacts attributable to past activities at the former test facility. The results of this facility-specific baseline risk assessment are presented in this document

Baseline ecological risk assessment Salmon Site, Lamar County, Mississippi

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

The Salmon Site (SS), formerly the Tatum Dome Test Site, located in Mississippi was the site of two nuclear and two gas explosion tests conducted between 1964 and 1970. A consequence of these testing activities is that radionuclides were released into the salt dome, where they are presently contained. During reentry drilling and other site activities, incidental liquid and solid wastes that contained radioactivity were generated, resulting in some soil, ground water and equipment contamination. As part of the remedial investigation effort, a Baseline Ecological Risk Assessment was conducted at the SS. The purpose is to gauge ecological and other environmental impacts attributable to past activities at the former test facility. The results of this facility-specific baseline risk assessment are presented in this document.

Yucca Mountain Site Characterization Project Technical Data Catalog

International Nuclear Information System (INIS)

1992-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear, Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

Yucca Mountain Site Characterization Project technical data catalog

International Nuclear Information System (INIS)

1992-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

Technical challenges in the qualitative ecological risk assessments performed on the Hanford Site operable units

International Nuclear Information System (INIS)

Probasco, K.M.

1994-01-01

Qualitative Risk Assessments (QRAS) have been selected as the method for providing the risk-driver indications for interim, remedial, and cleanup actions for the Hanford Site operable units' ecological risk assessments. This expedited response action path has been developed for the Hanford Site to facilitate time-critical decisions and generate immediate emergency cleanup actions. Tight budgets and aggressive time schedules are a major factor in the development of the QRA process. The QRA is a quick way to find immediate threats and a good precursor to a full risk assessment. However, numerous technical challenges have been identified with the QRA approach. The QRA approach differs from a baseline risk assessment in several ways. The main differences involve the use of data that have previously been gathered from the site, and the development of a ''bias-for-action'' document that would reveal qualitative risks from the contaminants identified at the operable units. Technical challenges concerning the ecological portion of these QRAs have raised questions about using the ORA for decision-making and may have weakened the validity of its use in the established procedural framework. Challenges involving such issues as the extrapolation of the contaminant data, data validation and screening techniques, receptor selections, and the final risk characterization outcome threaten the feasibility of the QRA as a decision-making tool. This discussion provides insight into resolving technical challenges and may be a ''lessons-learned'' device for those interested in the QRA approach. Ultimately, these challenges are proving to be learning tools for scientists, regulators, and ecologists and are identifying the data gaps and research direction for future ecological baseline risk assessments

Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

International Nuclear Information System (INIS)

1976-01-01

Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

Site Outcomes Baseline Multi Year Work Plan Volume 1, River Corridor Restoration Baseline

International Nuclear Information System (INIS)

Wintczak, T.M.

2001-01-01

The River Corridor Restoration volume is a compilation of Hanford Site scope, which excludes the approximately 194 km 2 Central Plateau. The River Corridor scope is currently contractually assigned to Fluor Hanford, Bechtel Hanford, inc., DynCorp, and Pacific Northwest National Laboratory, and others. The purpose of this project specification is to provide an overall scoping document for the River Corridor Restoration volume, and to provide a link with the overall Hanford Site River Corridor scope. Additionally, this specification provides an integrated and consolidated source of information for the various scopes, by current contract, for the River Corridor Restoration Baseline. It identifies the vision, mission, and goals, as well as the operational history of the Hanford Site, along with environmental setting and hazards

Conflict between public perceptions and technical processes in site selection

International Nuclear Information System (INIS)

Avant, R.V. Jr.; Jacobi, L.R.

1985-01-01

U.S. Nuclear Regulatory Commission regulations and guidance on site selection are based on sound technical reasoning. Geology, hydrology, flora and fauna, transportation, demographics, and sociopolitical concerns, to name a few, have been factored into the process. Regardless of the technical objectivity of a site selection process, local opposition groups will challenge technical decisions using technical, nontechnical, and emotional arguments. This paper explores the many conflicts between public perceptions, technical requirements designed to protect the general public, and common arguments against site selection. Ways to deal with opposition are also discussed with emphasis placed on developing effective community relations

Site systems engineering fiscal year 1999 multi-year work plan (MYWP) update for WBS 1.8.2.2; TOPICAL

International Nuclear Information System (INIS)

GRYGIEL, M.L.

1998-01-01

Manage the Site Systems Engineering process to provide a traceable integrated requirements-driven, and technically defensible baseline. Through the Site Integration Group(SIG), Systems Engineering ensures integration of technical activities across all site projects. Systems Engineering's primary interfaces are with the RL Project Managers, the Project Direction Office and with the Project Major Subcontractors, as well as with the Site Planning organization. Systems Implementation: (1) Develops, maintains, and controls the site integrated technical baseline, ensures the Systems Engineering interfaces between projects are documented, and maintain the Site Environmental Management Specification. (2) Develops and uses dynamic simulation models for verification of the baseline and analysis of alternatives. (3) Performs and documents fictional and requirements analyses. (4) Works with projects, technology management, and the SIG to identify and resolve technical issues. (5) Supports technical baseline information for the planning and budgeting of the Accelerated Cleanup Plan, Multi-Year Work Plans, Project Baseline Summaries as well as performance measure reporting. (6) Works with projects to ensure the quality of data in the technical baseline. (7) Develops, maintains and implements the site configuration management system

Assessment of local GNSS baselines at co-location sites

Science.gov (United States)

Herrera Pinzón, Iván; Rothacher, Markus

2018-01-01

As one of the major contributors to the realisation of the International Terrestrial Reference System (ITRS), the Global Navigation Satellite Systems (GNSS) are prone to suffer from irregularities and discontinuities in time series. While often associated with hardware/software changes and the influence of the local environment, these discrepancies constitute a major threat for ITRS realisations. Co-located GNSS at fundamental sites, with two or more available instruments, provide the opportunity to mitigate their influence while improving the accuracy of estimated positions by examining data breaks, local biases, deformations, time-dependent variations and the comparison of GNSS baselines with existing local tie measurements. With the use of co-located GNSS data from a subset sites of the International GNSS Service network, this paper discusses a global multi-year analysis with the aim of delivering homogeneous time series of coordinates to analyse system-specific error sources in the local baselines. Results based on the comparison of different GNSS-based solutions with the local survey ties show discrepancies of up to 10 mm despite GNSS coordinate repeatabilities at the sub-mm level. The discrepancies are especially large for the solutions using the ionosphere-free linear combination and estimating tropospheric zenith delays, thus corresponding to the processing strategy used for global solutions. Snow on the antennas causes further problems and seasonal variations of the station coordinates. These demonstrate the need for a permanent high-quality monitoring of the effects present in the short GNSS baselines at fundamental sites.

Technical assistance to Ohio closure sites; Recommendations toaddress contaminated soils, concrete, and corrective action managementunit/groundwater contamination at Ashtabula, Ohio

Energy Technology Data Exchange (ETDEWEB)

Charoglu, Emily; Eddy-Dilek, Carol; Gombert, Dirk; Hazen, Terry; Johnson, Bob; Looney, Brian; Krstich, Michael A.; Rautman, Chris; Tripp,Julia; Whitmill, Larry

2002-08-26

The Ashtabula Environmental Management Project (AEMP) at Department of Energy-Ohio (DOE-OH) requested technical assistance from the EM-50 Lead Lab to aid in defining new cost and time effective approaches in the following problem areas: soils, concrete, and groundwater/Corrective Action Management Unit (CAMU) at RMIES in Ashtabula, Ohio. Attachment 1 provides the site request for assistance. The technical assistance team assembled for this request is provided in Attachment 2. These individuals reviewed key site information prior to convening with DOE and contractor personnel (RMIES and Earthline) for a three-and-a-half-day meeting to better understand baseline technologies, limitations, and site-specific issues. After listening to presentations about the nature and extent of known contamination, the team broke out into several groups to brainstorm ideas and develop viable solutions. This executive summary details unresolved issues requiring management attention as well as recommendations to address soils, concrete, and groundwater/CAMU. It also provides a summary of additional technical assistance that could be provided to the site. More details are presented in the body of this report.

TWRS phase I privatization site environmental baseline and characterization plan

International Nuclear Information System (INIS)

Shade, J.W.

1997-01-01

This document provides a plan to characterize and develop an environmental baseline for the TWRS Phase I Privatization Site before construction begins. A site evaluation study selected the former Grout Disposal Area of the Grout Treatment Facility in the 200 East Area as the TWRS Phase I Demonstration Site. The site is generally clean and has not been used for previous activities other than the GTF. A DQO process was used to develop a Sampling and Analysis Plan that would allow comparison of site conditions during operations and after Phase I ends to the presently existing conditions and provide data for the development of a preoperational monitoring plan

Technical specifications for the Pajarito Site Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.; Paxton, H.C.

1980-12-01

This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

Yucca Mountain Site Characterization Project: Technical data catalog,(quarterly supplement)

International Nuclear Information System (INIS)

1993-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year

Technical guidance for siting criteria development

International Nuclear Information System (INIS)

Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.

1982-12-01

Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness

Technical guidance for siting criteria development

Energy Technology Data Exchange (ETDEWEB)

Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

1982-12-01

Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

Technical database and management system (DBMS) for the UMTRA project processing sites

International Nuclear Information System (INIS)

Hillman, R.L.; Mohr, D.E.

1985-01-01

The technical DBMS is a structured and organized method for collecting, storing, retrieving, and analyzing technical data based upon standard operating procedures and quality control measures. The automated environment created by this design exists both as a repository for processing site technical data and the analysis techniques used against this data for site characterization, evaluation, and design. The system is composed of diverse technical subjects that are collectively used to address remedial action problems associated with mill tailings disposal. These technical subjects include hydrology, geology, geochemistry, radiology, and engineering

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults

Office of Civilian Radioactive Waste Management Program Cost and Schedule Baseline

International Nuclear Information System (INIS)

1992-09-01

The purpose of this document is to establish quantitative expressions of proposed costs and schedule to serve as a basis for measurement of program performance. It identifies the components of the Program Cost and Schedule Baseline (PCSB) that will be subject to change control by the Executive (Level 0) and Program (Level 1) Change Control Boards (CCBS) and establishes their baseline values. This document also details PCSB reporting, monitoring, and corrective action requirements. The Program technical baseline contained in the Waste Management System Description (WMSD), the Waste Management System Requirements (WMSR), and the Physical System Requirements documents provide the technical basis for the PCSB. Changes to the PCSB will be approved by the Pregrain Change Control Board (PCCB)In addition to the PCCB, the Energy System Acquisition Advisory Board Baseline CCB (ESAAB BCCB) will perform control functions relating to Total Project Cost (TPC) and major schedule milestones for the Yucca Mountain Site Characterization Project and the Monitored Retrievable Storage (MRS) Project

Safety evaluation of the ESP sludge washing baselines runs. Revision 2

International Nuclear Information System (INIS)

Gupta, M.K.

1993-01-01

Purpose is to provide the technical basis for evaluation of unreviewed safety question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs, which are necessary to resolve technical questions associated with process control (sludge suspension, sludge settling, heat transfer, temperature control). The sludge is currently stored in below-ground tanks and will be prepared for processing at the Defense Waste Processing Facility as part of the Integrated Waste Removal Program for Savannah River Site

Hanford and Savannah River Site Programmatic and Technical Integration

International Nuclear Information System (INIS)

Ramsey, William Gene

2013-01-01

Abstract only. The Hanford Site and the Savannah River Site (SRS) were the primary plutonium production facilities within the U.S. nuclear weapons complex. Radioactive wastes were generated as part of these missions and are stored in similar fashion. The majority of radioactivity maintained by the two sites is located in underground carbon steel tanks in the physical form of supernatant, saltcake, or sludge. Disposition of SRS tank waste is ongoing by converting it into glass (pathway for sludge and radionuclides separated from supernatant or dissolved saltcake) or cement (pathway for the decontaminated supernatant and dissolved saltcake). Tank closure activity has also begun at SRS and will continue for the duration of mission. The Hanford tank waste inventory is roughly 2/3rds larger than SRS's by volume- but nominally half the radioactivity. The baseline disposition path includes high-level and low-activity waste vitrification with separate disposition of contact-handled transuranic tank waste. Retrieval of tank waste from aging single shell tanks (SSTs) into double-shell tanks (DSTs) is currently ongoing. As vitrification commences later this decade, Hanford will be in a similar operations mode as SRS. Site integration is increasing as the missions align. The ongoing integration is centered on key issues that impact both sites- regardless of mission timeframe. Three recent workshop exchanges have been held to improve communication with the primary intent of improving operations and technical work organization. The topics of these workshops are as follows: DST space utilization, optimization, and closure; Waste Feed Qualification; and, Cementitious Waste Forms. Key goals for these and future exchanges include aligning research and technology, preparing for joint initiatives (to maximize budgetary value for the customer), and reviewing lessons learned. Each site has played a leading role in the development of technology and operational practices that can be used

Estimating baseline risks from biouptake and food ingestion at a contaminated site

International Nuclear Information System (INIS)

MacDonell, M.; Woytowich, K.; Blunt, D.; Picel, M.

1993-01-01

Biouptake of contaminants and subsequent human exposure via food ingestion represents a public concern at many contaminated sites. Site-specific measurements from plant and animal studies are usually quite limited, so this exposure pathway is often modeled to assess the potential for adverse health effects. A modeling tool was applied to evaluate baseline risks at a contaminated site in Missouri, and the results were used to confirm that ingestion of fish and game animals from the site area do not pose a human health threat. Results were also used to support the development of cleanup criteria for site soil

Prioritizing sites for conservation based on similarity to historical baselines and feasibility of protection.

Science.gov (United States)

Popejoy, Traci; Randklev, Charles R; Neeson, Thomas M; Vaughn, Caryn C

2018-05-08

The shifting baseline syndrome concept advocates for the use of historical knowledge to inform conservation baselines, but does not address the feasibility of restoring sites to those baselines. In many regions, conservation feasibility varies among sites due to differences in resource availability, statutory power, and land-owner participation. We use zooarchaeological records to identify a historical baseline of the freshwater mussel community's composition before Euro-American influence at a river-reach scale. We evaluate how the community reference position and the feasibility of conservation might enable identification of sites where conservation actions would preserve historically representative communities and be likely to succeed. We first present a conceptual model that incorporates community information and landscape factors to link the best conservation areas to potential cost and conservation benefits. Using fuzzy ordination, we identify modern mussel beds that are most like the historical baseline. We then quantify the housing density and land use near each reach to estimate feasibility of habitat restoration. Using our conceptual framework, we identify reaches that have high conservation value (i.e., reaches that contain the best mussel beds) and where restoration actions would be most likely to succeed. Reaches above Lake Belton in central Texas, U.S.A. were most similar in species composition and relative abundance to zooarchaeological sites. A subset of these mussel beds occurred in locations where conservation actions appear to be most feasible. This study demonstrates how to use zooarchaeological data (biodiversity data often readily available) and estimates of conservation feasibility to inform conservation priorities at a local spatial scale. This article is protected by copyright. All rights reserved.

Site Screening and Technical Guidance for Monitored Natural Attenuation at DOE Sites

Energy Technology Data Exchange (ETDEWEB)

Borns, D.J.; Brady, P.V.; Brady, W.D.; Krupka, K.M.; Spalding, B.P.; Waters, R.D.; Zhang, P.

1999-03-01

Site Screening and Technical Guidance for Monitored Natural Attenuation at DOE Sites briefly outlines the biological and geochemical origins of natural attenuation, the tendency for natural processes in soils to mitigate contaminant transport and availability, and the means for relying on monitored natural attenuation (MNA) for remediation of contaminated soils and groundwaters. This report contains a step-by-step guide for (1) screening contaminated soils and groundwaters on the basis of their potential for remediation by natural attenuation and (2) implementing MNA consistent with EPA OSWER Directive 9200.4-17. The screening and implementation procedures are set up as a web-based tool (http://www.sandia.gov/eesector/gs/gc/na/mnahome.html) to assist US Department of Energy (DOE) site environmental managers and their staff and contractors to adhere to EPA guidelines for implementing MNA. This document is intended to support the Decision Maker's Framework Guide and Monitoring Guide both to be issued from DOE EM-40. Further technical advances may cause some of the approach outlined in this document to change over time.

Technical advisory on SSC site criteria and catalog of site information needs

Energy Technology Data Exchange (ETDEWEB)

1985-06-15

The Superconducting Super Collider, or SSC, is a proposed scientific instrument of the study of the fundamental nature of matter. In the SSC two 20-TeV beams of protons will be accelerated and counter circulate on an approximately circular path. The protons will be made to collide at six locations where detectors can be placed to count and measure the products of the collisions. These collisions, twenty times more energetic than in any existing facility, will enable scientists to probe deeper into the heart of matter in the quest for a deeper understanding of the universal forces of nature. The goal of the SSC project is to create a scientific laboratory in high energy physics whose facilities are unique. Ultimately the success of that laboratory will be measured by its scientific discoveries, measurements, interpretations, and innovations. Toward that end the accelerator-collider must be constructed to high standards at minimum cost and maximum effectiveness. Preparations must be made for future operations and a scientific-technical staff attracted and maintained. The chosen site must accommodate all of these factors. This document summarizes siting criteria for the SSC and enumerates site-specific information important to the evaluation of potential sites. This document is not a call for site proposals but a technical report prepared for the information and use of the Department of Energy (DOE).

Configuration management program plan for Hanford site systems engineering

International Nuclear Information System (INIS)

Hoffman, A.G.

1994-01-01

This plan establishes the integrated configuration management program for the evolving technical baseline developed through the systems engineering process. This configuration management program aligns with the criteria identified in the DOE Standard, DOE-STD-1073-93. Included are specific requirements for control of the systems engineering RDD-100 database, and electronic data incorporated in the database that establishes the Hanford site technical baseline

Information architecture. Volume 2, Part 1: Baseline analysis summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

The Department of Energy (DOE) Information Architecture, Volume 2, Baseline Analysis, is a collaborative and logical next-step effort in the processes required to produce a Departmentwide information architecture. The baseline analysis serves a diverse audience of program management and technical personnel and provides an organized way to examine the Department`s existing or de facto information architecture. A companion document to Volume 1, The Foundations, it furnishes the rationale for establishing a Departmentwide information architecture. This volume, consisting of the Baseline Analysis Summary (part 1), Baseline Analysis (part 2), and Reference Data (part 3), is of interest to readers who wish to understand how the Department`s current information architecture technologies are employed. The analysis identifies how and where current technologies support business areas, programs, sites, and corporate systems.

Brownfields Green Avenue Sites: Technical Memorandum - Conceptual Design for Sustainable Redevelopment

Science.gov (United States)

This technical memorandum briefly describes the site and proposed conceptual site plan, indicates conceptual design considerations, specifies recommended green and sustainable features, and offers other recommendations

Technical procedures for water resources, Deaf Smith County site, Texas: Volume 2: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains the following Technical Procedures pursuant to the Water Resources Site Study Plan operation of a Playa Lake conductivity monitoring station and processing of data from a Playa Lake conductivity monitoring station. This procedure defines steps and methods for the installation, operation, and maintenance of the Playa Lake conductivity monitoring stations. Conductivity measurements will be taken at six playa lakes in the site study area to record changes in total dissolved solids as a function of stage. Playa lake conductivity and stage (volume) measurements will be used, in conjunction with other water quality data collected at the Playa Lake and precipitation stations, to determine the mass of dissolved solids entering and leaving the playas. This baseline information on the pollutant mass balance of the playas will be used to assess potential changes in playa lake water quality and the magnitude of those changes due to site development. The pollutant mass balances will also be used on determining the source of pollutants. 2 refs., 5 figs

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 2, Revision 2

International Nuclear Information System (INIS)

Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

1996-12-01

This document is Volume 2 in a two-volume series that comprise the site characterization report, the Preoperational Baseline and Site Characterization Report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; preoperational baseline chemical data and aquifer test data. Five groundwater monitoring wells, six deep characterization boreholes, and two shallow characterization boreholes were drilled at the Environmental Restoration Disposal Facility (ERDF) site to directly investigate site-specific hydrogeologic conditions

Technical Assessment Of Selection Of A Waste Disposal Site

International Nuclear Information System (INIS)

Lee, Bong Hun

1992-04-01

This book gives overall descriptions of technical assessment of selection of a waste disposal site, which deals with standard of selection on incinerator of city waste, the method over assessment of selection of incinerator in city waste, prerequisite of technical assessment for selection of incinerator, waste incinerator and related equipment such as form, structure, quality of material, ventilation device, plumbing system and electrical installation, and total plan like plan of construction and a measure taken against environmental pollution.

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility

International Nuclear Information System (INIS)

Weekes, D.C.; Ford, B.H.; Jaeger, G.K.

1996-09-01

This document Volume 2 in a two-volume series that comprise the site characterization report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; and preoperational baseline chemical data and aquifer test data. This does not represent the entire body of data available. Other types of information are archived at BHI Document Control. Five ground water monitoring wells were drilled at the Environmental Restoration Disposal Facility site to directly investigate site- specific hydrogeologic conditions. Well and borehole activity summaries are presented in Volume 1. Field borehole logs and geophysical data from the drilling are presented in this document. Well development and pump installation sheets are presented for the groundwater monitoring wells. Other data presented in this document include borehole geophysical logs from existing wells; chemical data from the sampling of soil, vegetation, and mammals from the ERDF to support the preoperational baseline; ERDF surface radiation surveys;a nd aquifer testing data for well 699-32-72B

Program Baseline Change Control Procedure

International Nuclear Information System (INIS)

1993-02-01

This procedure establishes the responsibilities and process for approving initial issues of and changes to the technical, cost, and schedule baselines, and selected management documents developed by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System. This procedure implements the OCRWM Baseline Management Plan and DOE Order 4700.1, Chg 1. It streamlines the change control process to enhance integration, accountability, and traceability of Level 0 and Level I decisions through standardized Baseline Change Proposal (BCP) forms to be used by the Level 0, 1, 2, and 3 Baseline Change Control Boards (BCCBs) and to be tracked in the OCRWM-wide Configuration Information System (CIS) Database.This procedure applies to all technical, cost, and schedule baselines controlled by the Energy System Acquisition Advisory Board (ESAAB) BCCB (Level 0) and, OCRWM Program Baseline Control Board (PBCCB) (Level 1). All baseline BCPs initiated by Level 2 or lower BCCBs, which require approval from ESAAB or PBCCB, shall be processed in accordance with this procedure. This procedure also applies to all Program-level management documents controlled by the OCRWM PBCCB

Risk-based technical specifications program: Site interview results

International Nuclear Information System (INIS)

Andre, G.R.; Baker, A.J.; Johnson, R.L.

1991-08-01

The Electric Power Research Institute and Pacific Gas and Electric Company are sponsoring a program directed at improving Technical Specifications using risk-based methods. The major objectives of the program are to develop risk-based approaches to improve Technical Specifications and to develop an Interactive Risk Advisor (IRA) prototype. The IRA is envisioned as an interactive system that is available to plant personnel to assist in controlling plant operation. Use of an IRA is viewed as a method to improve plant availability while maintaining or improving plant safety. In support of the program, interviews were conducted at several PWR and BWR plant sites, to elicit opinions and information concerning risk-based approaches to Technical Specifications and IRA requirements. This report presents the results of these interviews, including the functional requirements of an IRA. 2 refs., 6 figs., 2 tabs

Web-based Tool Identifies and Quantifies Potential Cost Savings Measures at the Hanford Site

International Nuclear Information System (INIS)

Renevitz, Marisa J.; Peschong, Jon C.; Charboneau, Briant L.; Simpson, Brett C.

2014-01-01

The Technical Improvement system is an approachable web-based tool that is available to Hanford DOE staff, site contractors, and general support service contractors as part of the baseline optimization effort underway at the Hanford Site. Finding and implementing technical improvements are a large part of DOE's cost savings efforts. The Technical Improvement dashboard is a key tool for brainstorming and monitoring the progress of submitted baseline optimization and potential cost/schedule efficiencies. The dashboard is accessible to users over the Hanford Local Area Network (HLAN) and provides a highly visual and straightforward status to management on the ideas provided, alleviating the need for resource intensive weekly and monthly reviews

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site in Lakeview, Oregon

International Nuclear Information System (INIS)

1994-10-01

This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site in Lake view, Oregon evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site in Lakeview, Oregon

Energy Technology Data Exchange (ETDEWEB)

1994-10-01

This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site in Lake view, Oregon evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site.

Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado

International Nuclear Information System (INIS)

1994-11-01

This baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado, evaluates potential public health and environmental impacts resulting from ground water contamination at the former North Continent (NC) and Union Carbide (UC) uranium mill processing sites. The tailings at these sites will be placed in a disposal cell at the proposed Burro Canyon, Colorado, site. The US Department of Energy (DOE) anticipates the start of the first phase remedial action by the spring of 1995 under the direction of the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project will evaluate ground water contamination. This baseline risk assessment is the first site-specific document for these sites under the Ground Water Project. It will help determine the compliance strategy for contaminated ground water at the site. In addition, surface water and sediment are qualitatively evaluated in this report

Baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado

Energy Technology Data Exchange (ETDEWEB)

1994-11-01

This baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado, evaluates potential public health and environmental impacts resulting from ground water contamination at the former North Continent (NC) and Union Carbide (UC) uranium mill processing sites. The tailings at these sites will be placed in a disposal cell at the proposed Burro Canyon, Colorado, site. The US Department of Energy (DOE) anticipates the start of the first phase remedial action by the spring of 1995 under the direction of the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project will evaluate ground water contamination. This baseline risk assessment is the first site-specific document for these sites under the Ground Water Project. It will help determine the compliance strategy for contaminated ground water at the site. In addition, surface water and sediment are qualitatively evaluated in this report.

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

International Nuclear Information System (INIS)

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development.

Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-09-01

The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

Evaluation of a committed fusion site. Final report

International Nuclear Information System (INIS)

1979-07-01

This report is divided into five technical sections. Section 2 is a summary. In Section 3, which covers device and site analyses the major characteristics of devices that might be placed at the site, as envisioned by major fusion laboratories, are described; the characteristics of a site (baseline site) which would accommodate these devices are defined; and various approaches to a committed site meeting the baseline site requirements are discussed. Section 4 describes the scenarios selected to represent possible site development outcomes; these scenarios are evaluated with respect to comparative cost and schedule effects. Section 5 presents a brief evaluation of the effects fusion-fission hybrids might have on the committed site. Major conclusions and recommendations are discussed in Section 6

Design Study for a Future Laguna-LBNO Long-Baseline Neutrino Facility at CERN

CERN Document Server

Alabau-Gonzalvo, J; Antoniou, F; Benedikt, M; Calviani, M; Efthymiopoulos, I; Ferrari, A; Garoby, R; Gerigk, F; Gilardoni, S; Goddard, B; Kosmicki, A; Lazaridis, C; Osborne, J; Papaphillippou, Y; Parfenova, A; Shaposhnikova, E; Steerenberg, R; Velten, P; Vincke, H

2013-01-01

The Large Apparatus studying Grand Unification and Neutrino Astrophysics (LAGUNA) study [1] investigated seven pre-selected underground sites in Europe (Finland, France, Italy, Poland, Romania, Spain and UK), capable of housing large volume detectors for terrestrial, accelerator generated and astrophysical neutrino research. The study was focused on geo-technical assessment of the sites, concluding that no show-stoppers exist for the construction of the required large underground caverns in the chosen sites. The LAGUNA-LBNO FP7/EC-funded design study extends the LAGUNA study in two key aspects: the detailed engineering of detector construction and operation, and the study of a long-baseline neutrino beam from CERN, and possibly other accelerator centres in Europe. Based on the findings of the LAGUNA study, the Pyh¨asalmi mine in Finland is chosen as prime site for the far detector location. The mine offers the deepest underground location in Europe (-1400 m) and a baseline of 2’300 km from CERN (Fig. 1). ...

Logistics Operations Management Center: Maintenance Support Baseline (LOMC-MSB)

Science.gov (United States)

Kurrus, R.; Stump, F.

1995-01-01

The Logistics Operations Management Center Maintenance Support Baseline is defined. A historical record of systems, applied to and deleted from, designs in support of future management and/or technical analysis is provided. All Flight elements, Ground Support Equipment, Facility Systems and Equipment and Test Support Equipment for which LOMC has responsibilities at Kennedy Space Center and other locations are listed. International Space Station Alpha Program documentation is supplemented. The responsibility of the Space Station Launch Site Support Office is established.

SCFA lead lab technical assistance at Lawrence Berkeley National Laboratory: Baseline review of three groundwater plumes

Energy Technology Data Exchange (ETDEWEB)

Hazen, Terry; et al.

2002-09-26

During the closeout session, members of the technical assistance team conveyed to the site how impressed they were at the thoroughness of the site's investigation and attempts at remediation. Team members were uniformly pleased at the skilled detection work to identify sources, make quick remediation decisions, and change course when a strategy did not work well. The technical assistance team also noted that, to their knowledge, this is the only DOE site at which a world-class scientist has had primary responsibility for the environmental restoration activities. This has undoubtedly contributed to the successes observed and DOE should take careful note. The following overall recommendations were agreed upon: (1) The site has done a phenomenal job of characterization and identifying and removing source terms. (2) Technologies selected to date are appropriate and high impact, e.g. collection trenches are an effective remedial strategy for this complicated geology. The site should continue using technology that is adapted to the site's unique geology, such as the collection trenches. (3) The site should develop a better way to determine the basis of cleanup for all sites. (4) The sentinel well system should be evaluated and modified, if needed, to assure that the sentinel wells provide coverage to the current site boundary. Potential modifications could include installation, abandonment or relocation of wells based on the large amount of data collected since the original sentinel well system was designed. (5) Modeling to assist in remedial design and communication should continue. (6) The site should develop a plan to ensure institutional memory. (7) The most likely possibility for improving closure to 2006 is by removing the residual source of the Old Town plume and establishing the efficacy of remediation for the 51/64 plume.

Establishment of control site baseline data for erosion studies using radionuclides: a case study in East Slovenia

Energy Technology Data Exchange (ETDEWEB)

Mabit, Lionel, E-mail: L.Mabit@iaea.or [Soil Science Unit, FAO/IAEA Agriculture and Biotechnology Laboratory, IAEA Laboratories Seibersdorf, PO Box 100, Wagramerstrasse 5, A-1400 Vienna (Austria); Martin, Paul [Physics, Chemistry and Instrumentation Laboratory, IAEA Laboratories Seibersdorf, PO Box 100, Wagramerstrasse 5, A-1400 Vienna (Austria); Jankong, Patcharin; Toloza, Arsenio [Soil Science Unit, FAO/IAEA Agriculture and Biotechnology Laboratory, IAEA Laboratories Seibersdorf, PO Box 100, Wagramerstrasse 5, A-1400 Vienna (Austria); Padilla-Alvarez, Roman [Physics, Chemistry and Instrumentation Laboratory, IAEA Laboratories Seibersdorf, PO Box 100, Wagramerstrasse 5, A-1400 Vienna (Austria); Zupanc, Vesna [Department of Agronomy, Biotechnical Faculty, University of Ljubljana (Slovenia)

2010-10-15

The aim of the present study was to establish a reference site and its soil characteristics for use of fallout radionuclides in erosion studies in Slovenia. Prior to this study, no reference site and baseline data existed for Slovenia for this purpose. In the agricultural area of Goricko in East Slovenia, an undisturbed forest situated in Salamenci (46{sup o}44'N, 16{sup o}7'E), was selected to establish the inventory value of fallout {sup 137}Cs and to establish a baseline level of multi-elemental fingerprint (major, minor, trace elements including heavy metals) and naturally occurring radionuclides in soils. A total of 20 soil profiles were collected at four 10 cm depth increments for evaluation of baseline level of {sup 137}Cs inventory. An exponential distribution for {sup 137}Cs was found and the baseline level inventory was established at 7300 {+-} 2500 Bq m{sup -2} with a coefficient of variation of 34%. Of this mean present-day inventory, approximately 45% is due to the Chernobyl contribution. The physical degradation of soils through erosion is linked with biochemical degradation. This study introduces an approach to establishment of the naturally occurring radionuclide and elemental fingerprints baseline levels at a reference site which can provide comparative data to those from neighbouring agricultural fields for assessment of soil redistribution magnitude using fallout radionuclides. In addition, this information will be used to determine the impact of soil erosion processes and agricultural practices on soil quality and redistribution within agricultural landscapes in Slovenia.

Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1984-05-25

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

75 FR 11921 - Heritage Aviation, Ltd., Including On-Site Leased Workers From Global Technical Services and...

Science.gov (United States)

2010-03-12

... DEPARTMENT OF LABOR Employment and Training Administration [TA-W-72,924] Heritage Aviation, Ltd., Including On-Site Leased Workers From Global Technical Services and Global, Inc. (Global Employment... from Heritage Aviation, Ltd, including on-site leased workers from Global Technical Services, Grand...

Baseline report - tall upland shrubland at the Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1997-03-01

Rocky Flats Environmental Technology Site (Site) is located on the Colorado Piedmont east of the Front Range between Boulder and Golden. At an elevation of approximately 6,000 feet, the Site contains a unique ecotonal mixture of mountain and prairie plant species, resulting from the topography and close proximity to the mountain front. The Buffer Zone surrounding the Industrial Area is one of the largest remaining undeveloped areas of its kind along the Colorado Piedmont. A number of plant communities at the Site have been identified as increasingly rare and unique by Site ecologists and the Colorado Natural Heritage Program (CNHP). These include the xeric tallgrass prairie, tall upland shrubland, wetlands, and Great Plains riparian woodland communities. Many of these communities support populations of increasingly rare animals as well, including the Preble's meadow jumping mouse, grasshopper sparrow, loggerhead shrike, Merriam's shrew, black crowned night heron, and Hops blue and Argos skipper butterflies. One of the more interesting and important plant communities at the Site is the tall upland shrubland community. It has been generally overlooked by previous Site ecological studies, probably due to its relatively small size; only 34 acres total. Although mentioned in a plant community ordination study conducted by Clark et al. and also in the Site baseline ecological study, few data were available on this plant community before the present study

Baseline report - tall upland shrubland at the Rocky Flats Environmental Technology Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

Rocky Flats Environmental Technology Site (Site) is located on the Colorado Piedmont east of the Front Range between Boulder and Golden. At an elevation of approximately 6,000 feet, the Site contains a unique ecotonal mixture of mountain and prairie plant species, resulting from the topography and close proximity to the mountain front. The Buffer Zone surrounding the Industrial Area is one of the largest remaining undeveloped areas of its kind along the Colorado Piedmont. A number of plant communities at the Site have been identified as increasingly rare and unique by Site ecologists and the Colorado Natural Heritage Program (CNHP). These include the xeric tallgrass prairie, tall upland shrubland, wetlands, and Great Plains riparian woodland communities. Many of these communities support populations of increasingly rare animals as well, including the Preble`s meadow jumping mouse, grasshopper sparrow, loggerhead shrike, Merriam`s shrew, black crowned night heron, and Hops blue and Argos skipper butterflies. One of the more interesting and important plant communities at the Site is the tall upland shrubland community. It has been generally overlooked by previous Site ecological studies, probably due to its relatively small size; only 34 acres total. Although mentioned in a plant community ordination study conducted by Clark et al. and also in the Site baseline ecological study, few data were available on this plant community before the present study.

Technical data management at the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Statler, J.; Newbury, C.M.; Heitland, G.W.

1992-01-01

The Department of Energy/Office of Civilian Radioactive waste Management (DOE/OCRWM) is responsible for the characterization of Yucca Mountain, Nevada, to determine its potential as a site of a high-level radioactive waste repository. The characterization of Yucca Mountain encompasses many diverse investigations, both onsite and in laboratories across the country. Investigations are being conducted of the geology, hydrology, mineralogy, paleoclimate, geotechnical properties, and archeology of the area, to name a few. Effective program management requires that data from site investigations be processed, interpreted and disseminated in a timely manner to support model development and validation, repository design, and performance assessment. The Program must also meet regulatory requirements for making the technical data accessible to a variety of external users throughout the life of the Project. Finally, the DOE/OCRWM must make available the data or its description and access location available for use in support of the license application and supporting documentation. To accomplish these objectives, scientific and engineering data, generated by site characterization activities, and technical data, generated by environmental and socioeconomic impact assessment activities, must be systematically identified, cataloged, stored and disseminated in a controlled manner

Criteria and technical concept for demonstrating greater confinement disposal of radioactive wastes at Arid Western Sites

International Nuclear Information System (INIS)

Hunter, P.H.

1981-01-01

This report summarizes the work of two documents; the Criteria for Greater Confinement of Radioactive Wastes at Arid Western Sites, NVO-234, March 1981, (within this report, referred to as the GCDF Criteria Document); and the Draft Technical Concept for a Test of Greater Confinement Disposal of Radioactive Waste in Unsaturated Media at the Nevada Test Site, FBDU-343-004, June 1981, (referred within this report as the Technical Concept for the GCDF). For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in development of defense low-level waste management concepts, including the greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which we published in May of this year; then the draft for the technical concept for greater confinement disposal, published in June; leading up to the point where we are now. The final technical concept and design specifications should be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

International Nuclear Information System (INIS)

1992-07-01

The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

SRP baseline hydrogeologic investigation: Aquifer characterization. Groundwater geochemistry of the Savannah River Site and vicinity

Energy Technology Data Exchange (ETDEWEB)

Strom, R.N.; Kaback, D.S.

1992-03-31

An investigation of the mineralogy and chemistry of the principal hydrogeologic units and the geochemistry of the water in the principal aquifers at Savannah River Site (SRS) was undertaken as part of the Baseline Hydrogeologic Investigation. This investigation was conducted to provide background data for future site studies and reports and to provide a site-wide interpretation of the geology and geochemistry of the Coastal Plain Hydrostratigraphic province. Ground water samples were analyzed for major cations and anions, minor and trace elements, gross alpha and beta, tritium, stable isotopes of hydrogen, oxygen, and carbon, and carbon-14. Sediments from the well borings were analyzed for mineralogy and major and minor elements.

100-B area technical baseline report

International Nuclear Information System (INIS)

Carpenter, R.W.

1994-01-01

This document supports the environmental remediation effort of the 100-B Area by providing remediation planners with key data that characterize the 100-B and 100-C Reactor sites. It provides operational histories of the 100-B and 100-C Reactors and each of their associated liquid and solid waste sites

100-B area technical baseline report

Energy Technology Data Exchange (ETDEWEB)

Carpenter, R.W.

1994-09-01

This document supports the environmental remediation effort of the 100-B Area by providing remediation planners with key data that characterize the 100-B and 100-C Reactor sites. It provides operational histories of the 100-B and 100-C Reactors and each of their associated liquid and solid waste sites.

Technical Evaluation of Soil Remediation Alternatives at the Building 812 Operable Unit, Lawrence Livermore National Laboratory Site 300

International Nuclear Information System (INIS)

Eddy-Dilek, C.; Miles, D.; Abitz, R.

2009-01-01

implement the recommended phased approach, the cost of characterization, excavation and physical treatment of the contaminated materials is roughly estimated to be one third to one fourth of the cost of the current baseline treatment. This is an estimated cost; the actual cost of the project will be sensitive to actual soil/sediment volumes that can be refined with the results from characterization studies. The technical team encourages the site to promote a more holistic approach during remediation of contaminated sediments at Site 300. It is true that the presence of low levels of residual DU on the steep slopes may stress the ecosystem, as it is not possible to block the exposure of resident biota. It is clear that remediation of the primary source areas will reduce potential effects to humans. However, the site should consider that excavation of the slopes will profoundly disrupt the ecosystem and it may take decades to recover.

TECHNICAL EVALUATION OF SOIL REMEDIATION ALTERNATIVES AT THE BUILDING 812 OPERABLE UNIT, LAWRENCE LIVERMORE NATIONAL LABORATORY SITE 300

Energy Technology Data Exchange (ETDEWEB)

Eddy-Dilek, C.; Miles, D.; Abitz, R.

2009-08-14

decision to implement the recommended phased approach, the cost of characterization, excavation and physical treatment of the contaminated materials is roughly estimated to be one third to one fourth of the cost of the current baseline treatment. This is an estimated cost; the actual cost of the project will be sensitive to actual soil/sediment volumes that can be refined with the results from characterization studies. The technical team encourages the site to promote a more holistic approach during remediation of contaminated sediments at Site 300. It is true that the presence of low levels of residual DU on the steep slopes may stress the ecosystem, as it is not possible to block the exposure of resident biota. It is clear that remediation of the primary source areas will reduce potential effects to humans. However, the site should consider that excavation of the slopes will profoundly disrupt the ecosystem and it may take decades to recover.

Technical support for the EPA cleanup rule on radioactively contaminated sites

Energy Technology Data Exchange (ETDEWEB)

Hull, H.B.; Newman, A.; Wolbarst, A.B. [Environmental Protection Agency, Washington, DC (United States)] [and others

1995-12-31

The U.S. Environmental Protection Agency (EPA) is developing a radiation site cleanup regulation for the protection of the public from radionuclide contamination at sites that are to be cleaned up and released for public use. The regulation will apply to sites under the control of Federal agencies, and to sites licensed by the Nuclear Regulatory Commission (NRC) or NRC Agreement States. The agency is therefore conducting a comprehensive technical analysis aimed at developing information that will be used to support the rule. This presentation describes the regulation and the approach developed to determine how radiological health impacts and volumes of soil requiring remediation vary as functions of the possible cleanup dose or risk level.

Baseline design/economics for advanced Fischer-Tropsch technology. Quarterly report, January--March 1992

Energy Technology Data Exchange (ETDEWEB)

1992-09-01

The objectives of the study are to: Develop a baseline design for indirect liquefaction using advanced Fischer-Tropsch (F-T) technology. Prepare the capital and operating costs for the baseline design. Develop a process flow sheet simulation (PFS) model. This report summarizes the activities completed during the period December 23, 1992 through March 15, 1992. In Task 1, Baseline Design and Alternates, the following activities related to the tradeoff studies were completed: approach and basis; oxygen purity; F-T reactor pressure; wax yield; autothermal reformer; hydrocarbons (C{sub 3}/C{sub 4}s) recovery; and hydrogenrecovery. In Task 3, Engineering Design Criteria, activities were initiated to support the process tradeoff studies in Task I and to develop the environmental strategy for the Illinois site. The work completed to date consists of the development of the F-T reactor yield correlation from the Mobil dam and a brief review of the environmental strategy prepared for the same site in the direct liquefaction baseline study.Some work has also been done in establishing site-related criteria, in establishing the maximum vessel diameter for train sizing and in coping with the low H{sub 2}/CO ratio from the Shell gasifier. In Task 7, Project Management and Administration, the following activities were completed: the subcontract agreement between Amoco and Bechtel was negotiated; a first technical progress meeting was held at the Bechtel office in February; and the final Project Management Plan was approved by PETC and issued in March 1992.

Baseline risk assessment for groundwater contamination at the uranium mill tailings site near Monument Valley, Arizona

International Nuclear Information System (INIS)

1993-09-01

This baseline risk assessment evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site near Monument Valley, Arizona. The tailings and other contaminated material at this site are being relocated and stabilized in a disposal cell at Mexican Hat, Utah, through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The tailings removal is planned for completion by spring 1994. After the tailings are removed, groundwater contamination at the site will continue to be evaluated. This risk assessment is the first document specific to this site for the Groundwater Project. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site

Baseline risk assessment of ground water contamination at the uranium mill tailings site Salt Lake City, Utah

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This baseline risk assessment of groundwater contamination at the uranium mill tailings site near Salt Lake City, Utah, evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium ore processing site. The tailings and other contaminated material at this site were placed in a disposal cell located at Clive, Utah, in 1987 by the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate residual ground water contamination at the former uranium processing site, known as the Vitro processing site. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine the appropriate remedial action for contaminated ground water at the site.

Baseline risk assessment of ground water contamination at the uranium mill tailings site Salt Lake City, Utah

International Nuclear Information System (INIS)

1994-09-01

This baseline risk assessment of groundwater contamination at the uranium mill tailings site near Salt Lake City, Utah, evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium ore processing site. The tailings and other contaminated material at this site were placed in a disposal cell located at Clive, Utah, in 1987 by the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate residual ground water contamination at the former uranium processing site, known as the Vitro processing site. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine the appropriate remedial action for contaminated ground water at the site

Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

Integrated planning: A baseline development perspective

International Nuclear Information System (INIS)

Clauss, L.; Chang, D.

1994-01-01

The FEMP Baseline establishes the basis for integrating environmental activity technical requirements with their cost and schedule elements. The result is a path forward to successfully achieving the FERMCO mission. Specific to cost management, the FEMP Baseline has been incorporate into the FERMCO Project Control System (PCS) to provide a time-phased budget plan against which contractor performance is measured with an earned value management system. The result is the Performance Measurement Baseline (PMB), an important tool for keeping cost under control

Baseline development, economic risk, and schedule risk: An integrated approach

International Nuclear Information System (INIS)

Tonkinson, J.A.

1994-01-01

The economic and schedule risks of Environmental Restoration (ER) projects are commonly analyzed toward the end of the baseline development process. Risk analysis is usually performed as the final element of the scheduling or estimating processes for the purpose of establishing cost and schedule contingency. However, there is an opportunity for earlier assessment of risks, during development of the technical scope and Work Breakdown Structure (WBS). Integrating the processes of risk management and baselining provides for early incorporation of feedback regarding schedule and cost risk into the proposed scope of work. Much of the information necessary to perform risk analysis becomes available during development of the technical baseline, as the scope of work and WBS are being defined. The analysis of risk can actually be initiated early on during development of the technical baseline and continue throughout development of the complete project baseline. Indeed, best business practices suggest that information crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

Waters, R.D.; Gruebel, M.M. [eds.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site

10 CFR Appendix III to Part 960 - Application of the System and Technical Guidelines During the Siting Process

Science.gov (United States)

2010-01-01

... 960—Application of the System and Technical Guidelines During the Siting Process 1. This appendix... 10 Energy 4 2010-01-01 2010-01-01 false Application of the System and Technical Guidelines During the Siting Process III Appendix III to Part 960 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE...

Savannah River Site production reactor technical specifications. K Production Reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

Baseline risk assessment of groundwater contamination at the Uranium Mill Tailings Site near Gunnison, Colorado

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

This Baseline Risk Assessment of Groundwater Contamination at the Uranium Mill Tailings Site Near Gunnison, Colorado evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells. This risk assessment evaluates the most contaminated monitor wells at the processing site. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium.

Baseline risk assessment of groundwater contamination at the Uranium Mill Tailings Site near Gunnison, Colorado

International Nuclear Information System (INIS)

1993-12-01

This Baseline Risk Assessment of Groundwater Contamination at the Uranium Mill Tailings Site Near Gunnison, Colorado evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells. This risk assessment evaluates the most contaminated monitor wells at the processing site. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium

Baseline risk assessment of ground water contamination at the inactive uriniferous lignite ashing site near Belfield, North Dakota

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-08-01

This Baseline Risk Assessment of Ground Water Contamination at the Inactive Uraniferous Lignite Ashing Site Near Belfield, North Dakota, evaluates potential impacts to public health or the environment resulting from ground water contamination at the site where coal containing uranium was burned to produce uranium. The US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project is evaluating plans to remedy soil and ground water contamination at the site. Phase I of the UMTRA Project consists of determining the extent of soil contamination. Phase II of the UMTRA Project consists of evaluating ground water contamination. Under Phase II, results of this risk assessment will help determine what remedial actions may be necessary for contaminated ground water at the site. This risk assessment evaluates the potential risks to human health and the environment resulting from exposure to contaminated ground water as it relates to historic processing activities at the site. Potential risk is quantified for constituents introduced from the processing activities, and not for those constituents naturally occurring in water quality in the site vicinity. Background ground water quality has the potential to cause adverse health effects from exposure through drinking. Any risks associated with contaminants attributable to site activities are incremental to these risks from background ground water quality. This incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition.

Baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Belfield, North Dakota

International Nuclear Information System (INIS)

1994-08-01

This Baseline Risk Assessment of Ground Water Contamination at the Inactive Uraniferous Lignite Ashing Site Near Belfield, North Dakota, evaluates potential impacts to public health or the environment resulting from ground water contamination at the site where coal containing uranium was burned to produce uranium. The US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project is evaluating plans to remedy soil and ground water contamination at the site. Phase I of the UMTRA Project consists of determining the extent of soil contamination. Phase II of the UMTRA Project consists of evaluating ground water contamination. Under Phase II, results of this risk assessment will help determine what remedial actions may be necessary for contaminated ground water at the site. This risk assessment evaluates the potential risks to human health and the environment resulting from exposure to contaminated ground water as it relates to historic processing activities at the site. Potential risk is quantified for constituents introduced from the processing activities, and not for those constituents naturally occurring in water quality in the site vicinity. Background ground water quality has the potential to cause adverse health effects from exposure through drinking. Any risks associated with contaminants attributable to site activities are incremental to these risks from background ground water quality. This incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition

Independent technical reviews for groundwater and soil remediation projects at US Department Of Energy sites - 59188

International Nuclear Information System (INIS)

Kaback, Dawn S.; Chamberlain, Grover; Morse, John G.; Petersen, Scott W.

2012-01-01

The US Department of Energy Office of Environmental Management has supported independent technical reviews of soil and groundwater projects at multiple DOE sites over the last 10 years. These reviews have resulted in significant design improvements to remedial plans that have accelerated cleanup and site closure. Many have also resulted in improved understanding of complex subsurface conditions, promoting better approaches to design and implementation of new technologies. Independent technical reviews add value, because they provide another perspective to problem solving and act as a check for especially challenging problems. By bringing in a team of independent experts with a broad experience base, alternative solutions are recommended for consideration and evaluation. In addition, the independence of the panel is significant, because it is able to address politically sensitive issues. The expert panel members typically bring lessons learned from other sites to help solve the DOE problems. In addition, their recommendations at a particular site can often be applied at other sites, making the review even more valuable. The review process can vary, but some common lessons ensure a successful review: - Use a multi-disciplinary broadly experienced team; - Engage the panel early and throughout the project; - Involve regulators and stakeholders in the workshop, if appropriate. - Provide sufficient background information; - Close the workshop with a debriefing followed by a written report. Many groundwater remediation challenges remain at DOE sites. Independent technical reviews have and will ensure that the best capabilities and experience are applied to reduce risks and uncertainties. Even though the groundwater remediation industry has developed significantly over the last twenty years, advancements are needed to address the complexities of the subsurface at the DOE sites. These advancements have tremendous potential to save millions of dollars and to accelerate the

Baseline Assessment of Petroleum Contamination and Soil Properties at Contaminated Sites in Utqiagvik, Alaska

Science.gov (United States)

2017-08-01

microbial community, including high bacterial numbers in these soils. The results from this baseline study indicate that stimulating biodegradation...CEERD-RR), ERDC- CRREL. At the time of publication, Dr. Justin Berman was Chief, CEERD- RRN; CDR J. D. Horne, USN (Ret), was Chief, CEERD-RR; and Dr...of the fractions of petroleum hydrocarbons and microbial activity in ERDC/CRREL TR-17-13 3 situ to reveal the status of each site at the time of

Baseline risk assessment for groundwater contamination at the uranium mill tailings site near Monument Valley, Arizona. Draft

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

This baseline risk assessment evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site near Monument Valley, Arizona. The tailings and other contaminated material at this site are being relocated and stabilized in a disposal cell at Mexican Hat, Utah, through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The tailings removal is planned for completion by spring 1994. After the tailings are removed, groundwater contamination at the site will continue to be evaluated. This risk assessment is the first document specific to this site for the Groundwater Project. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site.

Low-level waste disposal site geotechnical subsidence corrective measures: technical progress

International Nuclear Information System (INIS)

Phillips, S.J.; Winterhalder, J.A.; Gilbert, T.W.

1983-01-01

A geotechnical test facility has been constructed at the Hanford Site Richland Site Richland, Washington. The purpose of this facility is to quantitatively evaluate the performance of alternative technologies to ameliorate geomechanical subsidence in solid waste burial structures. Alternatives to be tested include; accelerating mass ground surface impact, and two optional subsurface rod injection/withdrawal techniques. The alternatives involve the principle of dynamic consolidation of buried waste and matrix materials. A description of the geotechnical test facility, the monitoring instrumentation used therein, laboratory soil mechanics data evaluation, and facility baseline monitoring data are presented. 6 references, 5 figures

Technical procedures for implementation of acoustics site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-09-01

The purpose and scope of the technical procedure for processing data from the tethered meteorological system are covered. Definitions, interfaces, and concurrent data needs are also addressed. This technical procedure describes how to control, organize, verify, and archive tethered meteorological system data. These data will be received at the processing location from the field measurement location and are part of the characterization of the Deaf Smith County Site, Texas for the salt repository program. These measurements will be made in support of the sound propagation study and are a result of environmental data requirements for acoustics. 6 refs., 15 figs., 5 tabs

Independent Technical Review of In-Tank Precipitation (ITP) at the Savannah River Site

International Nuclear Information System (INIS)

1993-06-01

An Independent Technical Review of In-Tank Precipitation (ITP) and Extended Sludge Processing (ESP) at the Savannah River Site (SRS) was carried out in March, 1993. The review focused on ITP/ESP equipment and chemical processes, integration of ITP/ESP within the High Level Waste (HLW) and Defense Waste Processing Facility (DWPF) systems, and management and regulatory concerns. Following the ITR executive summary, this report includes: Chapter I--summary assessment; Chapter II--recommendations; and Chapter III--technical evaluations

Hanford Site baseline risk assessment methodology

International Nuclear Information System (INIS)

1993-03-01

This methodology has been developed to prepare human health and environmental evaluations of risk as part of the Comprehensive Environmental Response, Compensation, and Liability Act remedial investigations (RIs) and the Resource Conservation and Recovery Act facility investigations (FIs) performed at the Hanford Site pursuant to the Hanford Federal Facility Agreement and Consent Order referred to as the Tri-Party Agreement. Development of the methodology has been undertaken so that Hanford Site risk assessments are consistent with current regulations and guidance, while providing direction on flexible, ambiguous, or undefined aspects of the guidance. The methodology identifies Site-specific risk assessment considerations and integrates them with approaches for evaluating human and environmental risk that can be factored into the risk assessment program supporting the Hanford Site cleanup mission. Consequently, the methodology will enhance the preparation and review of individual risk assessments at the Hanford Site

K Basin Fuel Characterization Program Technical Baseline Summary

International Nuclear Information System (INIS)

SUYAMA, R.M.

1999-01-01

This document provides a summary of the systematic process used by the SNF Project to characterize K-Basin spent fuel, and to develop and apply the appropriate conservative safety margins to the resulting parameters for technical designs and safety analyses

Safety Evaluation of the ESP Sludge Washing Baselines Runs. Revision 1

International Nuclear Information System (INIS)

Gupta, M.K.

1994-08-01

The purpose is to provide the technical basis for the evaluation of Unreviewed Safety Question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs. The Baseline runs are necessary: to ascertain the mechanical fitness of the equipment and modifications not operated since 1988 and to resolve technical questions associated with process control; i.e., sludge suspension, sludge settling, heat transfer, and temperature control. These issues need to be resolved prior to resumption of normal ESP operations. The equipment used for the Baseline runs are Tanks 42H and 51H and their associated equipment

Parameters for characterizing sites for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Lutton, R.J.; Malone, P.G.; Meade, R.B.; Patrick, D.M.

1982-05-01

Sixty-seven site parameters and parameter groups are identified as important characteristics of sites for disposal of low-level radioactive waste and require detailed evaluation. Several of the most important parameters are needed for hydrological analysis while others are needed for facility design, construction, and operation. Still others are needed for baseline and detection stages of monitoring. It is recommended that all parameters be evaluated by technically qualified personnel. Appropriate tests and documentation methods are discussed in a second report, which will follow. However, site-specific testing or elaborate field measurement will not always be necessary, i.e., where indicated to be unnecessary on a technical basis. Much of this report, Appendices A through G, is directed to explaining the importances of parameters and to establishing site-specific limitations

E-KIT: An Electronic-Knowledge Information Tool for Organizing Site Information and Improving Technical Communication with Stakeholders - 13082

International Nuclear Information System (INIS)

Kautsky, Mark; Findlay, Richard C.; Hodges, Rex A.

2013-01-01

Managing technical references for projects that have long histories is hampered by the large collection of documents, each of which might contain discrete pieces of information relevant to the site conceptual model. A database application has been designed to improve the efficiency of retrieving technical information for a project. Although many databases are currently used for accessing analytical and geo-referenced data, applications designed specifically to manage technical reference material for projects are scarce. Retrieving site data from the array of available references becomes an increasingly inefficient use of labor. The electronic-Knowledge Information Tool (e-KIT) is designed as a project-level resource to access and communicate technical information. The e-KIT is a living tool that grows as new information becomes available, and its value to the project increases as the volume of site information increases. Having all references assembled in one location with complete reference citations and links to elements of the site conceptual model offers a way to enhance communication with outside groups. The published and unpublished references are incorporated into the e-KIT, while the compendium of references serves as a complete bibliography for the project. (authors)

E-KIT: An Electronic-Knowledge Information Tool for Organizing Site Information and Improving Technical Communication with Stakeholders - 13082

Energy Technology Data Exchange (ETDEWEB)

Kautsky, Mark [U.S. Department of Energy Office of Legacy Management, 2597 Legacy Way, Grand Junction CO 81503 (United States); Findlay, Richard C.; Hodges, Rex A. [Stoller LMS Team, 2597 Legacy Way, Grand Junction CO 81503 (United States)

2013-07-01

Managing technical references for projects that have long histories is hampered by the large collection of documents, each of which might contain discrete pieces of information relevant to the site conceptual model. A database application has been designed to improve the efficiency of retrieving technical information for a project. Although many databases are currently used for accessing analytical and geo-referenced data, applications designed specifically to manage technical reference material for projects are scarce. Retrieving site data from the array of available references becomes an increasingly inefficient use of labor. The electronic-Knowledge Information Tool (e-KIT) is designed as a project-level resource to access and communicate technical information. The e-KIT is a living tool that grows as new information becomes available, and its value to the project increases as the volume of site information increases. Having all references assembled in one location with complete reference citations and links to elements of the site conceptual model offers a way to enhance communication with outside groups. The published and unpublished references are incorporated into the e-KIT, while the compendium of references serves as a complete bibliography for the project. (authors)

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 5. Baseline rock properties-granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/5, Baseline Rock Properties--Granite, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report, on the rock properties of typical granites, includes an evaluation of the various test results reported in the literature. Firstly, a literature survey was made in order to obtain a feel for the range of rock properties encountered. Then, granites representative of different geologic ages and from different parts of the United States were selected and studied in further detail. Some of the special characteristics of granite, such as anisotropy, creep and weathering were also investigated. Lastly, intact properties for a typical granite were selected and rock mass properties were derived using appropriate correction factors

Environmental Audit, Rifle, Gunnison and Grand Junction UMTRA Project Sites

International Nuclear Information System (INIS)

1991-08-01

This report documents the results of the comprehensive baseline Environmental Audit completed for the Uranium Mill Tailings Remedial Action (UMTRA) sites at Grand Junction, Rifle, and Gunnison, Colorado. Included in the Audit were the actual abandoned mill sites, associated transportation and disposal cell facilities, and representative examples of the more than 4,000 known vicinity properties. Sites investigated include: Climax Mill Site, Truck/Train Haul Route, Cotter Transfer Station, Cheney Disposal Cell, Rifle Mill Sites (Old and New Rifle), Gunnison Mill Site, Vicinity Properties, and Estes Gulch and Proposed Landfill Site No. 1 Disposal Cells. The UMTRA Audit was a comprehensive baseline audit which considered all environmental programs and the activities associated with ongoing and planned remediation at the UMTRA sites listed above. Compliance with the National Environmental Policy Act (NEPA) was not considered during this investigation. The Audit Team looked at the following technical disciplines: air, surface water/drinking water, groundwater, soil/sediment/biota, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. 6 figs., 12 tabs

Environmental Audit, Rifle, Gunnison and Grand Junction UMTRA Project Sites

Energy Technology Data Exchange (ETDEWEB)

None

1991-08-01

This report documents the results of the comprehensive baseline Environmental Audit completed for the Uranium Mill Tailings Remedial Action (UMTRA) sites at Grand Junction, Rifle, and Gunnison, Colorado. Included in the Audit were the actual abandoned mill sites, associated transportation and disposal cell facilities, and representative examples of the more than 4,000 known vicinity properties. Sites investigated include: Climax Mill Site, Truck/Train Haul Route, Cotter Transfer Station, Cheney Disposal Cell, Rifle Mill Sites (Old and New Rifle), Gunnison Mill Site, Vicinity Properties, and Estes Gulch and Proposed Landfill Site No. 1 Disposal Cells. The UMTRA Audit was a comprehensive baseline audit which considered all environmental programs and the activities associated with ongoing and planned remediation at the UMTRA sites listed above. Compliance with the National Environmental Policy Act (NEPA) was not considered during this investigation. The Audit Team looked at the following technical disciplines: air, surface water/drinking water, groundwater, soil/sediment/biota, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. 6 figs., 12 tabs.

Continued benefits of a technical assistance web site to local tobacco control coalitions during a state budget shortfall.

Science.gov (United States)

Buller, David B; Young, Walter F; Bettinghaus, Erwin P; Borland, Ron; Walther, Joseph B; Helme, Donald; Andersen, Peter A; Cutter, Gary R; Maloy, Julie A

2011-01-01

A state budget shortfall defunded 10 local tobacco coalitions during a randomized trial but defunded coalitions continued to have access to 2 technical assistance Web sites. To test the ability of Web-based technology to provide technical assistance to local tobacco control coalitions. Randomized 2-group trial with local tobacco control coalitions as the unit of randomization. Local communities (ie, counties) within the State of Colorado. Leaders and members in 34 local tobacco control coalitions funded by the state health department in Colorado. Two technical assistance Web sites: A Basic Web site with text-based information and a multimedia Enhanced Web site containing learning modules, resources, and communication features. Use of the Web sites in minutes, pages, and session and evaluations of coalition functioning on coalition development, conflict resolution, leadership satisfaction, decision-making satisfaction, shared mission, personal involvement, and organization involvement in survey of leaders and members. Coalitions that were defunded but had access to the multimedia Enhanced Web site during the Fully Funded period and after defunding continued to use it (treatment group × funding status × period, F(3,714) = 3.18, P = .0234). Coalitions with access to the Basic Web site had low Web site use throughout and use by defunded coalitions was nearly zero when funding ceased. Members in defunded Basic Web site coalitions reported that their coalitions functioned worse than defunded Enhanced Web site coalitions (coalition development: group × status, F(1,360) = 4.81, P = .029; conflict resolution: group × status, F(1,306) = 5.69, P = .018; leadership satisfaction: group × status, F(1,342) = 5.69, P = .023). The Enhanced Web site may have had a protective effect on defunded coalitions. Defunded coalitions may have increased their capacity by using the Enhanced Web site when fully funded or by continuing to use the available online resources after defunding

Development of emergency response training program for on-site commanders (2). Extraction of non-technical skills

International Nuclear Information System (INIS)

Matsui, Yuko; Hikono, Masaru; Iwasaki, Mari; Morita, Miduho

2017-01-01

This study aimed at characterizing a non-technical skill exercise for on-site managers in charge of initial response at an emergency response center by extracting and clarifying the behavior examples of non-technical skills shown in the exercise scenario. From video observations, the non-technical skill examples were identified from seven of the eight non-technical skill categories which had been defined when the training program was developed. At the same time, the limitation when extracting the cases by observations was identified. The extracted non-technical skill cases are expected to be used for characterizing exercise scenarios, as well as provide knowledge to raise the awareness of exercise participants. (author)

Radiological control FY 1995 site support program plan WBS 6.7.2.4

International Nuclear Information System (INIS)

1994-09-01

The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon

Radiological control FY 1995 site support program plan WBS 6.7.2.4

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon.

Large Hospital 50% Energy Savings: Technical Support Document

Energy Technology Data Exchange (ETDEWEB)

Bonnema, E.; Studer, D.; Parker, A.; Pless, S.; Torcellini, P.

2010-09-01

This Technical Support Document documents the technical analysis and design guidance for large hospitals to achieve whole-building energy savings of at least 50% over ANSI/ASHRAE/IESNA Standard 90.1-2004 and represents a step toward determining how to provide design guidance for aggressive energy savings targets. This report documents the modeling methods used to demonstrate that the design recommendations meet or exceed the 50% goal. EnergyPlus was used to model the predicted energy performance of the baseline and low-energy buildings to verify that 50% energy savings are achievable. Percent energy savings are based on a nominal minimally code-compliant building and whole-building, net site energy use intensity. The report defines architectural-program characteristics for typical large hospitals, thereby defining a prototype model; creates baseline energy models for each climate zone that are elaborations of the prototype models and are minimally compliant with Standard 90.1-2004; creates a list of energy design measures that can be applied to the prototype model to create low-energy models; uses industry feedback to strengthen inputs for baseline energy models and energy design measures; and simulates low-energy models for each climate zone to show that when the energy design measures are applied to the prototype model, 50% energy savings (or more) are achieved.

Long-Term Stewardship Baseline Report and Transition Guidance

Energy Technology Data Exchange (ETDEWEB)

Kristofferson, Keith

2001-11-01

Long-term stewardship consists of those actions necessary to maintain and demonstrate continued protection of human health and the environment after facility cleanup is complete. As the Department of Energy’s (DOE) lead laboratory for environmental management programs, the Idaho National Engineering and Environmental Laboratory (INEEL) administers DOE’s long-term stewardship science and technology efforts. The INEEL provides DOE with technical, and scientific expertise needed to oversee its long-term environmental management obligations complexwide. Long-term stewardship is administered and overseen by the Environmental Management Office of Science and Technology. The INEEL Long-Term Stewardship Program is currently developing the management structures and plans to complete INEEL-specific, long-term stewardship obligations. This guidance document (1) assists in ensuring that the program leads transition planning for the INEEL with respect to facility and site areas and (2) describes the classes and types of criteria and data required to initiate transition for areas and sites where the facility mission has ended and cleanup is complete. Additionally, this document summarizes current information on INEEL facilities, structures, and release sites likely to enter long-term stewardship at the completion of DOE’s cleanup mission. This document is not intended to function as a discrete checklist or local procedure to determine readiness to transition. It is an overarching document meant as guidance in implementing specific transition procedures. Several documents formed the foundation upon which this guidance was developed. Principal among these documents was the Long-Term Stewardship Draft Technical Baseline; A Report to Congress on Long-Term Stewardship, Volumes I and II; Infrastructure Long-Range Plan; Comprehensive Facility Land Use Plan; INEEL End-State Plan; and INEEL Institutional Plan.

Overview of clustered nuclear siting and its technical aspects

International Nuclear Information System (INIS)

Meier, P.M.

1976-09-01

In recent years there has been growing discussion over the ability of new siting approaches to redress the increasing problems of nuclear plant location. This debate has focused largely on three alternatives to the conventional siting of nuclear reactors; floating offshore plants; underground siting; and nuclear energy centers (NECs) consisting of up to 40 reactors at a single site, and, possibly, including fuel cycle facilities within their perimeter. Congressional interest in energy centers, especially in view of concern over the proliferation of nuclear reactors throughout the country, and with the special problems of safeguards over fuel reprocessing and the use of plutonium as a reactor fuel, resulted in a mandate to the Nuclear Regulatory Commission to make a comprehensive analysis of the energy center concept. A common finding of all of the studies of the nuclear energy center concept thus far is that there appear to be no technical considerations that would clearly preclude energy centers. With the one significant exception regarding the meteorological impacts of the concentration of heat and moisture releases to the atmosphere, engineering solutions would appear to be quite adequate to address any difficulties of environmental impact, electrical systems management, water supply or construction management, and to keep the overall physical environmental impact of an energy center not significantly different to that of an equivalent number of dispersed reactors

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator R&D in the Technical Design Phase

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Hélène Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Technical Support Document: Strategies for 50% Energy Savings in Large Office Buildings

Energy Technology Data Exchange (ETDEWEB)

Leach, M.; Lobato, C.; Hirsch, A.; Pless, S.; Torcellini, P.

2010-09-01

This Technical Support Document (TSD) documents technical analysis that informs design guidance for designing and constructing large office buildings that achieve 50% net site energy savings over baseline buildings defined by minimal compliance with respect to ANSI/ASHRAE/IESNA Standard 90.1-2004. This report also represents a step toward developing a methodology for using energy modeling in the design process to achieve aggressive energy savings targets. This report documents the modeling and analysis methods used to identify design recommendations for six climate zones that capture the range of U.S. climate variability; demonstrates how energy savings change between ASHRAE Standard 90.1-2007 and Standard 90.1-2004 to determine baseline energy use; uses a four-story 'low-rise' prototype to analyze the effect of building aspect ratio on energy use intensity; explores comparisons between baseline and low-energy building energy use for alternate energy metrics (net source energy, energy emissions, and energy cost); and examines the extent to which glass curtain construction limits achieve energy savings by using a 12-story 'high-rise' prototype.

75 FR 21353 - Intel Corporation, Fab 20 Division, Including On-Site Leased Workers From Volt Technical...

Science.gov (United States)

2010-04-23

... DEPARTMENT OF LABOR Employment and Training Administration [TA-W-73,642] Intel Corporation, Fab 20... of Intel Corporation, Fab 20 Division, including on-site leased workers of Volt Technical Resources... Precision, Inc. were employed on-site at the Hillsboro, Oregon location of Intel Corporation, Fab 20...

Baseline risk assessment of ground water contamination at the uranium mill tailings site near Canonsburg, Pennsylvania

International Nuclear Information System (INIS)

1994-09-01

This baseline risk assessment evaluates potential impacts to public health and the environment resulting from ground water contamination from past activities at the former uranium processing site in Canonsburg, Pennsylvania. The US Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Project has placed contaminated material from this site in an on-site disposal cell. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the UMTRA Ground Water Project. Currently, no domestic or drinking water well tap into contaminated ground water of the two distinct ground water units: the unconsolidated materials and the bedrock. Because there is no access, no current health or environmental risks are associated with the direct use of the contaminated ground water. However, humans and ecological organisms could be exposed to contaminated ground water if a domestic well were to be installed in the unconsolidated materials in that part of the site being considered for public use (Area C). The first step is evaluating ground water data collected from monitor wells at the site. For the Canonsburg site, this evaluation showed the contaminants in ground water exceeding background in the unconsolidated materials in Area C are ammonia, boron, calcium, manganese, molybdenum, potassium, strontium, and uranium

Baseline risk assessment of ground water contamination at the uranium mill tailings site near Canonsburg, Pennsylvania

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This baseline risk assessment evaluates potential impacts to public health and the environment resulting from ground water contamination from past activities at the former uranium processing site in Canonsburg, Pennsylvania. The US Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Project has placed contaminated material from this site in an on-site disposal cell. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the UMTRA Ground Water Project. Currently, no domestic or drinking water well tap into contaminated ground water of the two distinct ground water units: the unconsolidated materials and the bedrock. Because there is no access, no current health or environmental risks are associated with the direct use of the contaminated ground water. However, humans and ecological organisms could be exposed to contaminated ground water if a domestic well were to be installed in the unconsolidated materials in that part of the site being considered for public use (Area C). The first step is evaluating ground water data collected from monitor wells at the site. For the Canonsburg site, this evaluation showed the contaminants in ground water exceeding background in the unconsolidated materials in Area C are ammonia, boron, calcium, manganese, molybdenum, potassium, strontium, and uranium.

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator \\& in the Technical Design Phase

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Office of Geologic Repositories program baseline procedures notebook (OGR/B-1)

International Nuclear Information System (INIS)

1986-06-01

Baseline management is typically applied to aid in the internal control of a program by providing consistent programmatic direction, control, and surveillance to an evolving system development. This fundamental concept of internal program control involves the establishment of a baseline to serve as a point of departure for consistent technical program coordination and to control subsequent changes from that baseline. The existence of a program-authorized baseline ensures that all participants are working to the same ground rules. Baseline management also ensures that, once the baseline is defined, changes are assessed and approved by a process which ensures adequate consideration of overall program impact. Baseline management also includes the consideration of examptions from the baseline. The process of baseline management continues through all the phases of an evolving system development program. As the Program proceeds, there will be a progressive increase in the data contained in the baseline documentation. Baseline management has been selected as a management technique to aid in the internal control of the Office of Geologic Repositories (OGR) program. Specifically, an OGR Program Baseline, including technical and programmatic requirements, is used for program control of the four Mined Geologic Disposal System field projects, i.e., Basalt Waste Isolation Project, Nevada Nuclear Waste Storage Investigation, Salt Repository Project and Crystalline Repository Project. This OGR Program Baseline Procedures Notebook provides a description of the baseline mwanagement concept, establishes the OGR Program baseline itself, and provides procedures to be followed for controlling changes to that baseline. The notebook has a controlled distribution and will be updated as required

Tools for Closure Project and Contract Management: Development of the Rocky Flats Integrated Closure Project Baseline

International Nuclear Information System (INIS)

Gelles, C. M.; Sheppard, F. R.

2002-01-01

This paper details the development of the Rocky Flats Integrated Closure Project Baseline - an innovative project management effort undertaken to ensure proactive management of the Rocky Flats Closure Contract in support of the Department's goal for achieving the safe closure of the Rocky Flats Environmental Technology Site (RFETS) in December 2006. The accelerated closure of RFETS is one of the most prominent projects within the Department of Energy (DOE) Environmental Management program. As the first major former weapons plant to be remediated and closed, it is a first-of-kind effort requiring the resolution of multiple complex technical and institutional challenges. Most significantly, the closure of RFETS is dependent upon the shipment of all special nuclear material and wastes to other DOE sites. The Department is actively working to strengthen project management across programs, and there is increasing external interest in this progress. The development of the Rocky Flats Integrated Closure Project Baseline represents a groundbreaking and cooperative effort to formalize the management of such a complex project across multiple sites and organizations. It is original in both scope and process, however it provides a useful precedent for the other ongoing project management efforts within the Environmental Management program

Baseline avian use and behavior at the CARES wind plant site, Klickitat County, Washington

Energy Technology Data Exchange (ETDEWEB)

Erickson, W.P.; Johnson, G.D.; Strickland, M.D.; Kronner, K.; Becker, P.S.; Orloff, S.

2000-01-03

This report presents a literature review on avian-wind turbine interactions and the results of a one-year avian baseline study conducted in 1998 at the proposed Conservation and Renewable Energy System (CARES) wind development site in Klickitat County, Washington. Avian use of the site ranged from 1.11/survey in the winter to 5.69/survey in the spring. Average use by passerines in the study plots ranged from 1.15 minutes/survey in the winter to 40.98 minutes/survey in the spring. Raptors spent much less time within plots than other groups, ranging from 0.05 minutes/survey in the winter to 0.77 minutes/survey during the fall. Thirteen percent of all flying birds were within the rotor-swept height (25 to 75 m); 41.6% of all raptors were flying at this height. Raptors with the greatest potential turbine exposure are red-tailed hawks and golden eagles. Passerines with the highest turbine exposure are common ravens, American robins, and horned larks. Spatial use data for the site indicate that avian use tends to be concentrated near the rim, indicating that placing turbines away from the rim may reduce risk. Avian use data at the CARES site indicate that if a wind plant is constructed in the future, avian mortality would likely be relatively low.

Baseline avian use and behavior at the CARES wind plant site, Klickitat County, Washington

International Nuclear Information System (INIS)

Erickson, W.P.; Johnson, G.D.; Strickland, M.D.; Kronner, K.; Becker, P.S.; Orloff, S.

2000-01-01

This report presents a literature review on avian-wind turbine interactions and the results of a one-year avian baseline study conducted in 1998 at the proposed Conservation and Renewable Energy System (CARES) wind development site in Klickitat County, Washington. Avian use of the site ranged from 1.11/survey in the winter to 5.69/survey in the spring. Average use by passerines in the study plots ranged from 1.15 minutes/survey in the winter to 40.98 minutes/survey in the spring. Raptors spent much less time within plots than other groups, ranging from 0.05 minutes/survey in the winter to 0.77 minutes/survey during the fall. Thirteen percent of all flying birds were within the rotor-swept height (25 to 75 m); 41.6% of all raptors were flying at this height. Raptors with the greatest potential turbine exposure are red-tailed hawks and golden eagles. Passerines with the highest turbine exposure are common ravens, American robins, and horned larks. Spatial use data for the site indicate that avian use tends to be concentrated near the rim, indicating that placing turbines away from the rim may reduce risk. Avian use data at the CARES site indicate that if a wind plant is constructed in the future, avian mortality would likely be relatively low

Baseline risk assessment of ground water contamination at the Monument Valley Uranium Mill Tailings Site, Cane Valley, Arizona. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This baseline risk assessment evaluates potential impact to public health or the environment from ground water contamination at the former uranium mill processing site in Cane Valley near Monument Valley, Arizona. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project has relocated and stabilized this site`s tailings and other contaminated material in a disposal cell at Mexican Hat, Utah. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project that evaluates potential health and environmental risks. It will help determine the approach required to address contaminated ground water at the site.

The optimized baseline project: Reinventing environmental restoration at Hanford

International Nuclear Information System (INIS)

Goodenough, J.D.; Janaskie, M.T.; Kleinen, P.J.

1994-01-01

The U.S. Department of Energy Richland Operations Office (DOE-RL) is using a strategic planning effort (termed the Optimized Baseline Project) to develop a new approach to the Hanford Environmental Restoration program. This effort seeks to achieve a quantum leap improvement in performance through results oriented prioritization of activities. This effort was conducted in parallel with the renegotiation of the Tri-Party Agreement and provided DOE with an opportunity to propose innovative initiatives to promote cost effectiveness, accelerate progress in the Hanford Environmental Restoration Program and involve stakeholders in the decision-making process. The Optimized Baseline project is an innovative approach to program planning and decision-making in several respects. First, the process is a top down, value driven effort that responds to values held by DOE, the regulatory community and the public. Second, planning is conducted in a way that reinforces the technical management process at Richland, involves the regulatory community in substantive decisions, and includes the public. Third, the Optimized Baseline Project is being conducted as part of a sitewide Hanford initiative to reinvent Government. The planning process used for the Optimized Baseline Project has many potential applications at other sites and in other programs where there is a need to build consensus among diverse, independent groups of stakeholders and decisionmakers. The project has successfully developed and demonstrated an innovative approach to program planning that accelerates the pace of cleanup, involves the regulators as partners with DOE in priority setting, and builds public understanding and support for the program through meaningful opportunities for involvement

Estimating the cold war mortgage: The 1995 baseline environmental management report. Volume II: Site summaries

International Nuclear Information System (INIS)

1995-03-01

This volume, Volume II presents the site data that was used to generate the Department of Energy's (DOE) initial Baseline Environmental Management Report (BEMR). The raw data was obtained by DOE field personnel from existing information sources and anticipated environmental management strategies for their sites and was tempered by general assumptions and guidance developed by DOE Headquarters personnel. This data was then integrated by DOE Headquarters personnel and modified to ensure that overall constraints such as funding and waste management capacity were addressed. The site summaries are presented by State and broken out by discrete activities and projects. The Volume I Glossary has been repeated to facilitate the reader's review of Volume II. The information presented in the site summaries represents the best data and assumptions available as of February 1, 1995. Assumptions that have not been mandated by formal agreement with appropriate regulators and other stakeholders do not constitute decisions by the Department nor do they supersede existing agreements. In addition, actions requiring decisions from external sources regarding unknowns such as future land use and funding/scheduling alternatives, as well as internal actions such as the Department's Strategic Realignment initiative, will alter the basis and general assumptions used to generate the results for this report. Consequently, the numbers presented in the site summaries do not represent outyear budget requests by the field installations

Carbon tetrachloride ERA soil-gas baseline monitoring

International Nuclear Information System (INIS)

Fancher, J.D.

1994-01-01

From December 1991 through December 1993, Westinghouse Hanford Company performed routine baseline monitoring of selected wells ad soil-gas points twice weekly in the 200 West Area of the Hanford Site. This work supported the carbon Tetrachloride Expedited Response Action (ERA) and provided a solid baseline of volatile organic compound (VOC) concentrations in wells and in the subsurface at the ERA site. As site remediation continues, comparisons to this baseline can be one means of measuring the success of carbon tetrachloride vapor extraction. This report contains observations of the patterns and trends associated with data obtained during soil-gas monitoring at the 200 West Area: Monitoring performed since late 1991 includes monitoring soil-gas probes ad wellheads for volatile organic compounds (VOCs). This report reflects monitoring data collected from December 1991 through December 1993

National Ignition Facility site requirements

International Nuclear Information System (INIS)

1996-07-01

The Site Requirements (SR) provide bases for identification of candidate host sites for the National Ignition Facility (NIF) and for the generation of data regarding potential actual locations for the facilities. The SR supplements the NIF Functional Requirements (FR) with information needed for preparation of responses to queries for input to HQ DOE site evaluation. The queries are to include both documents and explicit requirements for the potential host site responses. The Sr includes information extracted from the NIF FR (for convenience), data based on design approaches, and needs for physical and organization infrastructure for a fully operational NIF. The FR and SR describe requirements that may require new construction or may be met by use or modification of existing facilities. The SR do not establish requirements for NIF design or construction project planning. The SR document does not constitute an element of the NIF technical baseline

Strategy utilized for assessing baseline risks to human health from K-65 and metal oxide residues stored at the Fernald Site

International Nuclear Information System (INIS)

Harmon, J.E.; Janke, R.C.

1995-01-01

The U.S. Department of Energy (DOE) is responsible for cleanup activities at the Fernald Environmental Management Project (FEMP) site in southwestern Ohio. The 425-hectare site consists of a former 55-hectare Production Area, an adjacent Waste Storage Area and various support facilities. From 1952 until 1989, the FEMP processed uranium into metallic open-quotes feedclose quotes materials for other DOE facilities in the nation's defense program. In accordance with the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), the FEMP site is currently listed on the National Priorities List (NPL). To facilitate an expeditious cleanup effort, environmental issues associated with site cleanup are being managed under five operable units. This paper summarizes the risk assessment strategy employed to determine baseline human health risks associated with K-65 and metal oxide residues currently stored in Operable Unit 4. The K-65 and metal oxide residues were generated during the 1950s as a result of the extraction of uranium from uranium-bearing ores and concentrates. These residues are currently stored within Operable Unit 4 in concrete silos. Silos I and 2 contain approximately 6,120 cubic meters [m 3 ] (8,005 cubic yards [yd 3 ]) of K-65 residues, while silos 3 contains approximately 3890 m 3 (5,080 yd 3 ) of cold metal oxides. These concrete silos are beyond their design life and require remedial action. The risk assessment conducted for Operable Unit 4 constitutes the first detailed human health risk assessment to be approved by the Environmental Protection Agency (EPA) for the CERCLA clean-up effort at the FEMP Site. This paper discusses the FEMP's use of a Risk Information Quality Objective process in concert with the traditional risk assessment approach to determine baseline risk to human health and the environment posed by Operable Unit 4. A summary of the baseline risks to human health is also presented

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A., Westinghouse Hanford

1996-07-17

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A.

1996-09-20

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

On-site gamma dose rates at the Andreeva Bay shore technical base, northwest Russia

NARCIS (Netherlands)

Reistad, O.; Dowdall, M.; Standring, W. J. F.; Selnaes, O. G.; Hustveit, S.; Steinhusen, F.; Sorlie, A.

The spent nuclear fuel (SNF) and radioactive waste (RAW) storage facility at Andreeva Bay shore technical base (STB) is one of the largest and most hazardous nuclear legacy sites in northwest Russia. Originally commissioned in the 1960s the facility now stores large amounts of SNF and RAW associated

How the NDA Provides Transparency and Visibility of the Technical Deliverability of the R and D Programme - 13303

International Nuclear Information System (INIS)

Seed, Ian; James, Paula; Brownridge, Melanie; McMinn, Mervin

2013-01-01

The Nuclear Decommissioning Authority (NDA) was created under the UK Energy Act 2004 to ensure the UK historic civil public sector nuclear legacy sites are decommissioned safely, securely, cost effectively and in ways that protect the environment. The delivery will involve carrying out many unique projects within a high hazard environment requiring the very highest standards in safety, security and environmental management. Unique problems require unique solutions and there is a substantial amount of research and development required for each project. The NDA's R and D strategic objective is to ensure that delivery of the NDA's mission is technically underpinned by sufficient and appropriate research and development. This drives a requirement to provide transparency and visibility of the technical deliverability of the programme through the technical baseline and accompanying research and development requirements. The NDA need to have confidence in the technical deliverability of the Site License Companies (SLCs) plans, provide overall visibility of R and D across the NDA Estate and ensure that appropriate R and D is being carried out in a timely manner. They need to identify where coordinated R and D programmes may be advantageous as a result of common needs, risks and opportunities and ensure key R and D needs across NDA are identified, prioritised and work programmes are costed and scheduled in the Lifetime Plans for individual sites and SLCs. Evidence of the Site License Company's approach and their corresponding technical underpinning programmes is achieved through submission of a number of outputs collectively known as TBuRDs (Technical Baseline and Underpinning Research and Development Requirements). This paper is a summary of the information generated by an independent review of those TBuRDs. It highlights some of the key messages, synergies and common R and D activities across the estate. It demonstrates the value of a consistent approach to collecting R

Hanford Site Composite Analysis Technical Approach Description: Groundwater Pathway Dose Calculation.

Energy Technology Data Exchange (ETDEWEB)

Morgans, D. L. [CH2M Hill Plateau Remediation Company, Richland, WA (United States); Lindberg, S. L. [Intera Inc., Austin, TX (United States)

2017-09-20

The purpose of this technical approach document (TAD) is to document the assumptions, equations, and methods used to perform the groundwater pathway radiological dose calculations for the revised Hanford Site Composite Analysis (CA). DOE M 435.1-1, states, “The composite analysis results shall be used for planning, radiation protection activities, and future use commitments to minimize the likelihood that current low-level waste disposal activities will result in the need for future corrective or remedial actions to adequately protect the public and the environment.”

Waste site grouping for 200 Areas soil investigations

International Nuclear Information System (INIS)

1997-01-01

The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models

Baseline risk assessment of ground water contamination at the Monument Valley Uranium Mill Tailings Site, Cane Valley, Arizona. Revision 1

International Nuclear Information System (INIS)

1994-08-01

This baseline risk assessment evaluates potential impact to public health or the environment from ground water contamination at the former uranium mill processing site in Cane Valley near Monument Valley, Arizona. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project has relocated and stabilized this site's tailings and other contaminated material in a disposal cell at Mexican Hat, Utah. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project that evaluates potential health and environmental risks. It will help determine the approach required to address contaminated ground water at the site

Baseline geochemistry of soil and bedrock Tshirege Member of the Bandelier Tuff at MDA-P

International Nuclear Information System (INIS)

Warren, R.G.; McDonald, E.V.; Ryti, R.T.

1997-08-01

This report provides baseline geochemistry for soils (including fill), and for bedrock within three specific areas that are planned for use in the remediation of Material Disposal Area P (MDA-P) at Technical Area 16 (TA-16). The baseline chemistry includes leachable element concentrations for both soils and bedrock and total element concentrations for all soil samples and for two selected bedrock samples. MDA-P operated from the early 1950s to 1984 as a landfill for rubble and debris generated by the burning of high explosives (HE) at the TA-16 Burning Ground, HE-contaminated equipment and material, barium nitrate sand, building materials, and trash. The aim of this report is to establish causes for recognizable chemical differences between the background and baseline data sets. In many cases, the authors conclude that recognizable differences represent natural enrichments. In other cases, differences are best attributed to analytical problems. But most importantly, the comparison of background and baseline geochemistry demonstrates significant contamination for several elements not only at the two remedial sites near the TA-16 Burning Ground, but also within the entire region of the background study. This contamination is highly localized very near to the surface in soil and fill, and probably also in bedrock; consequently, upper tolerance limits (UTLs) calculated as upper 95% confidence limits of the 95th percentile are of little value and thus are not provided. This report instead provides basic statistical summaries and graphical comparisons for background and baseline samples to guide strategies for remediation of the three sites to be used in the restoration of MDA-P

48 CFR 34.202 - Integrated Baseline Reviews.

Science.gov (United States)

2010-10-01

... or contractor, and the Government, of the— (1) Ability of the project's technical plan to achieve the... successfully achieve the project schedule objectives; (3) Ability of the Performance Measurement Baseline (PMB... SPECIAL CATEGORIES OF CONTRACTING MAJOR SYSTEM ACQUISITION Earned Value Management System 34.202...

Baseline risk assessment for groundwater contamination at the uranium mill tailings site, Gunnison, Colorado

International Nuclear Information System (INIS)

1990-11-01

The Gunnison Baseline Risk Assessment for Groundwater Contamination at the Uranium Mill Tailings Site was performed to determine if long-term use of groundwater from domestic wells near the site has a potential for adverse health effects. The risk assessment was based on the results of sampling domestic wells during 1989--1990. A risk assessment evaluates health risks by comparing the amount of a contaminant taken in by a person with the amount of the contaminant that may be toxic. The Gunnison Risk Assessment used high intake values to estimate the maximum levels a person might be exposed to. The results of the risk assessment are divided into cancer (carcinogenic) risks and non-carcinogenic risks. Five key contaminants were evaluated for adverse health risks: uranium, manganese, lead antimony, and cadmium. Due to the potential health risks and the unavoidable uncertainties associated with limited groundwater and toxicity data, it is prudent public health policy to provide a permanent alternate water supply. Additionally, providing a permanent alternate water supply is cost-effective compared to long-term routine monitoring

Radon baseline monitoring around a potential shale gas development site in Yorkshire, England

International Nuclear Information System (INIS)

Daraktchieva, Z.; Wasikiewicz, J. M.; Howarth, C. B.; Bradley, E.J.

2017-01-01

The Vale of Pickering in Yorkshire, England has been identified as a potential area for shale gas extraction. Public Health England joined a collaboration led by the British Geological Survey for environmental baseline monitoring near the potential shale gas extraction site following a grant award from UK Government Department for Business, Energy and Industrial Strategy. The analysis of results for the first 6 months of indoor monitoring indicated that the results followed a log-normal distribution. The numbers of homes found to be at or above the Action Level followed the numbers predicted by the radon potential maps. The results from the measurements of outdoor air in this study indicated that the radon concentrations are slightly higher than previously measured but close to the detection limit of the technique. (authors)

Baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota

Energy Technology Data Exchange (ETDEWEB)

1994-11-01

This baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota, evaluates the potential impacts to public health or the environment from contaminated ground water at this site. This contamination is a result of the uraniferous lignite ashing process, when coal containing uranium was burned to produce uranium. Potential risk is quantified only for constituents introduced by the processing activities and not for the constituents naturally occurring in background ground water in the site vicinity. Background ground water, separate from any site-related contamination, imposes a percentage of the overall risk from ground water ingestion in the Bowman site vicinity. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to address soil and ground water contamination at the site. The UMTRA Surface Project involves the determination of the extent of soil contamination and design of an engineered disposal cell for long-term storage of contaminated materials. The UMTRA Ground Water Project evaluates ground water contamination. Based on results from future site monitoring activities as defined in the site observational work plan and results from this risk assessment, the DOE will propose an approach for managing contaminated ground water at the Bowman site.

Baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota

International Nuclear Information System (INIS)

1994-11-01

This baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota, evaluates the potential impacts to public health or the environment from contaminated ground water at this site. This contamination is a result of the uraniferous lignite ashing process, when coal containing uranium was burned to produce uranium. Potential risk is quantified only for constituents introduced by the processing activities and not for the constituents naturally occurring in background ground water in the site vicinity. Background ground water, separate from any site-related contamination, imposes a percentage of the overall risk from ground water ingestion in the Bowman site vicinity. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to address soil and ground water contamination at the site. The UMTRA Surface Project involves the determination of the extent of soil contamination and design of an engineered disposal cell for long-term storage of contaminated materials. The UMTRA Ground Water Project evaluates ground water contamination. Based on results from future site monitoring activities as defined in the site observational work plan and results from this risk assessment, the DOE will propose an approach for managing contaminated ground water at the Bowman site

Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-09-01

This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

Baseline risk assessment for exposure to contaminants at the St. Louis Site, St. Louis, Missouri

International Nuclear Information System (INIS)

1993-11-01

The St. Louis Site comprises three noncontiguous areas in and near St. Louis, Missouri: the St. Louis Downtown Site (SLDS), the St. Louis Airport Storage Site (SLAPS), and the Latty Avenue Properties. The main site of the Latty Avenue Properties includes the Hazelwood Interim Storage Site (HISS) and the Futura Coatings property, which are located at 9200 Latty Avenue. Contamination at the St. Louis Site is the result of uranium processing and disposal activities that took place from the 1940s through the 1970s. Uranium processing took place at the SLDS from 1942 through 1957. From the 1940s through the 1960s, SLAPS was used as a storage area for residues from the manufacturing operations at SLDS. The materials stored at SLAPS were bought by Continental Mining and Milling Company of Chicago, Illinois, in 1966, and moved to the HISS/Futura Coatings property at 9200 Latty Avenue. Vicinity properties became contaminated as a result of transport and movement of the contaminated material among SLDS, SLAPS, and the 9200 Latty Avenue property. This contamination led to the SLAPS, HISS, and Futura Coatings properties being placed on the National Priorities List (NPL) of the US Environmental Protection Agency (EPA). The US Department of Energy (DOE) is responsible for cleanup activities at the St. Louis Site under its Formerly Utilized Sites Remedial Action Program (FUSRAP). The primary goal of FUSRAP is the elimination of potential hazards to human health and the environment at former Manhattan Engineer District/Atomic Energy Commission (MED/AEC) sites so that, to the extent possible, these properties can be released for use without restrictions. To determine and establish cleanup goals for the St. Louis Site, DOE is currently preparing a remedial investigation/feasibility study-environmental impact statement (RI/FS-EIS). This baseline risk assessment (BRA) is a component of the process; it addresses potential risk to human health and the environment associated wi

Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

International Nuclear Information System (INIS)

1978-02-01

The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

Corrective action baseline report for underground storage tank 2331-U Building 9201-1

International Nuclear Information System (INIS)

1994-01-01

The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

Land Use Baseline Report Savannah River Site

International Nuclear Information System (INIS)

Noah, J.C.

1995-01-01

This document is to serve as a resource for Savannah River Site managers, planners, and SRS stakeholders by providing a general description of the site and land-use factors important to future use decisions and plans. The intent of this document is to be comprehensive in its review of SRS and the surrounding area

Land Use Baseline Report Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Noah, J.C.

1995-06-29

This document is to serve as a resource for Savannah River Site managers, planners, and SRS stakeholders by providing a general description of the site and land-use factors important to future use decisions and plans. The intent of this document is to be comprehensive in its review of SRS and the surrounding area.

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Shiprock, New Mexico

International Nuclear Information System (INIS)

1994-04-01

This baseline risk assessment at the former uranium mill tailings site near Shiprock, New Mexico, evaluates the potential impact to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an on-site disposal cell in 1986 through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. There are no domestic or drinking water wells in the contaminated ground water of the two distinct ground water units: the contaminated ground water in the San Juan River floodplain alluvium below the site and the contaminated ground water in the terrace alluvium area where the disposal cell is located. Because no one is drinking the affected ground water, there are currently no health or environmental risks directly associated with the contaminated ground water. However, there is a potential for humans, domestic animals, and wildlife to the exposed to surface expressions of ground water in the seeps and pools in the area of the San Juan River floodplain below the site. For these reasons, this risk assessment evaluates potential exposure to contaminated surface water and seeps as well as potential future use of contaminated ground water

THE US LONG BASELINE NEUTRINO EXPERIMENT STUDY.

Energy Technology Data Exchange (ETDEWEB)

BISHAI,M.

2007-08-06

The US Long Baseline Neutrino Experiment Study was commissioned jointly by Brookhaven National Laboratory (BNL)and Fermi National Accelerator Laboratory (FNAL) to investigate the potential for future U.S. based long baseline neutrino oscillation experiments using MW class conventional neutrino beams that can be produced at FNAL. The experimental baselines are based on two possible detector locations: (1) off-axis to the existing FNAL NuMI beamline at baselines of 700 to 810 km and (2) NSF's proposed future Deep Underground Science and Engineering Laboratory (DUSEL) at baselines greater than 1000km. Two detector technologies are considered: a megaton class Water Cherenkov detector deployed deep underground at a DUSEL site, or a 100kT Liquid Argon Time-Projection Chamber (TPC) deployed on the surface at any of the proposed sites. The physics sensitivities of the proposed experiments are summarized. We find that conventional horn focused wide-band neutrino beam options from FNAL aimed at a massive detector with a baseline of > 1000km have the best sensitivity to CP violation and the neutrino mass hierarchy for values of the mixing angle {theta}{sub 13} down to 2{sup o}.

Facilitating Site Specific and Citizens Advisory Boards: Running Effective Meetings that Involve Complex Technical Issues

International Nuclear Information System (INIS)

Freeman, J.

2009-01-01

Environmental cleanup issues at federal sites are more often than not on the agendas of meetings of the Site Specific Advisory Boards (SSABs), also called Citizens Advisory Boards (CABs), that exist at most U.S. Department of Energy (DOE) sites with an Environmental Management (EM) mission. In 1994, when Congress established these committees comprised of local citizens, it enabled community stakeholders to become more directly involved in DOE EM cleanup decisions. This involvement is to help the agency make cost-effective and environmentally sound decisions which lead to faster, safer cleanups. Eight local Boards that fall under the Federal Advisory Committee Act-chartered EM SSAB charter are found in Hanford, Washington; Idaho; Northern New Mexico; Nevada; Oak Ridge, Tennessee; Paducah, Kentucky; Portsmouth, Ohio; and at the Savannah River Site in South Carolina. These boards provide advice and recommendations about EM site-specific issues such as cleanup standards (how clean is clean?), environmental restoration, waste management, the stabilization and disposal of non-stockpile nuclear materials, future land use and long-term stewardship, risk assessment and management, and cleanup science and technology activities. These issues are, by their very nature, loaded with complicated technical terms and strategies, scientific data and interpretations, and long histories of studies and reports. The members of SSABs and CABs rotate on and off the Boards according to defined terms of office, thereby routinely opening the Boards' ranks to new members, many of whom are new to the issues. In addition, members of the public who have access to public comment periods at each Board meeting run up against the same daunting menu of obscure acronyms, scientific terms and notations, and an historical trail which is not always evident except to those involved with the issues over many years. How does a facilitator effectively guide such a group of citizens, each of whom arrives to

Demonstration of Eastman Christensen horizontal drilling system -- Integrated Demonstration Site, Savannah River Site

International Nuclear Information System (INIS)

1992-12-01

An innovative horizontal drilling system was used to install two horizontal wells as part of an integrated demonstration project at the Savannah River Site (SRS), Aiken, South Carolina. The SRS is located in south-central South Carolina in the upper Coastal Plain physiographic province. The demonstration site is located near the A/M Area, and is currently known as the Integated Demonstration Site. The Department of Energy's Office of Technology Development initiated an integrated demonstration of innovative technologies for cleanup of volatile organic compounds (VOCS) in soils and groundwater at the SRS in 1989. The overall goal of the program is to demonstrate, at a single location, multiple technologies in the fields of drilling, characterization, monitoring, and remediation. Innovative technologies are compared to one another and to baseline technologies in terms of technical performance and cost effectiveness. Transfer of successfully demonstrated technologies and systems to DOE environmental restoration organizations, to other government agencies, and to industry is a critical part of the program

The 1993 baseline biological studies and proposed monitoring plan for the Device Assembly Facility at the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

1995-02-01

This report contains baseline data and recommendations for future monitoring of plants and animals near the new Device Assembly Facility (DAF) on the Nevada Test Site (NTS). The facility is a large structure designed for safely assembling nuclear weapons. Baseline data was collected in 1993, prior to the scheduled beginning of DAF operations in early 1995. Studies were not performed prior to construction and part of the task of monitoring operational effects will be to distinguish those effects from the extensive disturbance effects resulting from construction. Baseline information on species abundances and distributions was collected on ephemeral and perennial plants, mammals, reptiles, and birds in the desert ecosystems within three kilometers (km) of the DAF. Particular attention was paid to effects of selected disturbances, such as the paved road, sewage pond, and the flood-control dike, associated with the facility. Radiological monitoring of areas surrounding the DAF is not included in this report.

Strategy utilized for assessing baseline risks to human health from K-65 and metal oxide residues stored at the Fernald Site

Energy Technology Data Exchange (ETDEWEB)

Harmon, J.E. [FERMCO, Cincinnati, OH (United States). Fernald Environmental Management Project; Janke, R.C.

1995-04-01

The U.S. Department of Energy (DOE) is responsible for cleanup activities at the Fernald Environmental Management Project (FEMP) site in southwestern Ohio. The 425-hectare site consists of a former 55-hectare Production Area, an adjacent Waste Storage Area and various support facilities. From 1952 until 1989, the FEMP processed uranium into metallic {open_quotes}feed{close_quotes} materials for other DOE facilities in the nation`s defense program. In accordance with the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), the FEMP site is currently listed on the National Priorities List (NPL). To facilitate an expeditious cleanup effort, environmental issues associated with site cleanup are being managed under five operable units. This paper summarizes the risk assessment strategy employed to determine baseline human health risks associated with K-65 and metal oxide residues currently stored in Operable Unit 4. The K-65 and metal oxide residues were generated during the 1950s as a result of the extraction of uranium from uranium-bearing ores and concentrates. These residues are currently stored within Operable Unit 4 in concrete silos. Silos I and 2 contain approximately 6,120 cubic meters [m{sup 3}] (8,005 cubic yards [yd{sup 3}]) of K-65 residues, while silos 3 contains approximately 3890 m{sup 3} (5,080 yd{sup 3}) of cold metal oxides. These concrete silos are beyond their design life and require remedial action. The risk assessment conducted for Operable Unit 4 constitutes the first detailed human health risk assessment to be approved by the Environmental Protection Agency (EPA) for the CERCLA clean-up effort at the FEMP Site. This paper discusses the FEMP`s use of a Risk Information Quality Objective process in concert with the traditional risk assessment approach to determine baseline risk to human health and the environment posed by Operable Unit 4. A summary of the baseline risks to human health is also presented.

The technical-economic problems concerning the search for sites for nuclear electricity generation facilities

International Nuclear Information System (INIS)

Zimmer, H.J.

1976-01-01

An outline of technical-physical fundamentals, of the design and the mode of operation of LWR reactors is followed by a brief description of the licensing procedure. It is pointed out that safety cannot be a criterion for a site because nuclear power plants have to be safe on every site. The problem of nuclear power plants in the vicinity of towns or densely populated areas is dealt with briefly, too. A method is proposed which allows to find a possible site while investing little time on search and evaluation and which stores this site in a site provision plan. The choice of possible sites is made on three levels which are independent of each other. Possible nuclear power plant sites, on the first level, are considered on the basis of the dominating influence of waste heat discharge and network integration. On the second level, macro-sites are determined by examining the realizability of these possible sites by looking at negative criteria, and, on the third level, the 'fine points' planning stage, a pool of potential micro-sites is determined by applying the 'measure of value' analysis. This is followed by citing an analytical method with which the order of priority amongst 8 possible sites in the USA was determined. (orig./HP) [de

BASELINE DEVELOPMENT USING THE CRITICAL DECISION AND DOE ORDER 413.3 FRAMEWORKS: A CASE STUDY

International Nuclear Information System (INIS)

Darnell, M.L.; Duffy, M.A.; Gantos, N.J.; Zadeh, B.

2003-01-01

From 1943 through 1986, Battelle Memorial Institute performed nuclear research and development on behalf of various Federal government agencies, primarily for the U.S. Department of Energy (DOE) and its predecessor agencies. This work was performed in Battelle's privately owned facilities in Columbus, Ohio, and a research park located at an 11-acre facility 16 miles west of Columbus, in a rural area near the village of West Jefferson, Ohio. Under the Battelle Columbus Laboratories Decommissioning Project (BCLDP), Battelle is now engaged in cleaning up the West Jefferson site on a cost-sharing basis with the DOE. The BCLDP mission is to decontaminate Battelle facilities in a safe, environmentally sound, and cost-effective manner, returning the facilities to a condition suitable for use without radiological restriction. The Columbus Environmental Management Project (CEMP), reporting to the DOE Ohio Field Office, is the DOE organization that is responsible for overseeing the BCLDP. CEMP requested preparation of a technical baseline, suitable for independent validation, establishing the scope, cost, and schedule for completing the project. Concurrent with this request, the DOE Office of Environmental Management issued DOE Order 413.3, Program and Project Management for the Acquisition of Capital Assets, for review and, shortly thereafter, published the first drafts of companion documents titled Program and Project Management Manual and Project Management Practices. These two documents suggest or require the use of a variety of techniques and tools for planning and executing DOE cleanup programs. Accordingly, Battelle successfully developed a project baseline for obtaining approval of Critical Decision 2/3 (CD-2/3) in compliance with the requirements of DOE Order 413.3 and the technical approaches described in the companion documents. This paper addresses three fundamental questions:(1) What were the planned baseline development methodology and its implementation

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

Technical procedures for implementation of aesthetics site studies, Deaf Smith County site, Texas: Environmental Field Program

International Nuclear Information System (INIS)

1987-06-01

This chapter introduces the purpose and scope of the visually affected areas determination, as well as definitions, interfaces, and concurrent data needs. This procedure provides a method for determining the extent of visibility of the project. This area is identified as the visually affected area, and becomes the area within which all visual analysis is conducted. The visually affected area analysis of the Deaf Smith County site will involve identifying and mapping the visibility of all major proposed project features. Baseline analysis will be conducted within the overall visually affected area; impact assessment will be conducted within the visually affected area of each major project feature. This procedure presents the guidelines for determining the visually affected area will be in computer data base construction; viewshed modeling, and site visit and verification of results. Computer data base construction will involve digitizing topographic and project facility data from available data source. The extent of the visible area from each major project feature will then be plotted. Finally, these computer-generated visibility plots will be verified in the field

Baseline risk assessment of ground water contamination at the uranium mill tailings site near Falls City, Texas: Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This baseline risk assessment of ground water contamination of the uranium mill tailings site near Falls City, Texas, evaluates potential impact to public health and the environment resulting from ground water contamination at the former Susquehanna Western, Inc. (SWI), uranium mill processing site. This document fulfills the following objectives: determine if the site presents immediate or potential future health risks, determine the need for interim institutional controls, serve as a key input to project planning and prioritization, and recommend future data collection efforts to more fully characterize risk. The Uranium Mill Tailings Remedial Action (UMTRA) Project has begun its evaluation of ground water contamination at the Falls City site. This risk assessment is one of the first documents specific to this site for the Ground Water Project. The first step is to evaluate ground water data collected from monitor wells at or near the site. Evaluation of these data show the main contaminants in the Dilworth ground water are cadmium, cobalt, fluoride, iron, nickel, sulfate, and uranium. The data also show high levels of arsenic and manganese occur naturally in some areas.

Baseline risk assessment of ground water contamination at the uranium mill tailings site near Falls City, Texas: Revision 1

International Nuclear Information System (INIS)

1994-09-01

This baseline risk assessment of ground water contamination of the uranium mill tailings site near Falls City, Texas, evaluates potential impact to public health and the environment resulting from ground water contamination at the former Susquehanna Western, Inc. (SWI), uranium mill processing site. This document fulfills the following objectives: determine if the site presents immediate or potential future health risks, determine the need for interim institutional controls, serve as a key input to project planning and prioritization, and recommend future data collection efforts to more fully characterize risk. The Uranium Mill Tailings Remedial Action (UMTRA) Project has begun its evaluation of ground water contamination at the Falls City site. This risk assessment is one of the first documents specific to this site for the Ground Water Project. The first step is to evaluate ground water data collected from monitor wells at or near the site. Evaluation of these data show the main contaminants in the Dilworth ground water are cadmium, cobalt, fluoride, iron, nickel, sulfate, and uranium. The data also show high levels of arsenic and manganese occur naturally in some areas

Site characterization progress report: Yucca Mountain, Nevada. October 1, 1996--March 31, 1997

International Nuclear Information System (INIS)

1997-10-01

The report is the sixteenth in a series issued approximately every six months to report progress and results of site characterization activities being conducted to evaluate Yucca Mountain as a possible geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. This report highlights work started, in progress, and completed during the reporting period. In addition, this report documents and discusses changes to the Office of Civilian Radioactive Waste Management (OCRWM) Site Characterization Program (Program) resulting from the ongoing collection and evaluation of site information, systems analyses, development of repository and waste package designs, and results of performance assessment activities. Details on the activities summarized can be found in the numerous technical reports cited throughout the progress report. Yucca Mountain Site Characterization Project (Project) activities this period focused on implementing the near-term objectives of the revised Program Plan issued last period. Near-term objectives of the revised Program Plan include updating the US Department of Energy's (DOE) repository siting guidelines to be consistent with a more focused performance-driven program; supporting an assessment in 1998 of the viability of continuing with actions leading to the licensing of a repository; and if the site is suitable, submittal of a Secretarial site recommendation to the President in 2001 and license application the US Nuclear Regulatory Commission (NRC) in 2002. During this reporting period, the Project developed and baselined its long-range plan in December 1996. That revision reflected the detailed fiscal year (FY) 1997 work scope and funding plan previously baselined at the end of FY 1996. Site characterization activities have been focused to answer the major open technical issues and to support the viability assessment

Technical, normative and social aspects of the site selection process for radioactive waste repositories

International Nuclear Information System (INIS)

Branco, Otavio E.A.; Rodrigues, Paulo C.H.; Carvalho Filho, Carlos A.; Cota, Stela D.S.; Ferreira, Vinicius V.M.; Peres, Sueli S.; Hiromoto, Goro

2009-01-01

In force since 2001, the Federal Law 10.308 states, in article 37, that the Comissao Nacional de Energia Nuclear - CNEN should start studies for the implementation of a final radioactive waste repository, 'in the shortest timeframe technically feasible'. Nevertheless, not only technical aspects have to be taken into account to accomplish with this schedule, but, also factors of political, economic and social nature. In this paper, the importance and impact of public acceptance aspects are discussed, as well as the methodology of site selection for radioactive wastes repositories, and proposals to accommodate the emanated criteria from the existing legislation. Additionally, practical results from the international experience in the implementation of such deposits are presented. (author)

Technical Services on the Net: Where Are We Now? A Comparative Study of Sixty Web Sites of Academic Libraries

Science.gov (United States)

Wang, Jianrong; Gao, Vera

2004-01-01

This study examines sixty academic libraries' Web sites and finds that 80 percent of them do not have a technical services' homepage. Data reveal that institution's status might be a factor in whether a library has such a page. Further content analysis suggests there is an appropriate and useful public service role that technical services…

Hanford Site baseline risk assessment methodology. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This methodology has been developed to prepare human health and environmental evaluations of risk as part of the Comprehensive Environmental Response, Compensation, and Liability Act remedial investigations (RIs) and the Resource Conservation and Recovery Act facility investigations (FIs) performed at the Hanford Site pursuant to the Hanford Federal Facility Agreement and Consent Order referred to as the Tri-Party Agreement. Development of the methodology has been undertaken so that Hanford Site risk assessments are consistent with current regulations and guidance, while providing direction on flexible, ambiguous, or undefined aspects of the guidance. The methodology identifies Site-specific risk assessment considerations and integrates them with approaches for evaluating human and environmental risk that can be factored into the risk assessment program supporting the Hanford Site cleanup mission. Consequently, the methodology will enhance the preparation and review of individual risk assessments at the Hanford Site.

Surface Signature Characterization at SPE through Ground-Proximal Methods: Methodology Change and Technical Justification

Energy Technology Data Exchange (ETDEWEB)

Schultz-Fellenz, Emily S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-09-09

A portion of LANL’s FY15 SPE objectives includes initial ground-based or ground-proximal investigations at the SPE Phase 2 site. The area of interest is the U2ez location in Yucca Flat. This collection serves as a baseline for discrimination of surface features and acquisition of topographic signatures prior to any development or pre-shot activities associated with SPE Phase 2. Our team originally intended to perform our field investigations using previously vetted ground-based (GB) LIDAR methodologies. However, the extended proposed time frame of the GB LIDAR data collection, and associated data processing time and delivery date, were unacceptable. After technical consultation and careful literature research, LANL identified an alternative methodology to achieve our technical objectives and fully support critical model parameterization. Very-low-altitude unmanned aerial systems (UAS) photogrammetry appeared to satisfy our objectives in lieu of GB LIDAR. The SPE Phase 2 baseline collection was used as a test of this UAS photogrammetric methodology.

Fire Protection Program fiscal year 1996, site support program plan Hanford Fire Department. Revision 2

International Nuclear Information System (INIS)

Good, D.E.

1995-09-01

The mission of the Hanford Fire Department (HFD) is to support the safe and timely cleanup of the Hanford site by providing fire suppression, fire prevention, emergency rescue, emergency medical service, and hazardous materials response; and to be capable of dealing with and terminating emergency situations which could threaten the operations, employees, or interest of the US Department of Energy operated Hanford Site. This includes response to surrounding fire departments/districts under a mutual aid agreement and contractual fire fighting, hazardous materials, and ambulance support to Washington Public Power Supply System (Supply System). The fire department also provides site fire marshal overview authority, fire system testing and maintenance, self-contained breathing apparatus maintenance, building tours and inspections, ignitable and reactive waste site inspections, prefire planning, and employee fire prevention education. This report gives a program overview, technical program baselines, and cost and schedule baseline

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Grand Junction, Colorado

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site Near Grand Junction, Colorado evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site. This risk assessment follows an approach outlined by the EPA. the first step is to evaluate ground water data collected from monitor wells at the site. Evaluation of these data showed that the contaminants of potential concern in the ground water are arsenic, cadmium, cobalt, fluoride, iron, manganese, molybdenum, nickel, sulfate, uranium, vanadium, zinc, and radium-226. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if they drank from a well installed in the contaminated ground water at the former processing site.

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Grand Junction, Colorado

International Nuclear Information System (INIS)

1994-06-01

This Baseline Risk Assessment of Ground Water Contamination at the Uranium Mill Tailings Site Near Grand Junction, Colorado evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site. This risk assessment follows an approach outlined by the EPA. the first step is to evaluate ground water data collected from monitor wells at the site. Evaluation of these data showed that the contaminants of potential concern in the ground water are arsenic, cadmium, cobalt, fluoride, iron, manganese, molybdenum, nickel, sulfate, uranium, vanadium, zinc, and radium-226. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if they drank from a well installed in the contaminated ground water at the former processing site

Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

International Nuclear Information System (INIS)

Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens; Starsec, Peter

2005-04-01

The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is established

Study of tunnelling through water-bearing fracture zones. Baseline study on technical issues with NE-1 as reference

Energy Technology Data Exchange (ETDEWEB)

Yanting Chang; Swindell, Robert; Bogdanoff, Ingvar; Lindstroem, Beatrice; Termen, Jens [WSP Sweden, Stockholm (Sweden) ; Starsec, Peter [SGI, Linkoeping (Sweden)

2005-04-01

The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for the management of Sweden's nuclear waste. SKB is investigating various designs for the construction of an underground deep repository for spent nuclear fuel at 500-600 m depths. For the construction of an access tunnel for such a deep repository, the possibility of encountering a water-bearing fracture zone cannot be discounted. Such a zone named NE-1 (deformation zone in accordance to SKB's terminology) was encountered during the construction of the Aespoe Hard Rock Laboratory (HRL) and difficulties with large water inflows were reported. With the aim to assess the feasibility of different technical solutions, SKB commissioned a baseline study into the passage of an access tunnel through a water-bearing fracture zone at three different depths (200 m, 400 m and 600 m). The objectives of this baseline study are to: Increase the knowledge of possible technical solutions for tunnelling through water-bearing fractures zones with the characteristics of the brittle deformation zone NE-1 at different depths, namely 200, 400 and 600 metres; Form a reference document to assist the engineering design and construction work for the passage through such a water-bearing fracture zone; To highlight the engineering parameters that should be obtained to facilitate design for the passage through water-bearing fracture zones.The study has been carried out in the following five stages: A. Compilation of the relevant data for deformation zone NE-1; B. Problem identification and proposal of technical solutions; C. Identification of hazards to be involved in the tunnel excavation; D. Recommendations and conclusions for further investigations; E. Documentation of the results in a final report. The analyses will be expressed in statistical/probabilistic terms where appropriate. In order to specify the precondition that will be valid for this study, a descriptive model of the water-bearing fracture zone is

The International Linear Collider Technical Design Report - Volume 2: Physics

CERN Document Server

Barklow, Tim; Fujii, Keisuke; Gao, Yuanning; Hoang, Andre; Kanemura, Shinya; List, Jenny; Logan, Heather E; Nomerotski, Andrei; Perelstein, Maxim; Peskin, Michael E; Pöschl, Roman; Reuter, Jürgen; Riemann, Sabine; Savoy-Navarro, Aurore; Servant, Geraldine; Tait, Tim M P

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

The International Linear Collider Technical Design Report - Volume 4: Detectors

CERN Document Server

Behnke, Ties; Burrows, Philip N.; Fuster, Juan; Peskin, Michael; Stanitzki, Marcel; Sugimoto, Yasuhiro; Yamada, Sakue; Yamamoto, Hitoshi

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

RADON BASELINE MONITORING AROUND A POTENTIAL SHALE GAS DEVELOPMENT SITE IN YORKSHIRE, ENGLAND.

Science.gov (United States)

Daraktchieva, Z; Wasikiewicz, J M; Howarth, C B; Bradley, E J

2017-11-01

The Vale of Pickering in Yorkshire, England has been identified as a potential area for shale gas extraction. Public Health England joined a collaboration led by the British Geological Survey for environmental baseline monitoring near the potential shale gas extraction site following a grant award from UK Government Department for Business, Energy and Industrial Strategy. The analysis of results for the first 6 months of indoor monitoring indicated that the results followed a log-normal distribution. The numbers of homes found to be at or above the Action Level followed the numbers predicted by the radon potential maps. The results from the measurements of outdoor air in this study indicated that the radon concentrations are slightly higher than previously measured but close to the detection limit of the technique. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

American Samoa Initial Technical Assessment Report

Energy Technology Data Exchange (ETDEWEB)

Busche, S.; Conrad, M.; Funk, K.; Kandt, A.; McNutt, P.

2011-09-01

This document is an initial energy assessment for American Samoa, the first of many steps in developing a comprehensive energy strategy. On March 1, 2010, Assistant Secretary of the Interior Tony Babauta invited governors and their staff from the Interior Insular Areas to meet with senior principals at the National Renewable Energy Laboratory (NREL). Meeting discussions focused on ways to improve energy efficiency and increase the deployment of renewable energy technologies in the U.S. Pacific Territories. In attendance were Governors Felix Camacho (Guam), Benigno Fitial (Commonwealth of the Northern Mariana Islands), and Togiola Tulafono, (American Samoa). This meeting brought together major stakeholders to learn and understand the importance of developing a comprehensive strategic plan for implementing energy efficiency measures and renewable energy technologies. For several decades, dependence on fossil fuels and the burden of high oil prices have been a major concern but never more at the forefront as today. With unstable oil prices, the volatility of fuel supply and the economic instability in American Samoa, energy issues are a high priority. In short, energy security is critical to American Samoa's future economic development and sustainability. Under an interagency agreement, funded by the Department of Interior's Office of Insular Affairs, NREL was tasked to deliver technical assistance to the islands of American Samoa. Technical assistance included conducting an initial technical assessment to define energy consumption and production data, establish an energy consumption baseline, and assist with the development of a strategic plan. The assessment and strategic plan will be used to assist with the transition to a cleaner energy economy. NREL provided an interdisciplinary team to cover each relevant technical area for the initial energy assessments. Experts in the following disciplines traveled to American Samoa for on-island site assessments: (1

Ultrasound-Guided Intermediate Site Greater Occipital Nerve Infiltration: A Technical Feasibility Study.

Science.gov (United States)

Zipfel, Jonathan; Kastler, Adrian; Tatu, Laurent; Behr, Julien; Kechidi, Rachid; Kastler, Bruno

2016-01-01

Two studies recently reported that computed tomography (CT) guided infiltration of the greater occipital nerve at its intermediate site allows a high efficacy rate with long-lasting pain relief following procedure in occipital neuralgia and in various craniofacial pain syndromes. The purpose of our study was to evaluate the technical feasibility and safety of ultrasound-guided intermediate site greater occipital nerve infiltration. Retrospective study. This study was conducted at the imaging department of a 1,409 bed university hospital. Local institutional review board approval was obtained and written consent was waived. In this retrospective study, 12 patients suffering from refractory occipital neuralgia or craniofacial pain syndromes were included between April and October 2014. They underwent a total of 21 ultrasound-guided infiltrations. Infiltration of the greater occipital nerve was performed at the intermediate site of the greater occipital nerve, at its first bend between obliqus capitis inferior and semispinalis capitis muscles with local anestetics and cortivazol. Technical success was defined as satisfactory diffusion of added iodinated contrast media in the fatty space between these muscles depicted on control CT scan. We also reported first data of immediate block test efficacy and initial clinical efficacy at 7 days, one month, and 3 months, defined by a decrease of at least 50% of visual analog scale (VAS) scores. Technical success rate was 95.24%. Patients suffered from right unilateral occipital neuralgia in 3 cases, left unilateral occipital neuralgia in 2 cases, bilateral occipital neuralgia in 2 cases, migraine in one case, cervicogenic headache in one case, tension-type headache in 2 cases, and cluster headache in one case. Block test efficacy was found in 93.3% (14/15) cases. Clinical efficacy was found in 80% of cases at 7 days, in 66.7% of cases at one month and in 60% of cases at 3 months. No major complications were noted. Some of the

Analysis of baseline gene expression levels from ...

Science.gov (United States)

The use of gene expression profiling to predict chemical mode of action would be enhanced by better characterization of variance due to individual, environmental, and technical factors. Meta-analysis of microarray data from untreated or vehicle-treated animals within the control arm of toxicogenomics studies has yielded useful information on baseline fluctuations in gene expression. A dataset of control animal microarray expression data was assembled by a working group of the Health and Environmental Sciences Institute's Technical Committee on the Application of Genomics in Mechanism Based Risk Assessment in order to provide a public resource for assessments of variability in baseline gene expression. Data from over 500 Affymetrix microarrays from control rat liver and kidney were collected from 16 different institutions. Thirty-five biological and technical factors were obtained for each animal, describing a wide range of study characteristics, and a subset were evaluated in detail for their contribution to total variability using multivariate statistical and graphical techniques. The study factors that emerged as key sources of variability included gender, organ section, strain, and fasting state. These and other study factors were identified as key descriptors that should be included in the minimal information about a toxicogenomics study needed for interpretation of results by an independent source. Genes that are the most and least variable, gender-selectiv

Technical summary of geological, hydrological, and engineering studies at the Slick Rock Uranium Mill Tailings sites, Slick Rock, Colorado

International Nuclear Information System (INIS)

1990-12-01

The purpose of this document is to provide the Colorado Department of Health (CDH) with a summary of the technical aspects of the proposed remedial action for the Slick Rock tailings near Slick Rock, Colorado. The technical issues summarized in this document are the geology and groundwater at the Burro Canyon disposal site and preliminary engineering considerations for the disposal cell

TECHNICAL EFFICIENCY AND IMPACT EVALUATION DIFFERENTIALS BETWEEN THE ADOPTERS AND NON-ADOPTERS OF NERICA IN THE SIX BASELINE STATES IN NIGERIA

Directory of Open Access Journals (Sweden)

Abiodun Elijah OBAYELU

2017-04-01

Full Text Available The study examined the adoption rate of New Rice for Africa (NERICA, technical efficiency differentials of production of these varieties between adopters and non-adopters and the determinants. It further analysed the impact of adoption of NERICA on area cultivated, output, yield, expenditure and total income of rice farmers in the NERICA baseline states in Nigeria. To achieve the objectives, it employed the descriptive statistics, stochastic production frontier and counterfactual outcomes framework of modern evaluation technique (the Local Average Treatment Effect to analyse 621 rice farmers across the six NERICA baseline states in Nigeria in 2012. The findings show that NERICA adopters were more technically efficient than the non-adopters. In addition, adoption of NERICA was found to significantly increase the areas of land cultivated, output, yield, household expenditure, per capita household expenditure and total income among NERICA adopters by 1.2ha (p < 0.01, 1998.2kg (p< 0.01, 191.2kg/ha (p < 0.1, N13,222.63≈$66.4 (p < 0.05, N2,015.6≈$10.1 (p < 0.05 and N145,098.7 ≈$728.0 (p < 0.01 respectively despite their high level of inefficiency (39 percent by the adopters. The positive impact of NERICA adoption on rice yields, poverty status measured by the per capita household expenditure and total farm income of farmers is a clear indication that NERICA has the potential to increase rice productivity, reduce poverty and food insecurity. NERICA adoption rate will rise if more farmers are aware of the varieties in the study. Farmers who had adopted, and government at all levels should therefore intensify their efforts to encourage others rice farmers possibly through the extension agents on the need to grow NERICA varieties so as to increase rice production level, reduce rice importation and ensure a sustainable rice production.

Test methods for on site measurement of resistivity of concrete. A RILEM TC-154 Technical Recommendation

NARCIS (Netherlands)

Polder, R.B.

2000-01-01

This paper describes methods to assess concrete resistivity on site for various purposes related to corrosion and protection of reinforcement. It is based on a first draft of a RILEM Technical Recommendation. The electrical resistivity of concrete can be related to the two processes involved in

Site characterization progress report: Yucca Mountain, Nevada. October 1, 1996--March 31, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

The report is the sixteenth in a series issued approximately every six months to report progress and results of site characterization activities being conducted to evaluate Yucca Mountain as a possible geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. This report highlights work started, in progress, and completed during the reporting period. In addition, this report documents and discusses changes to the Office of Civilian Radioactive Waste Management (OCRWM) Site Characterization Program (Program) resulting from the ongoing collection and evaluation of site information, systems analyses, development of repository and waste package designs, and results of performance assessment activities. Details on the activities summarized can be found in the numerous technical reports cited throughout the progress report. Yucca Mountain Site Characterization Project (Project) activities this period focused on implementing the near-term objectives of the revised Program Plan issued last period. Near-term objectives of the revised Program Plan include updating the US Department of Energy`s (DOE) repository siting guidelines to be consistent with a more focused performance-driven program; supporting an assessment in 1998 of the viability of continuing with actions leading to the licensing of a repository; and if the site is suitable, submittal of a Secretarial site recommendation to the President in 2001 and license application the US Nuclear Regulatory Commission (NRC) in 2002. During this reporting period, the Project developed and baselined its long-range plan in December 1996. That revision reflected the detailed fiscal year (FY) 1997 work scope and funding plan previously baselined at the end of FY 1996. Site characterization activities have been focused to answer the major open technical issues and to support the viability assessment.

Utilization of a Technical Peer Review to Support the Mission of the Nevada Test Site Community Advisory Board

International Nuclear Information System (INIS)

Dixon, Earle C.; Peterson, Kathleen

2003-01-01

The U. S. Department of Energy's (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Environmental Management (EM) Underground Test Area (UGTA) project addresses the characterization and needs for long-term monitoring of the subsurface contamination resulting from 828 underground nuclear weapon tests at the Nevada Test Site (NTS). EM promotes, and is required, to include stakeholders in its program. However, UGTA is a very complex program not easily understood by members of the public. The NTS Community Advisory Board (CAB), a federally chartered Site Specific Advisory Board (SSAB), has studied the UGTA project since 1996, and has found it a challenge to completely comprehend and provide NNSA/NV meaningful citizen input. The CAB realized the benefit of a technical peer review and in 2000 recommended to NNSA/NV that a peer review of the UGTA strategy would provide valuable feedback to the program to address underground contamination at the NTS. N NSA agreed to the CAB's recommendation, and moved forward with a scope of work to have the American Society of Mechanical Engineers (ASME) perform the peer review of the UGTA strategy. The ASME began the peer review in June 2001, and their final report was published in November 2001. In January 2002, the CAB devoted their monthly meeting in Las Vegas, Nevada to reporting the results of the peer review of the UGTA strategy to the public. Two public workshops were later held in the community of Amargosa, Nevada during the month of January to help educate and build interest in the CAB February 2002 monthly meeting which was also held in Amargosa. The CAB recommendation to NNSA to utilize a technical peer review has provided valuable information to NNSA, the State of Nevada, and the CAB. At other DOE sites SSABs are challenged by a number of complex, technical programs requiring considerable time and resources for the board to comprehend. It is worth considering the utilization of an independent

Independent technical evaluation and recommendations for contaminated groundwater at the department of energy office of legacy management Riverton processing site

Energy Technology Data Exchange (ETDEWEB)

Looney, Brain B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Denham, Miles E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Eddy-Dilek, Carol A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-04-01

The U.S. Department of Energy Office of Legacy Management (DOE-LM) manages the legacy contamination at the Riverton, WY, Processing Site – a former uranium milling site that operated from 1958 to 1963. The tailings and associated materials were removed in 1988-1989 and contaminants are currently flushing from the groundwater. DOE-LM commissioned an independent technical team to assess the status of the contaminant flushing, identify any issues or opportunities for DOE-LM, and provide key recommendations. The team applied a range of technical frameworks – spatial, temporal, hydrological and geochemical – in performing the evaluation. In each topic area, an in depth evaluation was performed using DOE-LM site data (e.g., chemical measurements in groundwater, surface water and soil, water levels, and historical records) along with information collected during the December 2013 site visit (e.g., plant type survey, geomorphology, and minerals that were observed, collected and evaluated).

European youth care sites serve different populations of adolescents with cannabis use disorder. Baseline and referral data from the INCANT trial.

Science.gov (United States)

Phan, Olivier; Henderson, Craig E; Angelidis, Tatiana; Weil, Patricia; van Toorn, Manja; Rigter, Renske; Soria, Cecilia; Rigter, Henk

2011-07-12

MDFT (Multidimensional Family Therapy) is a family based outpatient treatment programme for adolescent problem behaviour. MDFT has been found effective in the USA in adolescent samples differing in severity and treatment delivery settings. On request of five governments (Belgium, France, Germany, the Netherlands, and Switzerland), MDFT has now been tested in the joint INCANT trial (International Cannabis Need of Treatment) for applicability in Western Europe. In each of the five countries, study participants were recruited from the local population of youth seeking or guided to treatment for, among other things, cannabis use disorder. There is little information in the literature if these populations are comparable between sites/countries or not. Therefore, we examined if the study samples enrolled in the five countries differed in baseline characteristics regarding demographics, clinical profile, and treatment delivery setting. INCANT was a multicentre phase III(b) randomized controlled trial with an open-label, parallel group design. It compared MDFT with treatment as usual (TAU) at and across sites in Berlin, Brussels, Geneva, The Hague and Paris.Participants of INCANT were adolescents of either sex, from 13 through 18 years of age, with a cannabis use disorder (dependence or abuse), and at least one parent willing to take part in the treatment. In total, 450 cases/families were randomized (concealed) into INCANT. We collected data about adolescent and family demographics (age, gender, family composition, school, work, friends, and leisure time). In addition, we gathered data about problem behaviour (substance use, alcohol and cannabis use disorders, delinquency, psychiatric co-morbidity).There were no major differences on any of these measures between the treatment conditions (MDFT and TAU) for any of the sites. However, there were cross-site differences on many variables. Most of these could be explained by variations in treatment culture, as reflected by

European youth care sites serve different populations of adolescents with cannabis use disorder. Baseline and referral data from the INCANT trial

Directory of Open Access Journals (Sweden)

Rigter Renske

2011-07-01

Full Text Available Abstract Background MDFT (Multidimensional Family Therapy is a family based outpatient treatment programme for adolescent problem behaviour. MDFT has been found effective in the USA in adolescent samples differing in severity and treatment delivery settings. On request of five governments (Belgium, France, Germany, the Netherlands, and Switzerland, MDFT has now been tested in the joint INCANT trial (International Cannabis Need of Treatment for applicability in Western Europe. In each of the five countries, study participants were recruited from the local population of youth seeking or guided to treatment for, among other things, cannabis use disorder. There is little information in the literature if these populations are comparable between sites/countries or not. Therefore, we examined if the study samples enrolled in the five countries differed in baseline characteristics regarding demographics, clinical profile, and treatment delivery setting. Methods INCANT was a multicentre phase III(b randomized controlled trial with an open-label, parallel group design. It compared MDFT with treatment as usual (TAU at and across sites in Berlin, Brussels, Geneva, The Hague and Paris. Participants of INCANT were adolescents of either sex, from 13 through 18 years of age, with a cannabis use disorder (dependence or abuse, and at least one parent willing to take part in the treatment. In total, 450 cases/families were randomized (concealed into INCANT. Results We collected data about adolescent and family demographics (age, gender, family composition, school, work, friends, and leisure time. In addition, we gathered data about problem behaviour (substance use, alcohol and cannabis use disorders, delinquency, psychiatric co-morbidity. There were no major differences on any of these measures between the treatment conditions (MDFT and TAU for any of the sites. However, there were cross-site differences on many variables. Most of these could be explained by

Summary Report for the Technical Interchange Meeting on Development of Baseline Material Properties and Design Guidelines for In-Space Manufacturing Activities

Science.gov (United States)

Prater, T. J.; Bean, Q. A.; Werkheiser, N. J.; Johnston, M. M.; Ordonez, E. A.; Ledbetter, F. E.; Risdon, D. L.; Stockman, T. J.; Sandridge, S. K. R.; Nelson, G. M.

2016-01-01

NASA Marshall Space Flight Center (MSFC) and the Agency as a whole are currently engaged in a number of in-space manufacturing (ISM) activities that have the potential to reduce launch costs, enhance crew safety, and provide the capabilities needed to undertake long-duration spaceflight. The recent 3D Printing in Zero-G experiment conducted on board the International Space Station (ISS) demonstrated that parts of acrylonitrile butadiene styrene (ABS) plastic can be manufactured in microgravity using fused deposition modeling (FDM). This project represents the beginning of the development of a capability that is critical to future NASA missions. Current and future ISM activities will require the development of baseline material properties to facilitate design, analysis, and certification of materials manufactured using in-space techniques. The purpose of this technical interchange meeting (TIM) was to bring together MSFC practitioners and experts in materials characterization and development of baseline material properties for emerging technologies to advise the ISM team as we progress toward the development of material design values, standards, and acceptance criteria for materials manufactured in space. The overall objective of the TIM was to leverage MSFC's shared experiences and collective knowledge in advanced manufacturing and materials development to construct a path forward for the establishment of baseline material properties, standards development, and certification activities related to ISM. Participants were asked to help identify research and development activities that will (1) accelerate acceptance and adoption of ISM techniques among the aerospace design community; (2) benefit future NASA programs, commercial technology developments, and national needs; and (3) provide opportunities and avenues for further collaboration.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

International Nuclear Information System (INIS)

1994-01-01

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

Technical procedures for ecology: Environmental field program, Deaf Smith County Site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including walkover surveys for threatened, endangered, or candidate species; vegetation classification and mapping; reclamation planning; wetland and floodplain determination and characterization of playas; wildlife habitat mapping methods; mammal sampling; bird survey methods; reptile and amphibian survey methods; preexisting environmental; stress and disturbance studies methods; voucher specimens for plants; and voucher specimens to wildlife. 9 refs., 5 figs., 1 tab

Technical procedures for water resources: Volume 4, Deaf Smith County site, Texas: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the water Resources Site Study Plan: including Collection, Preservation, and Shipment of Ground-Water Samples; Inventory Current Water Use and Estimating Projected Water Use; Estimation of Precipitation Depth, Duration, Frequence; Estimation of Probable Maximum Precipitation; Calculation of Floodplains

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Shiprock, New Mexico. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

This baseline risk assessment at the former uranium mill tailings site near Shiprock, New Mexico, evaluates the potential impact to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an on-site disposal cell in 1986 through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. There are no domestic or drinking water wells in the contaminated ground water of the two distinct ground water units: the contaminated ground water in the San Juan River floodplain alluvium below the site and the contaminated ground water in the terrace alluvium area where the disposal cell is located. Because no one is drinking the affected ground water, there are currently no health or environmental risks directly associated with the contaminated ground water. However, there is a potential for humans, domestic animals, and wildlife to the exposed to surface expressions of ground water in the seeps and pools in the area of the San Juan River floodplain below the site. For these reasons, this risk assessment evaluates potential exposure to contaminated surface water and seeps as well as potential future use of contaminated ground water.

Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual

International Nuclear Information System (INIS)

Jenkins, J.B.

1996-01-01

The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten prototype units have been built and tested. This report describes the design of the new NIM and the testing that took place to verify its acceptability

The International Linear Collider Technical Design Report - Volume 2: Physics

Energy Technology Data Exchange (ETDEWEB)

Baer, Howard [Univ. of Oklahoma, Norman, OK (United States); Barklow, Tim [SLAC National Accelerator Lab., Menlo Park, CA (United States); Fujii, Keisuke [National Lab. for High Energy Physics (KEK), Tokai (Japan); Gao, Yuanning [Unlisted; Hoang, Andre [Univ. of Vienna (Austria); Kanemura, Shinya [Univ. of Toyama (Japan); List, Jenny [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Logan, Heather E. [Carleton Univ., Ottawa, ON (Canada); Nomerotski, Andrei [Univ. of Oxford (United Kingdom); Perelstein, Maxim [Cornell Univ., Ithaca, NY (United States); Peskin, Michael E. [SLAC National Accelerator Lab., Menlo Park, CA (United States); Pöschl, Roman [Univ. Paris-Sud, Orsay (France). Linear Accelerator Lab. (LAL); Reuter, Jürgen [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Riemann, Sabine [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Savoy-Navarro, Aurore [CNRS/IN2P3. Univ. Paris (France). Observatoire de Paris. AstroParticule et Cosmologie (APC); Servant, Geraldine [European Organization for Nuclear Research (CERN), Geneva (Switzerland); Tait, Tim P. [Univ. of California, Los Angeles, CA (United States); Yu, Jaehoon [Univ. of Science and Technology of China, Hefei (China)

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

The International Linear Collider Technical Design Report - Volume 4: Detectors

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Belfield, North Dakota. Revision 1

International Nuclear Information System (INIS)

1994-09-01

This risk assessment evaluates the potential for impacts to public health or the environment from contaminated ground water at this site caused by the burning of coal containing uranium to produce uranium. Potential risk is quantified for constituents introduced from the processing activities and not for those constituents naturally occurring in background ground water in the site vicinity. Because background ground water quality has the potential to cause adverse health effects from exposure through drinking, any risks associated with contaminants attributable to site activities are incremental to these risks from background. The incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition. The US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to remedy soil and ground water contamination at the site. The UMTRA Surface Project consists of determining the extent of soil contamination and disposing of the contaminated soils in an engineered disposal cell. The UMTRA Ground Water Project consists of evaluating ground water contamination. Under the UMTRA Ground Water Project, results of this risk assessment will help determine what ground water compliance strategy may be applied at the site

(Review Draft) Radiation Site Cleanup Regulations: Technical Support Document For The Development Of Radionuclide Cleanup Levels For Soil

Science.gov (United States)

This document describes parts of the technical analysis being undertaken in support of standards that ensure certain sites are cleaned up to a level that is protective of human health and the environment before they are released for public use.

Siting controversial facilities

International Nuclear Information System (INIS)

Baird, R.D.; Blacker, P.B.

1985-01-01

There is often significant difficulty involved with siting controversial facilities. The social and political problems are frequently far more difficult to resolve than the technical and economic issues. The tendancy for most developing organizations is to address only technical issues in the search for a technically optimal site, to the exclusion of such weighting considerations as the social and political climate associated with potential sites--an approach which often imperils the success of the project. The site selection processes currently suggested is summarized and two contemporary examples of their application are cited. The difference between developers' real objectives and the objectives they have implicitly assumed by adopting the recommended approaches without augmentation are noted. The resulting morass of public opposition is attributed to the failure to consider the needs of individuals and groups who stand to be negatively impacted by the development. A comprehensive implementation strategy which addresses non-technical consideration in parallel with technical ones is presented and evaluated

The SocioEconomic Analysis of Repository Siting (SEARS): Technical description: Final draft

International Nuclear Information System (INIS)

1984-11-01

Socioeconomic impacts must be assessed both for the near term and for the future. One means of addressing the need for the assessment of such impacts has been through the development of the computerized socioeconomic assessment model called the SocioEconomic Analysis of Repository Siting (SEARS) model. The SEARS model was developed for the Battelle Project Management Division. It was refined and adapted from state-of-the-art computerized projection models and thoroughly validated and is now available for use in projecting the likely socioeconomic impacts of a repository facility. This Technical Description is one of six major products that describe the SEARS modeling system. 61 refs., 11 figs., 9 tabs

Record of Technical Change No.2 for ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada''

International Nuclear Information System (INIS)

1999-01-01

This Record of Technical Change provides updates to the technical information included in ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada.''

Comprehensive Baseline Environmental Audit of the Inhalation Toxicology Research Institute, Albuquerque, New Mexico

International Nuclear Information System (INIS)

1993-06-01

This report documents the results of the Comprehensive Baseline Environmental Audit conducted at the Inhalation Toxicology Research Institute (ITRI) in Albuquerque, New Mexico. The scope of the audit at the ITRI was comprehensive, addressing environmental activities in the technical areas of air; soils, sediments, and biota; surface water/drinking water; groundwater; waste management; toxic and chemical materials; quality assurance; radiation; inactive waste sites; environmental management; and environmental monitoring programs. Specifically assessed was the compliance of ITRI operations and activities with Federal, state, and local regulations; DOE Orders; internal operating standards; and best management practices. Onsite activities included inspection of ITRI facilities and operations; review of site documents; interviews with DOE and contractor personnel, as well as representatives from state regulatory agencies; and reviews of previous appraisals. Using these sources of information, the environmental audit team developed findings, which fell into two general categories: compliance findings and best management practice findings. Each finding also identifies apparent causal factor(s) that contributed to the finding and will assist line management in developing ''root causes'' for implementing corrective actions

Technical procedures for water resources, Deaf Smith County site, Texas: Volume 1: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the Water Resources Site Study Plan including, determination of basin topographic characteristics, determination of channel and playa lake characteristics, operation of a stream gaging station, operation of a playa lake stage gaging system, and processing of data from a playa lake stage gaging system

Technical Training: WBTechT offers online training

CERN Multimedia

Monique Duval

2005-01-01

CERN Technical Training 2005 The 2005 CERN Web-Based Technical Training portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications and 90.- CHF for technical applications for three months' unlimited access. Visit the WBTechT portal or http://www.cern.ch/TechnicalTraining, and contact Technical.Training@cern.ch or your DTOs to find out more information. ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING Monique Duval 74924 technical.training@cern.ch

Technical Training: WBTechT offers online training

CERN Multimedia

Monique Duval

2005-01-01

CERN Technical Training 2005 The 2005 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications and 90.- CHF for technical applications for three months' unlimited access. Visit the WBTechT portal or http://www.cern.ch/TechnicalTraining, and contact Technical.Training@cern.ch or your DTO to find out more information. ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING Monique Duval 74924 technical.training@cern.ch

75 FR 26743 - Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To...

Science.gov (United States)

2010-05-12

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 12779-005] Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To Discuss Information and Monitoring Needs for a License Application for a Pilot Project May 5, 2010. a. Type of Application: Draft Pilot License Application. b. Project N...

STATUS OF THE US LONG BASELINE NEUTRINO EXPERIMENT STUDY.

Energy Technology Data Exchange (ETDEWEB)

BISHAI,M.

2006-09-21

The US Long Baseline Neutrino Experiment Study was commissioned jointly by Brookhaven National Laboratory and Fermi National Accelerator Laboratory to investigate the potential for future U.S. based long baseline neutrino oscillation experiments beyond the currently planned program. The Study focused on MW class convention at neutrino beams that can be produced at Fermilab or BNL. The experimental baselines are based on two possible detector locations: (1) off-axis to the existing Fermilab NuMI beamline at baselines of 700 to 810 km and (2) NSF's proposed future Deep Underground Science and Engineering Laboratory (DUSEL) at baselines greater than 1000 km. Two detector technologies are considered: a megaton class Water Cherenkov detector deployed deep underground at a DUSEL site, or a 100kT Liquid Argon Time-Projection Chamber (TPC) deployed on the surface at any of the proposed sites. The physics sensitivities of the proposed experiments are summarized. We find that conventional horn focused wide-band neutrino beam options from Fermilab or BNL aimed at a massive detector with a baseline of > 1000 km have the best sensitivity to CP violation and the neutrino mass hierarchy for values of the mixing angle {theta}{sub 13} down to 2.2{sup o}.

The International Linear Collider Technical Design Report - Volume 1: Executive Summary

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Brau, James E. [Univ. of Oregon, Eugene, OR (United States); Foster, Brian [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Fuster, Juan [Univ. of Valencia (Spain); Harrison, Mike [Brookhaven National Lab. (BNL), Upton, NY (United States); Paterson, James McEwan [SLAC National Accelerator Lab., Menlo Park, CA (United States); Peskin, Michael [SLAC National Accelerator Lab., Menlo Park, CA (United States); Stanitzki, Marcel [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Walker, Nicholas [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Yamamoto, Hitoshi [Tohoku Univ., Sendai (Japan)

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

HANFORD SITE SOLID WASTE MANAGEMENT ENVIRONMENTAL IMPACT STATEMENT TECHNICAL INFORMATION DOCUMENT [SEC 1 THRU 4

International Nuclear Information System (INIS)

FRITZ, L.L.

2004-01-01

This Technical Information Document (TID) provides engineering data to support DOE/EIS-0286, ''Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement''. Assumptions and waste volumes used to calculate engineering data are also provided in this document. This chapter provides a brief description of: the Solid Waste Management Program (including a description of waste types and known characteristics of waste covered under the program), the Hanford Site (including a general discussion of the operating areas), and the alternatives analyzed. The Hanford Site Solid Waste Management Program and DOE/EIS-0286 address solid radioactive waste types generated by various activities from both onsite and offsite generators. The Environmental Restoration (ER) waste management activities are not within the scope of DOE/EIS-0286 or this TID. Activities for processing and disposal of immobilized low-activity waste (ILAW) are not within the scope of the Solid Waste Management Program and this TID

Environmental Baseline File National Transportation

International Nuclear Information System (INIS)

Harris, M.

1999-01-01

This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics addressed include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

Radio-contaminated casualties treatment: an unusual application of technical shelters used on the Ile Longue site

International Nuclear Information System (INIS)

Laroche, P.; Rousset, J.; Abiliou, R.; Roe, H.; Berthelot, B.; Lemaire, L.

2002-01-01

While the radio-contaminated casualties treatment center (CTBRC) of the military hospital of Brest is reconstructed an unusual structure has been built on the Ile Longue site. Technical shelters (ETM) of the French military health service have been put together in order to constitute the CTBRC/ETM. This structure is adapted to the necessities of the nuclear site of Brest. First we explain the organization of the medical intervention in case of a nuclear accident; then we describe the functions of the CTBRC. People from hospital and medical teams of the nuclear oceanic French forces (FOST) take part in utilization, maintenance, training according to a particular protocol. (author)

Selecting, engineering and constructing drilling sites at the Geysers geothermal field. Geysers chinetsu ryoiki ni okeru kussaku shikichi no sentei engineering kochiku

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This paper describes some examples of selection, engineering and construction of drilling sites at the Geysers geothermal field in the northern district of California State. Steep landform, thin-layered soil and violent rainfall create unstable conditions bringing about numerous landslide in the field. Selection of a well drilling site appropriate in such conditions is started by analyzing the aerial photographs by technical staff. After site selection, prospecting and soil test are conducted and a working plan in the well site is decided to prepare engineering drawings. In the construction, land preparation, the open-cutting of base-line trench, etc. are carried out. The base-line trench is a large and sufficiently deep one which is open-cut to the front end or the middle of the bottom part of the well plateau. The final construction work is to build a leading casing for interpolating cementing. The well site construction in the Geysers geothermal field is done in consideration of protecting human life, health and properties. 1 fig.

Scoping evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Examples: Sandia National Laboratories and Los Alamos National Laboratory

International Nuclear Information System (INIS)

Gruebel, M.R.; Parsons, A.M.; Waters, R.D.

1996-01-01

The disposal of mixed low-level waste has become an issue for the U.S. Department of Energy and the States since the inception of the Federal Facilities Compliance Act in 1992. Fifteen sites, including Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL), have been evaluated to estimate their technical capabilities for disposal of this type of waste after it has been subjected to treatment processes. The analyses were designed to quantify the maximum permissible concentrations of radioactive and hazardous constituents in mixed low-level waste that could potentially be disposed of in a facility at one of the fifteen sites and meet regulatory requirements. The evaluations provided several major insights about the disposal of mixed low-level waste. All of the fifteen sites have the technical capability for disposal of some waste. Maximum permissible concentrations for the radioactive component of the waste at and sites such as SNL and LANL are almost exclusively determined by pathways other than through groundwater. In general, for the hazardous component of the waste, travel times through groundwater to a point 100 meters from the disposal facility are on the order of thousands of years. The results of the evaluations will be compared to actual treated waste that may be disposed of in a facility at one of these fifteen evaluated sites. These comparisons will indicate which waste streams may exceed the disposal limitations of a site and which component of the waste limits the technical acceptability for disposal. The technical analyses provide only partial input to the decision-making process for determining the disposal sites for mixed low-level waste. Other, less quantitative factors such as social and political issues will also be considered

Technical Assistance Plan (TAP)

Science.gov (United States)

A Technical Assistance Plan (TAP) enables community groups to retain the services of an independent technical advisor and to provide resources for a community group to help inform other community members about site decisions.

EPA R1 RCRA Corrective Action 2020 Baseline Site Property Boundaries

Data.gov (United States)

U.S. Environmental Protection Agency — Property boundaries as indicated in figures of all facilities subject to RCRA Corrective Action on the 2020 baseline in Region 1. For more information on the RCRA...

Baseline mapping study of the Steed Pond aquifer and vadose zone beneath A/M Area, Savannah River Site, Aiken, South Carolina

International Nuclear Information System (INIS)

Jackson, D.G. Jr.

2000-01-01

This report presents the second phase of a baseline mapping project conducted for the Environmental Restoration Department (ERD) at Savannah River Site. The purpose of this second phase is to map the structure and distribution of mud (clay and silt-sized sediment) within the vadose zone beneath A/M Area. The results presented in this report will assist future characterization and remediation activities in the vadose zone and upper aquifer zones in A/M Area

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

International Nuclear Information System (INIS)

Meek, N.C.; Ingram, S.; Page, J.

2003-01-01

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

Technical Note

African Journals Online (AJOL)

Administratör

In this report on four patients, we did not use any of these techniques. The existence and the site of the fistulas was clearly demonstrated using basic but important preoperative detailed assessment and two intraoperative findings. The preoperative referral note that indicated the site of technical difficulty during the previous ...

Financial services FY 1996 site support program plan, WBS 6.10.4. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Schafer, D.D.

1995-09-01

This program plan outlines the financial services to be provided to the Hanford reservation by the Westinghouse Hanford Company. The topics of the plan include the Hanford strategic plan, program mission, program strategy, technical requirements baseline, schedule baseline, cost baseline, performance measures, technical objectives, program performance and program funding required.

Financial services FY 1996 site support program plan, WBS 6.10.4. Revision 1

International Nuclear Information System (INIS)

Schafer, D.D.

1995-09-01

This program plan outlines the financial services to be provided to the Hanford reservation by the Westinghouse Hanford Company. The topics of the plan include the Hanford strategic plan, program mission, program strategy, technical requirements baseline, schedule baseline, cost baseline, performance measures, technical objectives, program performance and program funding required

Survey package: Technical and contracting strategies for single-shell tank waste retrieval on the Hanford Site

International Nuclear Information System (INIS)

Ramsower, D.C.

1995-01-01

Westinghouse Hanford Company is interested in innovative, commercially available or adaptable retrieval system equipment, concepts, and contracting strategies that will ad to existing Hanford Site technology and significantly reduce cost and/or risk from the baseline retrieval approach of sluicing (hydraulically mining) the waste from the SSTs onsite. The objective of this request is to gather information from industry to identify and summarize a suite of retrieval-related components, systems, and contracting approaches. This information will be used to ensure that WHC understands the various waste retrieval alternative approaches, their risks, and their application on the Hanford Site tanks for those occasions when sluicing is not sufficiently effective, appropriate, or cost-effective. An additional objective is to facilitate industry's understanding of the tank and site interface requirements for SST waste retrieval and the complex statutory, legal, regulatory, labor, and other institutional standards being applied to the Hanford Site. This effort will identify and summarize retrieval solutions by the end of September 1996 so that a clear basis for future retrieval program decisions can be established

SRP baseline hydrogeologic investigation: Aquifer characterization

Energy Technology Data Exchange (ETDEWEB)

Strom, R.N.; Kaback, D.S.

1992-03-31

An investigation of the mineralogy and chemistry of the principal hydrogeologic units and the geochemistry of the water in the principal aquifers at Savannah River Site (SRS) was undertaken as part of the Baseline Hydrogeologic Investigation. This investigation was conducted to provide background data for future site studies and reports and to provide a site-wide interpretation of the geology and geochemistry of the Coastal Plain Hydrostratigraphic province. Ground water samples were analyzed for major cations and anions, minor and trace elements, gross alpha and beta, tritium, stable isotopes of hydrogen, oxygen, and carbon, and carbon-14. Sediments from the well borings were analyzed for mineralogy and major and minor elements.

The TDAQ Baseline Architecture

CERN Multimedia

Wickens, F J

The Trigger-DAQ community is currently busy preparing material for the DAQ, HLT and DCS TDR. Over the last few weeks a very important step has been a series of meetings to complete agreement on the baseline architecture. An overview of the architecture indicating some of the main parameters is shown in figure 1. As reported at the ATLAS Plenary during the February ATLAS week, the main area where the baseline had not yet been agreed was around the Read-Out System (ROS) and details in the DataFlow. The agreed architecture has: Read-Out Links (ROLs) from the RODs using S-Link; Read-Out Buffers (ROB) sited near the RODs, mounted in a chassis - today assumed to be a PC, using PCI bus at least for configuration, control and monitoring. The baseline assumes data aggregation, in the ROB and/or at the output (which could either be over a bus or in the network). Optimization of the data aggregation will be made in the coming months, but the current model has each ROB card receiving input from 4 ROLs, and 3 such c...

On-site and off-site activities

International Nuclear Information System (INIS)

Martin, H.D.

1986-01-01

Design principles for NPP training programs. Effects of NPP contracts. Effects of domestic industrial activities. The role of international bodies. Requirements for on-site training. Training abroad, technical, financial and social aspects. Training center on-site, an evaluation. (orig.)

Guam Initial Technical Assessment Report

Energy Technology Data Exchange (ETDEWEB)

Baring-Gould, I.; Conrad, M.; Haase, S.; Hotchkiss, E.; McNutt, P.

2011-04-01

Under an interagency agreement, funded by the Department of Interior's (DOI) Office of Insular Affairs (OIA), the National Renewable Energy Laboratory (NREL) was tasked to deliver technical assistance to the island of Guam by conducting an island initial technical assessment that would lay out energy consumption and production data and establish a baseline. This assessment will be used to conduct future analysis and studies by NREL that will estimate energy efficiency and renewable energy potential for the island of Guam.

OCRWM baseline management procedure for document identifiers

International Nuclear Information System (INIS)

1993-03-01

This procedure establishes a uniform numbering system (document identifier) for all Program and project technical, cost, and schedule baselines, and selected management and procurement documents developed for and controlled by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System (CRWMS). The document identifier defined in this procedure is structured to ensure that the relational integrity between configuration items (CIs) and their associated documentation and software is maintained, traceable, categorical, and retrievable for the life of the program

The SocioEconomic Analysis of Repository Siting (SEARS): Technical Documentation: Volume 1, Description of code and files

International Nuclear Information System (INIS)

Kiel, B.; Parpia, B.; Murdock, S.; Hamm, R.; Fannin, D.; Ransom-Nelson, W.; Leistritz, F.L.

1985-05-01

The SEARS Model is a comprehensive, highly flexible, user-oriented system for projecting economic, demographic, public service and fiscal impacts of a high-level nuclear waste repository siting. Both baseline and project-related impact projections may be performed for regions, counties, municipalities, and school districts. It is an interactive APL model requiring comprehensive data bases and parameters to generate the outputs desired. 75 refs., 24 figs., 14 tabs

Technical Basis for PNNL Beryllium Inventory

Energy Technology Data Exchange (ETDEWEB)

Johnson, Michelle Lynn

2014-07-09

The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

Pinellas Plant Environmental Baseline Report

Energy Technology Data Exchange (ETDEWEB)

1997-06-01

The Pinellas Plant has been part of the Department of Energy`s (DOE) nuclear weapons complex since the plant opened in 1957. In March 1995, the DOE sold the Pinellas Plant to the Pinellas County Industry Council (PCIC). DOE has leased back a large portion of the plant site to facilitate transition to alternate use and safe shutdown. The current mission is to achieve a safe transition of the facility from defense production and prepare the site for alternative uses as a community resource for economic development. Toward that effort, the Pinellas Plant Environmental Baseline Report (EBR) discusses the current and past environmental conditions of the plant site. Information for the EBR is obtained from plant records. Historical process and chemical usage information for each area is reviewed during area characterizations.

Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1987-10-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

A contractor report to the Department of Energy on environmental management baseline programs and integration opportunities (discussion draft)

International Nuclear Information System (INIS)

1997-05-01

In July 1996, the US Department of Energy (DOE) Assistant Secretary for Environmental Management (EM) chartered a government contractor led effort to develop a suite of technically defensible, integrated alternatives which meet the EM mission. The contractor team was challenged to ''think outside-the-box'' for solutions that cross traditional site boundaries and enable the programs to get the job done at an earlier date and at a lower cost. This report documents baseline programs current plans for material disposition and presents the opportunities for additional acceleration of cleanup and cost savings. A graphical depiction of the disposition of EM-owned waste and material from current state to final disposition is shown as disposition maps in Attachments 1, 3, 5, 7, 9, and 11. These disposition maps detail the material disposition at eleven major DOE sites as planned in the current discussion draft plan, Accelerating Cleanup: Focus on 2006. Maps reflecting material disposition at additional sites will be added in the future. Opportunities to further accelerate the cleanup of DOE-EM sites and reduce the overall cost of cleanup are depicted in the alternative disposition maps shown in Attachments 2, 4, 6, 8, 10, and 12. These integration opportunities bring nation-wide resources to bear on common problems facing the DOE sites

Aedes aegypti breeding ecology in Guerrero: cross-sectional study of mosquito breeding sites from the baseline for the Camino Verde trial in Mexico

OpenAIRE

Arcadio Morales-Pérez; Elizabeth Nava-Aguilera; Alejandro Balanzar-Martínez; Antonio Juan Cortés-Guzmán; David Gasga-Salinas; Irma Esther Rodríguez-Ramos; Alba Meneses-Rentería; Sergio Paredes-Solís; José Legorreta-Soberanis; Felipe Gil Armendariz-Valle; Robert J. Ledogar; Anne Cockcroft; Neil Andersson

2017-01-01

Abstract Background Understanding the breeding patterns of Aedes aegypti in households and the factors associated with infestation are important for implementing vector control. The baseline survey of a cluster randomised controlled trial of community mobilisation for dengue prevention in Mexico and Nicaragua collected information about the containers that are the main breeding sites, identified possible actions to reduce breeding, and examined factors associated with household infestation. T...

On-site gamma dose rates at the Andreeva Bay shore technical base, northwest Russia.

Science.gov (United States)

Reistad, O; Dowdall, M; Standring, W J F; Selnaes, Ø G; Hustveit, S; Steinhusen, F; Sørlie, A

2008-07-01

The spent nuclear fuel (SNF) and radioactive waste (RAW) storage facility at Andreeva Bay shore technical base (STB) is one of the largest and most hazardous nuclear legacy sites in northwest Russia. Originally commissioned in the 1960s the facility now stores large amounts of SNF and RAW associated with the Russian Northern Fleet of nuclear powered submarines. The objective of the present study was to map ambient gamma dose rates throughout the facility, in particular at a number of specific sites where SNF and RAW are stored. The data presented here are taken from a Norwegian-Russian collaboration enabling the first publication in the scientific literature of the complete survey of on-site dose rates. Results indicate that elevated gamma dose rates are found primarily at discrete sites within the facility; maximum dose rates of up to 1000 microSv/h close to the ground (0.1m) and up to 3000 microSv/h at 1m above ground were recorded, higher doses at the 1m height being indicative primarily of the presence of contaminated equipment as opposed to ground contamination. Highest dose rates were measured at sites located in the immediate vicinity of buildings used for storing SNF and sites associated with storage of solid and liquid radioactive wastes. Elevated dose rates were also observed near the former channel of a small brook that became heavily contaminated as a result of radioactive leaks from the SNF storage at Building 5 starting in 1982. Isolated patches of elevated dose rates were also observed throughout the STB. A second paper detailing the radioactive soil contamination at the site is published in this issue of Journal of Environmental Radioactivity.

Environmental Baseline File for National Transportation

International Nuclear Information System (INIS)

1999-01-01

This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics address include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

Technical area status report for chemical/physical treatment

International Nuclear Information System (INIS)

Brown, C.H. Jr.; Schwinkendorf, W.E.

1993-08-01

The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs and activities throughout the DOE Complex. The Mixed Waste Integrated Program (MWIP) was created by the DOE Office of Technology Development (OTD) to develop, deploy, and complete appropriate technologies for the treatment of an DOE low-level mixed waste (LLMW). The MWIP mission includes development of strategies related to enhanced waste form production, improvements to and testing of the EM-30 baseline flowsheet for mixed waste treatment, programmatic oversight for ongoing technical projects, and specific technical tasks related to the site specific Federal Facilities Compliance Agreement (FFCA). The MWIP has established five Technical Support Groups (TSGs) based on primary functional areas of the Mixed Waste Treatment Plant) identified by EM-30. These TSGs are: (1) Front-End Waste Handling, (2) Chemical/Physical Treatment, (3) Waste Destruction and Stabilization, (4) Second-stage Destruction and Offgas Treatment, and (5) Final Waste Forms. The focus of this document is the Chemical/Physical Treatment System (CPTS). The CPTS performs the required pretreatment and/or separations on the waste streams passing through the system for discharge to the environment or efficient downstream processing. Downstream processing can include all system components except Front-End Waste Handling. The primary separations to be considered by the CPTS are: (1) removal of suspended and dissolved solids from aqueous and liquid organic streams, (2) separation of water from organic liquids, (3) treatment of wet and dry solids, including separation into constituents as required, for subsequent thermal treatment and final form processing, (4) mercury removal and control, and (5) decontamination of equipment and waste classified as debris

Technical procedures for water resources: Volume 3, Environmental Field Program, Deaf Smith County Site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Water Resources (ONWI, 1987). This technical procedure (TP) has been developed to implement the field program described in the Water Resources Site Study Plan. This procedure provides the general method for the field collection of water and sediment samples from playa lakes using an Alpha horizontal type sampler or equivalent or a peristaltic pump for water and a KB-coring devise or ponar grab for sediments. The samples will be preserved and then shipped to a laboratory for analysis. The water quality and sediment samples will be collected as part of the surface-water quality field study described in the Site Plan for Water Resources. 15 refs., 5 figs., 3 tabs

Technical procedures for the implementation of cultural resource site studies, Deaf Smith County, Texas: Preliminary draft

International Nuclear Information System (INIS)

1987-01-01

Cultural resources at the Deaf Smith County site will be identified, evaluated and managed through the implementation of studies detailed in the Site Study Plan for Cultural Resources. This technical procedure outlines the conduct of pedestrian survey and the documentation of identified cultural resources. The purpose of the field surveys is to identify and document cultural resources in the areas that will be affected by site characterization activities and to record the environmental setting of identified cultural resources. Three pedestrian surveys will cover 100 percent of the on-site and off-site project areas. Survey 1 will provide coverage of the Repository Surface Facility (RSF) area, which includes the Exploratory Shaft Facility (ESF) and two linear engineering design borehole (EDBH) seismic survey corridors. Survey 2 will provide coverage of a 39 km 2 (15 mi 2 ) area that includes the 23 km 2 (9 mi 2 ) Deaf Smith County site plus a 0.4 to 0.8 kM (1/4 to 1/2 mi) border area but excludes the area covered by Survey 1. Survey 3 will cover offsite geotechnical test areas, such as the locations of playa boreholes, deep playa wells, hydrologic tests, site foundation borings, and their access routes. The purpose of site documentation or recording is to address the project information needs for land use permits and approvals, engineering design support, and cultural resource evaluation for National Register of Historic Places eligibility. Site documentation will consist of gathering sufficient data on identified resources to complete Texas Natural Resource Information System (TNRIS). 7 refs., 3 figs

A comparison of baseline methodologies for 'Reducing Emissions from Deforestation and Degradation'

Directory of Open Access Journals (Sweden)

Kok Kasper

2009-07-01

Full Text Available Abstract Background A mechanism for emission reductions from deforestation and degradation (REDD is very likely to be included in a future climate agreement. The choice of REDD baseline methodologies will crucially influence the environmental and economic effectiveness of the climate regime. We compare three different historical baseline methods and one innovative dynamic model baseline approach to appraise their applicability under a future REDD policy framework using a weighted multi-criteria analysis. Results The results show that each baseline method has its specific strengths and weaknesses. Although the dynamic model allows for the best environmental and for comparatively good economic performance, its high demand for data and technical capacity limit the current applicability in many developing countries. Conclusion The adoption of a multi-tier approach will allow countries to select the baseline method best suiting their specific capabilities and data availability while simultaneously ensuring scientific transparency, environmental effectiveness and broad political support.

EML Chester - 1982. Annual report of the Regional Baseline Station at Chester, New Jersey

International Nuclear Information System (INIS)

Volchok, H.L.

1982-11-01

The Environmental Measurements Laboratory (EML) has maintained a regional baseline station at Chester, New Jersey since 1976. The site provides EML with a remote, rural facility for carrying out regional baseline research and for testing field equipment. This report updates the various programs underway at the Chester site. Separate abstracts have been prepared for the included papers

Scoping evaluation of the technical capabilities of DOE sites for disposal of hazardous metals in mixed low-level waste

International Nuclear Information System (INIS)

Gruebel, M.M.; Waters, R.D.; Langkopf, B.S.

1997-05-01

A team of analysts designed and conducted a scoping evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of the hazardous metals in mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Eight hazardous metals were evaluated: arsenic, barium, cadmium, chromium, lead, mercury, selenium, and silver. The analysis considered transport only through the groundwater pathway. The results are reported as site-specific estimates of maximum concentrations of each hazardous metal in treated mixed low-level waste that do not exceed the performance measures established for the analysis. Also reported are site-specific estimates of travel times of each hazardous metal to the point of compliance

National greenhouse gas emissions baseline scenarios. Learning from experiences in developing countries

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-04-15

This report reviews national approaches to preparing baseline scenarios of greenhouse-gas (GHG) emissions. It does so by describing and comparing in non-technical language existing practices and choices made by ten developing countries - Brazil, China, Ethiopia, India, Indonesia, Kenya, Mexico, South Africa, Thailand and Vietnam. The review focuses on a number of key elements, including model choices, transparency considerations, choices about underlying assumptions and challenges associated with data management. The aim is to improve overall understanding of baseline scenarios and facilitate their use for policy-making in developing countries more broadly. The findings are based on the results of a collaborative project involving a number of activities undertaken by the Danish Energy Agency, the Organisation for Economic Co-operation and Development (OECD) and the UNEP Risoe Centre (URC), including a series of workshops on the subject. The ten contributing countries account for approximately 40% of current global GHG emissions - a share that is expected to increase in the future. The breakdown of emissions by sector varies widely among these countries. In some countries, the energy sector is the leading source of emissions; for others, the land-use sector and/or agricultural sector dominate emissions. The report underscores some common technical and financial capacity gaps faced by developing countries when preparing baseline scenarios. It does not endeavour to propose guidelines for preparing baseline scenarios. Rather, it is hoped that the report will inform any future attempts at preparing such kind of guidelines. (Author)

Modeling of 137Cs and 90Sr behavior in the soil-plant system within the territory adjacent to 'Experimental field' technical site in the Semipalatinsk test site

International Nuclear Information System (INIS)

Spiridonov, S.I.; Gontarenko, I.A.; Mukusheva, M.K.

2005-01-01

Modelling of 137 Cs and 90 Sr behavior in the soil-plant system is presented. Models have been parameterized for the area adjacent to the 'Experimental Field' Technical Site of the Semipalatinsk Test Site. The models describe the main processes responsible for changes of 137 Cs and 90 Sr content in the soil solution and, thereby, dynamics of radionuclides intake by vegetation. Results are presented from perspective and retrospective calculations, that reflect the dynamics of 137 and 90 Sr distribution by species in soil after nuclear explosions. The importance of factors governing radionuclide accumulation in plants within Semipalatinsk test site area is assessed. The analysis of sensitivity of model output variable to change in its parameters has revealed that the key soil properties significantly influence the results of prediction of radionuclide content in plants. (author)

[The LESS (Laparo-endoscopic Single-Site) procedure in urology. Technical and clinical aspects].

Science.gov (United States)

Neri, F; Cindolo, L; Gidaro, S; Schips, L

2010-01-01

Minimally invasive urology is rapidly advancing, and single-site laparoscopic surgery is being explored clinically. Such laparoscopic procedures are technically challenging and require an experienced laparoscopic surgeon due to the lack of port placement triangulation and instrument clashing. In the last years several surgeons all over the world have explored the feasibility and safety of LESS using several and different ports, approaches and devices. Hundreds of procedures have been described with overall favorable intraoperative and postoperative outcomes. Our experience consists of more than 30 procedures successfully completed for adrenal, kidney disease and varicocele. To date, LESS could be considered feasible and effective using currently available devices, however it is to be considered as an initial status technique requiring further confirmatory studies and advanced laparoscopic skills.

CALS Baseline Architecture Analysis of Weapons System. Technical Information: Army, Draft. Volume 8

Science.gov (United States)

1989-09-01

This effort was performed to provide a common framework for analysis and planning of CALS initiatives across the military services, leading eventually to the development of a common DoD-wide architecture for CALS. This study addresses Army technical ...

SRP Baseline Hydrogeologic Investigation, Phase 3

Energy Technology Data Exchange (ETDEWEB)

Bledsoe, H.W.

1988-08-01

The SRP Baseline Hydrogeologic Investigation was implemented for the purpose of updating and improving the knowledge and understanding of the hydrogeologic systems underlying the SRP site. Phase III, which is discussed in this report, includes the drilling of 7 deep coreholes (sites P-24 through P-30) and the installation of 53 observation wells ranging in depth from approximately 50 ft to more than 970 ft below the ground surface. In addition to the collection of geologic cores for lithologic and stratigraphic study, samples were also collected for the determination of physical characteristics of the sediments and for the identification of microorganisms.

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

Mixed waste focus area technical baseline report. Volume 2

International Nuclear Information System (INIS)

1997-04-01

As part of its overall program, the MWFA uses a national mixed waste data set to develop approaches for treating mixed waste that cannot be treated using existing capabilities at DOE or commercial facilities. The current data set was originally compiled under the auspices of the 1995 Mixed Waste Inventory Report. The data set has been updated over the past two years based on Site Treatment Plan revisions and clarifications provided by individual sites. The current data set is maintained by the MWFA staff and is known as MWFA97. In 1996, the MWFA developed waste groupings, process flow diagrams, and treatment train diagrams to systematically model the treatment of all mixed waste in the DOE complex. The purpose of the modeling process was to identify treatment gaps and corresponding technology development needs for the DOE complex. Each diagram provides the general steps needed to treat a specific type of waste. The NWFA categorized each MWFA97 waste stream by waste group, treatment train, and process flow. Appendices B through F provide the complete listing of waste streams by waste group, treatment train, and process flow. The MWFA97 waste strewn information provided in the appendices is defined in Table A-1

Using a site-specific technical error to establish training responsiveness: a preliminary explorative study.

Science.gov (United States)

Weatherwax, Ryan M; Harris, Nigel K; Kilding, Andrew E; Dalleck, Lance C

2018-01-01

Even though cardiorespiratory fitness (CRF) training elicits numerous health benefits, not all individuals have positive training responses following a structured CRF intervention. It has been suggested that the technical error (TE), a combination of biological variability and measurement error, should be used to establish specific training responsiveness criteria to gain further insight on the effectiveness of the training program. To date, most training interventions use an absolute change or a TE from previous findings, which do not take into consideration the training site and equipment used to establish training outcomes or the specific cohort being evaluated. The purpose of this investigation was to retrospectively analyze training responsiveness of two CRF training interventions using two common criteria and a site-specific TE. Sixteen men and women completed two maximal graded exercise tests and verification bouts to identify maximal oxygen consumption (VO 2 max) and establish a site-specific TE. The TE was then used to retrospectively analyze training responsiveness in comparison to commonly used criteria: percent change of >0% and >+5.6% in VO 2 max. The TE was found to be 7.7% for relative VO 2 max. χ 2 testing showed significant differences in all training criteria for each intervention and pooled data from both interventions, except between %Δ >0 and %Δ >+7.7% in one of the investigations. Training nonresponsiveness ranged from 11.5% to 34.6%. Findings from the present study support the utility of site-specific TE criterion to quantify training responsiveness. A similar methodology of establishing a site-specific and even cohort specific TE should be considered to establish when true cardiorespiratory training adaptations occur.

Technical training: WBTechT offers online training

CERN Multimedia

Davide Vitè

2006-01-01

The 2006 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications (e.g. Microsoft Office Suite, Frontpage, Dreamweaver, Illustrator, Photoshop) and 90.- CHF for technical applications (e.g. Unix, Oracle, Java, JavaScript, C, C++) for three months'unlimited access. Visit the WBTechT portal, or the WBTechT information page at http://www.cern.ch/TechnicalTraining Contact: Technical.Training@cern.ch or your DTO to find out more information.

Integrating risk management into the baselining process

International Nuclear Information System (INIS)

Jennett, N.; Tonkinson, A.

1994-01-01

These processes work together in building the project (comprised of the technical, schedule, and cost baselines) against which performance is measured and changes to the scope, schedule and cost of a project are managed and controlled. Risk analysis is often performed as the final element of the scheduling or estimating processes, a precursor to establishing cost and schedule contingency. However, best business practices dictate that information that may be crucial to the success of a project be analyzed and incorporated into project planning as soon as it is available and usable. The purpose or risk management is not to eliminate risk. Neither is it intended to suggest wholesale re-estimating and re-scheduling of a project. Rather, the intent is to make provisions to reduce and control the schedule and/or cost ramifications of risk by anticipating events and conditions that cannot be reliably planned for and which have the potential to negatively impact accomplishment of the technical objectives and requirements of the project

Engineering Technical Support Center Annual Report Fiscal ...

Science.gov (United States)

The United States Environmental Protection Agency (EPA or Agency) Office of Research and Development (ORD) created the Engineering Technical Support Center (ETSC) in 1987, one of several technical support centers created as part of the Technical Support Project (TSP). ETSC provides engineering expertise to Agency program and regional offices and remediation teams working at contaminated sites across the country. The ETSC is operated within ORD’s Land Remediation and Pollution Control Division (LRPCD) of the National Risk Management Research Laboratory (NRMRL) in Cincinnati, Ohio. The ETSC’s mission is to provide site-specific scientific and engineering technical support to Remedial Project Managers, On-Scene Coordinators, and other remediation personnel at contaminated sites. This allows local, regional, or national authorities to work more quickly, efficiently, and cost effectively, while also increasing the technical experience of the remediation team. Since its inception, the ETSC has supported countless projects across all EPA Regions in almost all states and territories. This report highlights significant projects the ETSC supported in fiscal year 2015 (FY15). These projects addressed an array of environmental scenarios, such as remote mining contamination, expansive landfill waste, cumulative impacts from multiple contamination sources, and persistent threats from abandoned industrial sites. Constructing and testing new and innovative treatment technol

Demonstration of innovative monitoring technologies at the Savannah River Integrated Demonstration Site

Energy Technology Data Exchange (ETDEWEB)

Rossabi, J. [Westinghouse Savannah River Co., Aiken, SC (United States); Jenkins, R.A.; Wise, M.B. [Oak Ridge National Lab., TN (United States)] [and others

1993-12-31

The Department of Energy`s Office of Technology Development initiated an Integrated Demonstration Program at the Savannah River Site in 1989. The objective of this program is to develop, demonstrate, and evaluate innovative technologies that can improve present-day environmental restoration methods. The Integrated Demonstration Program at SRS is entitled ``Cleanup of Organics in Soils and Groundwater at Non-Arid Sites.`` New technologies in the areas of drilling, characterization, monitoring, and remediation are being demonstrated and evaluated for their technical performance and cost effectiveness in comparison with baseline technologies. Present site characterization and monitoring methods are costly, time-consuming, overly invasive, and often imprecise. Better technologies are required to accurately describe the subsurface geophysical and geochemical features of a site and the nature and extent of contamination. More efficient, nonintrusive characterization and monitoring techniques are necessary for understanding and predicting subsurface transport. More reliable procedures are also needed for interpreting monitoring and characterization data. Site characterization and monitoring are key elements in preventing, identifying, and restoring contaminated sites. The remediation of a site cannot be determined without characterization data, and monitoring may be required for 30 years after site closure.

Demonstration of innovative monitoring technologies at the Savannah River Integrated Demonstration Site

International Nuclear Information System (INIS)

Rossabi, J.; Jenkins, R.A.; Wise, M.B.

1993-01-01

The Department of Energy's Office of Technology Development initiated an Integrated Demonstration Program at the Savannah River Site in 1989. The objective of this program is to develop, demonstrate, and evaluate innovative technologies that can improve present-day environmental restoration methods. The Integrated Demonstration Program at SRS is entitled ''Cleanup of Organics in Soils and Groundwater at Non-Arid Sites.'' New technologies in the areas of drilling, characterization, monitoring, and remediation are being demonstrated and evaluated for their technical performance and cost effectiveness in comparison with baseline technologies. Present site characterization and monitoring methods are costly, time-consuming, overly invasive, and often imprecise. Better technologies are required to accurately describe the subsurface geophysical and geochemical features of a site and the nature and extent of contamination. More efficient, nonintrusive characterization and monitoring techniques are necessary for understanding and predicting subsurface transport. More reliable procedures are also needed for interpreting monitoring and characterization data. Site characterization and monitoring are key elements in preventing, identifying, and restoring contaminated sites. The remediation of a site cannot be determined without characterization data, and monitoring may be required for 30 years after site closure

Design and Baseline Findings of a Multi-site Non-randomized Evaluation of the Effect of a Health Programme on Microfinance Clients in India

OpenAIRE

Saha, Somen

2013-01-01

Microfinance is the provision of financial services for the poor. Health program through microfinance has the potential to address several access barriers to health. We report the design and baseline findings of a multi-site non-randomized evaluation of the effect of a health program on the members of two microfinance organizations from Karnataka and Gujarat states of India. Villages identified for roll-out of health services with microfinance were pair-matched with microfinance only villages...

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

International Nuclear Information System (INIS)

1996-03-01

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

Hanford spent fuel inventory baseline

International Nuclear Information System (INIS)

Bergsman, K.H.

1994-01-01

This document compiles technical data on irradiated fuel stored at the Hanford Site in support of the Hanford SNF Management Environmental Impact Statement. Fuel included is from the Defense Production Reactors (N Reactor and the single-pass reactors; B, C, D, DR, F, H, KE and KW), the Hanford Fast Flux Test Facility Reactor, the Shipping port Pressurized Water Reactor, and small amounts of miscellaneous fuel from several commercial, research, and experimental reactors

Corrective Action Investigation Plan for Corrective Action Unit 536: Area 3 Release Site, Nevada Test Site, Nevada (Rev. 0 / June 2003), Including Record of Technical Change No. 1

Energy Technology Data Exchange (ETDEWEB)

None

2003-06-27

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 536: Area 3 Release Site, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 536 consists of a single Corrective Action Site (CAS): 03-44-02, Steam Jenny Discharge. The CAU 536 site is being investigated because existing information on the nature and extent of possible contamination is insufficient to evaluate and recommend corrective action alternatives for CAS 03-44-02. The additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating CAAs and selecting the appropriate corrective action for this CAS. The results of this field investigation are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3-2004.

THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

Energy Technology Data Exchange (ETDEWEB)

Partnership, ALMA [Astrophysics Research Institute, Liverpool John Moores University, IC2, Liverpool Science Park, 146 Brownlow Hill, Liverpool L3 5RF (United Kingdom); Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S. [Joint ALMA Observatory, Alonso de Córdova 3107, Vitacura, Santiago (Chile); Lucas, R. [Institut de Planétologie et d’Astrophysique de Grenoble (UMR 5274), BP 53, F-38041 Grenoble Cedex 9 (France); Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W. [National Radio Astronomy Observatory, 520 Edgemont Road, Charlottesville, VA 22903 (United States); Asaki, Y. [National Astronomical Observatory of Japan, 2-21-1 Osawa, Mitaka, Tokyo 181-8588 (Japan); Matsushita, S. [Institute of Astronomy and Astrophysics, Academia Sinica, P.O. Box 23-141, Taipei 106, Taiwan (China); Hills, R. E. [Astrophysics Group, Cavendish Laboratory, JJ Thomson Avenue, Cambridge CB3 0HE (United Kingdom); Richards, A. M. S. [Jodrell Bank Centre for Astrophysics, School of Physics and Astronomy, University of Manchester, Oxford Road, Manchester M13 9PL (United Kingdom); Broguiere, D., E-mail: efomalon@nrao.edu [Institut de Radioastronomie Millime´trique (IRAM), 300 rue de la Piscine, Domaine Universitaire, F-38406 Saint Martin d’Hères (France); and others

2015-07-20

A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy.

THE 2014 ALMA LONG BASELINE CAMPAIGN: AN OVERVIEW

International Nuclear Information System (INIS)

Partnership, ALMA; Fomalont, E. B.; Vlahakis, C.; Corder, S.; Remijan, A.; Barkats, D.; Dent, W. R. F.; Phillips, N.; Cox, P.; Hales, A. S.; Lucas, R.; Hunter, T. R.; Brogan, C. L.; Amestica, R.; Cotton, W.; Asaki, Y.; Matsushita, S.; Hills, R. E.; Richards, A. M. S.; Broguiere, D.

2015-01-01

A major goal of the Atacama Large Millimeter/submillimeter Array (ALMA) is to make accurate images with resolutions of tens of milliarcseconds, which at submillimeter (submm) wavelengths requires baselines up to ∼15 km. To develop and test this capability, a Long Baseline Campaign (LBC) was carried out from 2014 September to late November, culminating in end-to-end observations, calibrations, and imaging of selected Science Verification (SV) targets. This paper presents an overview of the campaign and its main results, including an investigation of the short-term coherence properties and systematic phase errors over the long baselines at the ALMA site, a summary of the SV targets and observations, and recommendations for science observing strategies at long baselines. Deep ALMA images of the quasar 3C 138 at 97 and 241 GHz are also compared to VLA 43 GHz results, demonstrating an agreement at a level of a few percent. As a result of the extensive program of LBC testing, the highly successful SV imaging at long baselines achieved angular resolutions as fine as 19 mas at ∼350 GHz. Observing with ALMA on baselines of up to 15 km is now possible, and opens up new parameter space for submm astronomy

CERN Technical Training 2006 - WBTechT offers online training

CERN Multimedia

2006-01-01

The 2006 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications (e.g. Microsoft Office Suite, Frontpage, Dreamweaver, Illustrator, Photoshop) and 90.- CHF for technical applications (e.g. Unix, Oracle, Java, JavaScript, C, C++) for three months'unlimited access. Visit the WBTechT portal, or the WBTechT information page at http://www.cern.ch/TechnicalTraining, and contact technical.training@cern.ch or your DTO to find out more information. ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING technical.training@cern.ch

CERN Technical Training 2006: WBTechT offers online training

CERN Multimedia

Davide Vitè

2006-01-01

The 2006 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications (e.g. Microsoft Office Suite, Frontpage, Dreamweaver, Illustrator, Photoshop) and 90.- CHF for technical applications (e.g. Unix, Oracle, Java, JavaScript, C, C++) for three months'unlimited access. Visit the WBTechT portal or http://www.cern.ch/TechnicalTraining, and contact Technical.Training@cern.ch or your DTO to find out more information. ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING technical.training@cern.ch

CERN Technical Training 2006: WBTechT offers online training

CERN Multimedia

Davide Vitè

2006-01-01

The 2006 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications (e.g. Microsoft Office Suite, Frontpage, Dreamweaver, Illustrator, Photoshop) and 90.- CHF for technical applications (e.g. Unix, Oracle, Java, JavaScript, C, C++) for three months' unlimited access. Visit the WBTechT portal or http://www.cern.ch/TechnicalTraining, and contact Technical.Training@cern.ch or your DTO to find out more information. ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING technical.training@cern.ch

ITER co-ordinated technical activities

International Nuclear Information System (INIS)

2001-01-01

As agreed upon between the ITER Engineering Design Activities (EDA) Parties 'Co-ordinated Technical Activities' (CTA) means technical activities which are deemed necessary to maintain the integrity of the international project, so as to prepare for the ITER joint implementation. The scope of these activities includes design adaptation to the specific site conditions, safety analysis and licensing preparation that are based on specific site offers, evaluation of cost and construction schedule, preparation of procurement documents and other issues raised by the Parties collectively, whilst assuring the coherence of the ITER project including design control

Eielson Air Force Base OU-1 baseline risk assessment

International Nuclear Information System (INIS)

Jarvis, M.T.; Jarvis, T.T.; Van Houten, N.C.; Lewis, R.E.

1993-09-01

This Baseline Risk Assessment report is the second volume in a set of three volumes for operable Unit 1 (OU-1). The companion documents contain the Remedial Investigation and the Feasibility Study. Operable Unit 1 (OU-1) is one of several groups of hazardous waste sites located at Eielson Air Force Base (AFB) near Fairbanks, Alaska. The operable units at Eielson are typically characterized by petroleum, oil, lubricant/solvent contamination, and by the presence of organics floating at the water table. In 1989 and 1990, firms under contract to the Air Force conducted field studies to gather information about the extent of chemical contamination in soil, groundwater, and soil air pore space (soil gas) at the site. This report documents the results of a baseline risk assessment, which uses the 1989 and 1991 site characterization database to quantify the potential human health risk associated with past Base industrial activities in the vicinity of OU-1. Background data collected in 1992 were also used in the preparation of this report

SCFA lead lab technical assistance at Oak Ridge Y-12 nationalsecurity complex: Evaluation of treatment and characterizationalternatives of mixed waste soil and debris at disposal area remedialaction DARA solids storage facility (SSF)

Energy Technology Data Exchange (ETDEWEB)

Hazen, Terry

2002-08-26

On July 17-18, 2002, a technical assistance team from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with the Bechtel Jacobs Company Disposal Area Remedial Action (DARA) environmental project leader to review treatment and characterization options for the baseline for the DARA Solids Storage Facility (SSF). The technical assistance request sought suggestions from SCFA's team of technical experts with experience and expertise in soil treatment and characterization to identify and evaluate (1) alternative treatment technologies for DARA soils and debris, and (2) options for analysis of organic constituents in soil with matrix interference. Based on the recommendations, the site may also require assistance in identifying and evaluating appropriate commercial vendors.

Fort Davis National Historic Site : acoustical monitoring

Science.gov (United States)

2013-06-01

During the summer of 2010 (September - October 2010), the Volpe Center collected baseline acoustical data at Fort Davis National Historic Site (FODA)at two sites deployed for approximately 30 days each. The baseline data collected during this period ...

Technical approach document

International Nuclear Information System (INIS)

1989-12-01

The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law 95-604 (PL95-604), grants the Secretary of Energy the authority and responsibility to perform such actions as are necessary to minimize radiation health hazards and other environmental hazards caused by inactive uranium mill sites. This Technical Approach Document (TAD) describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement remedial action plans (RAPS) and final designs that comply with EPA standards. It does not address the technical approaches necessary for aquifer restoration at processing sites; a guidance document, currently in preparation, will describe aquifer restoration concerns and technical protocols. This document is a second revision to the original document issued in May 1986; the revision has been made in response to changes to the groundwater standards of 40 CFR 192, Subparts A--C, proposed by EPA as draft standards. New sections were added to define the design approaches and designs necessary to comply with the groundwater standards. These new sections are in addition to changes made throughout the document to reflect current procedures, especially in cover design, water resources protection, and alternate site selection; only minor revisions were made to some of the sections. Sections 3.0 is a new section defining the approach taken in the design of disposal cells; Section 4.0 has been revised to include design of vegetated covers; Section 8.0 discusses design approaches necessary for compliance with the groundwater standards; and Section 9.0 is a new section dealing with nonradiological hazardous constituents. 203 refs., 18 figs., 26 tabs

Global Geodesy Using GPS Without Fiducial Sites

Science.gov (United States)

Heflin, Michael B.; Blewitt, Geoffrey

1994-01-01

Global Positioning System, GPS, used to make global geodetic measurements without use of fiducial site coordinates. Baseline lengths and geocentric radii for each site determined without having to fix any site coordinates. Given n globally distributed sites, n baseline lengths and n geocentric radii form polyhedron with each site at vertex and with geocenter at intersection of all radii. Geodetic information derived from structure of polyhedron and its change with time. Approach applied to any global geodetic technique.

SSC [Superconducting Super Collider] site evaluations

International Nuclear Information System (INIS)

1988-11-01

With this report, the SSC Site Task Force forwards to the Director, Office of Energy Research, US Department of Energy (DOE), its evaluation of the technical criteria and life-cycle costs for the proposed SSC sites judged to be the best qualified. The criteria against which each site was evaluated are those set forth in the Invitation for Site Proposals for the Superconducting Super Collider (DOE/ER-0315) (Invitation) which was prepared by the Task Force and issued in April 1987. The methodology followed by the Task Force in this report and in all other phases of the proposal evaluation has been consistent with the SSC site selection process approved by DOE's Energy System Acquisition Advisory Board (ESAAB). The goal of the site selection process is to identify a site that will permit the highest level of research productivity and overall effectiveness of the SSC at a reasonable cost of construction and operation and with minimial impact on the environment. The Task Force acknowledges that all seven sites are, indeed, highly qualified locations for the construction and operation of the SSC on the basis of technical and cost considerations. In performing its evaluation, which is presented in this paper, the Task Force took an in-depth look at each site on the basis of site visits and extensive technical analyses. A consensus rating for each technical evaluation criterion and subcriterion was developed for each site

Baseline risk assessment for the quarry residuals operable unit of the Weldon Spring Site, Weldon Spring, Missouri

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The U.S. Department of Energy (DOE) is conducting cleanup activities at the Weldon Spring site, located in St. Charles County, Missouri, about 48 km (30 mi) west of St. Louis. Cleanup of the site consists of several integrated components. The quarry residuals operable unit (QROU), consisting of the Weldon Spring quarry and its surrounding area, is one of four operable units being evaluated. In accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, DOE is conducting a remedial investigation/feasibility study (RI/FS) to determine the proper response to address various contaminated media that constitute the QROU. Specifically, the operable unit consists of the following areas and media: the residual material remaining at the Weldon Spring quarry after removal of the pond water and the bulk waste; groundwater underlying the quarry and surrounding area; and other media located in the surrounding vicinity of the quarry, including surface water and sediment at Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek. An initial evaluation of conditions at the quarry area identified remaining data requirements needed to support the conceptual site exposure and hydrogeological models. These data requirements are discussed in the RI/FS work plan issued in January 1994. Soil contamination located at a property adjacent to the quarry, referred to as Vicinity Property 9 (VP9), was originally part of the scope of the QROU, as discussed in the work plan. However, a decision was subsequently made to remediate this vicinity property as part of cleanup activities for the chemical plant operable unit, as provided for in the Record of Decision (ROD). Remediation of VP9 was completed in early 1996. Hence, this baseline risk assessment (BRA) does not address VP9.

Baseline risk assessment for the quarry residuals operable unit of the Weldon Spring Site, Weldon Spring, Missouri

International Nuclear Information System (INIS)

1998-02-01

The U.S. Department of Energy (DOE) is conducting cleanup activities at the Weldon Spring site, located in St. Charles County, Missouri, about 48 km (30 mi) west of St. Louis. Cleanup of the site consists of several integrated components. The quarry residuals operable unit (QROU), consisting of the Weldon Spring quarry and its surrounding area, is one of four operable units being evaluated. In accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, DOE is conducting a remedial investigation/feasibility study (RI/FS) to determine the proper response to address various contaminated media that constitute the QROU. Specifically, the operable unit consists of the following areas and media: the residual material remaining at the Weldon Spring quarry after removal of the pond water and the bulk waste; groundwater underlying the quarry and surrounding area; and other media located in the surrounding vicinity of the quarry, including surface water and sediment at Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek. An initial evaluation of conditions at the quarry area identified remaining data requirements needed to support the conceptual site exposure and hydrogeological models. These data requirements are discussed in the RI/FS work plan issued in January 1994. Soil contamination located at a property adjacent to the quarry, referred to as Vicinity Property 9 (VP9), was originally part of the scope of the QROU, as discussed in the work plan. However, a decision was subsequently made to remediate this vicinity property as part of cleanup activities for the chemical plant operable unit, as provided for in the Record of Decision (ROD). Remediation of VP9 was completed in early 1996. Hence, this baseline risk assessment (BRA) does not address VP9

10 CFR 960.4-2 - Technical guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Technical guidelines. 960.4-2 Section 960.4-2 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Postclosure Guidelines § 960.4-2 Technical guidelines. The technical guidelines in this subpart...

Experimental Setup for Evaluation of the Protective Technical Measures Against the Slopes Degradation Along Linear Construction Sites

Science.gov (United States)

Kavka, Petr; Zumr, David; Neumann, Martin; Lidmila, Martin; Dufka, Dušan

2017-04-01

Soil erosion of the slopes along the linear construction sites, such as railroads, roads, pipelines or watercourses, is usually underestimated by the construction companies and controlling authorities. But under certain circumstances, when the construction site is not maintained and protected properly, a large amounts of soil may be transported from the sites to the surrounding environment during the intensive rainfall. Transported sediment, often carrying adsorbed pollutants, may reach watercourses and cause water recipient siltation and pollution. Within the applied research project we investigate ways of low cost, quick and easy technical measures that would help to protect the slopes against the splash erosion, rills development and sliding. The methodology is based on testing of various permeable covers, sheets, anchoring and patchy vegetation on a plot and hillslope scales. In this contribution we will present the experimental plot setup, consisting of large soil blocks encapsulated in the monitored steel containers and nozzle rainfall simulator. The presentation is funded by the Technological Agency of the Czech Republic (research project TH02030428) and an internal student CTU grant.

Japanese site for ITER: Rokkasho

International Nuclear Information System (INIS)

Kishimoto, Hiroshi

2003-01-01

This paper describes the status of Japanese efforts for hosting ITER in Japan. In May 2002, Japanese Government decided to propose an ITER site, Rokkasho in Aomori Prefecture, a Northern part of the main island, based on the comprehensive/intensive assessments by the Site Selection Committee established by Japanese Government. ITER is designed basically with a potential flexibility beyond the detailed technical objectives to have more clear scope for developing technical key elements in a future power plant. Various flexibilities in the construction, operation and decommissioning of ITER are totally assessed. Consequently the Japanese site has been chosen and it satisfies sufficiently not only the Site Requirements and the Site Design Assumptions but also the further extension and flexibilities. In particular the potential for more flexible construction schedule and operations is technically described as well as the fulfillment of the site requirements and its assumptions as the minimum requirements in this paper. The socio-cultural environment is also described briefly because of a key aspect for the scientists and engineers who will participate in the project

10 CFR 960.5-2 - Technical guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Technical guidelines. 960.5-2 Section 960.5-2 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Preclosure Guidelines § 960.5-2 Technical guidelines. The technical guidelines in this subpart set...

Land contamination. Technical guidance on special sites: nuclear sites

International Nuclear Information System (INIS)

Hill, M.; Steeds, J.; Slade, N.

2001-01-01

Part IIA of the Environmental Protection Act 1990 sets out a regulatory regime for the identification and remediation of land where contamination is causing unacceptable risks to defined receptors. The Environment Agency has a number of regulatory roles under this regime. Where land is designated as a Special Site, as defined in the Contaminated Land (England) Regulations 2000, the Agency will act as the enforcing authority. It is expected that a similar regime will be introduced in Wales during 2001, but the reader should check whether definitions of Special Sites in the Welsh regulations are the same as in the English ones. The Environment Agency's approach to carrying out its regulatory responsibilities is set out in its Part RA Process Documentation,, available on the Agency website (www.environment-agency. gov.uk). This documentation sets out how the Agency intends to carry out its responsibilities under Part IIA of the Environmental Protection Act 1990, which came into force in England on 1 April 2000

Geochemical baseline studies of soil in Finland

Science.gov (United States)

Pihlaja, Jouni

2017-04-01

The soil element concentrations regionally vary a lot in Finland. Mostly this is caused by the different bedrock types, which are reflected in the soil qualities. Geological Survey of Finland (GTK) is carrying out geochemical baseline studies in Finland. In the previous phase, the research is focusing on urban areas and mine environments. The information can, for example, be used to determine the need for soil remediation, to assess environmental impacts or to measure the natural state of soil in industrial areas or mine districts. The field work is done by taking soil samples, typically at depth between 0-10 cm. Sampling sites are chosen to represent the most vulnerable areas when thinking of human impacts by possible toxic soil element contents: playgrounds, day-care centers, schools, parks and residential areas. In the mine districts the samples are taken from the areas locating outside the airborne dust effected areas. Element contents of the soil samples are then analyzed with ICP-AES and ICP-MS, Hg with CV-AAS. The results of the geochemical baseline studies are published in the Finnish national geochemical baseline database (TAPIR). The geochemical baseline map service is free for all users via internet browser. Through this map service it is possible to calculate regional soil baseline values using geochemical data stored in the map service database. Baseline data for 17 elements in total is provided in the map service and it can be viewed on the GTK's web pages (http://gtkdata.gtk.fi/Tapir/indexEN.html).

Technical concept for a test of geologic storage of spent reactor fuel in the climax granite, Nevada Test Site

International Nuclear Information System (INIS)

Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

1979-01-01

We plan to emplace spent fuel assemblies from an operating commercial nuclear reactor in the Climax granite at the US Department of Energy's Nevada Test Site. In this generic test, 11 canisters of spent fuel will be emplaced with 6 electrical simulator canisters in a storage drift 420 m below in surface and their effects compared. Two adjacent drifts will contain electrical heaters, operated to simulate the temperature-stress-displacement fields of a large repository. We describe the test objectives, the technical issues, the site, the preoperational measurement program, thermal and mechanical response calculations, the characteristics of the spent fuel, the field instrumentation and data-acquisition systems, and the system for handling the spent fuel

ITER technical advisory committee meeting at Garching

International Nuclear Information System (INIS)

Fujiwara, M.

1999-01-01

The ITER Technical Advisory Committee meeting took place on 24-27 February at the Garching Joint Work Site. According to the discussions at the ITER meeting in Yokohama in October 1998, the Technical Advisory Committee was requested to conduct a thorough review of the document 'Options for the reduced technical objectives / reduced cost ITER'

Inter-Site Consistency at a Multi-Site Psychiatry Clerkship

Science.gov (United States)

Shultes von Schlageter, Margo; Park, EunMi; Tucker, Phebe

2006-01-01

Objective: This study examines the effects of clinical site assignment within a multiple-site psychiatry clerkship program on the convergent outcome of the National Board of Medical Examiners (NBME) subject examination. Method: NBME scores, controlled for baseline pre-clerkship knowledge base as measured by second year human behavior scores, were…

40 CFR 74.20 - Data for baseline and alternative baseline.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Data for baseline and alternative baseline. 74.20 Section 74.20 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR... baseline and alternative baseline. (a) Acceptable data. (1) The designated representative of a combustion...

Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

International Nuclear Information System (INIS)

Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

1980-01-01

This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive

Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

Energy Technology Data Exchange (ETDEWEB)

Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

1980-05-23

This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

International Nuclear Information System (INIS)

Bouget, Y.H.

1994-01-01

The seminar discussed the objectives, organization and scope of work of the Central and Site Technical Service Department in support of operating NPP; transfer of capability to establish and maintain an efficient operation support; defined the responsibilities and interface between on site and Central Technical Staff

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C.; Ballou, L.B.; Revelli, M.A.; Ducharme, A.R.; Shephard, L.E.; Dudley, W.W.; Hoxie, D.T.; Herbst, R.J.; Patera, E.A.; Judd, B.R.; Docka, J.A.; Rickertsen, L.D.

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE's Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ''current information'' or ''available evidence.''

Computer aided site management. Site use management by digital mapping

International Nuclear Information System (INIS)

Chupin, J.C.

1990-01-01

The logistics program developed for assisting the Hague site management is presented. A digital site mapping representation and geographical data bases are used. The digital site map and its integration into a data base are described. The program can be applied to urban and rural land management aid. Technical administrative and economic evaluations of the program are summarized [fr

CERN Technical Training 2005: WBTechT offers online training

CERN Multimedia

Davide Vitè

2005-01-01

The 2005 CERN Web-Based Technical Training (WBTechT) portal is a computer-skills site offering multimedia learning. Visit http://www.course-source.net/sites/cern/ to self-register, consult the available programmes or request a course via EDH. A self-directed online course costs 50.- CHF for desktop applications (e.g. Microsoft Office Suite, Frontpage, Dreamweaver, Illustrator, Photoshop) and 90.- CHF for technical applications (e.g. Unix, Oracle, Java, JavaScript, C, C++) for three months' unlimited access. Visit the WBTechT portal or http://www.cern.ch/TechnicalTraining, and contact Technical.Training@cern.ch or your DTO to find out more information.

Tanks focus area site needs assessment FY 1997

International Nuclear Information System (INIS)

1997-04-01

The Tanks Focus Area's (TFA's) mission is to manage an integrated technology development program that results in the application of technology to safely and efficiently accomplish tank waste remediation across the U.S. Department of Energy (DOE) complex. The TFA uses a systematic process for developing its annual program that draws from the tanks technology development needs expressed by four DOE tank waste sites - Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). The process is iterative and involves six steps: (1) Site needs identification and documentation, (2) Site communication of priority needs, (3) Technical response development, (4) Review technical responses, (5) Develop program planning documents, and (6) Review planning documents. This document describes the outcomes of the first two steps: site needs identification and documentation, and site communication of priority needs. It also describes the initial phases of the third and fourth steps: technical response development and review technical responses. Each site's Site Technology Coordination Group (STCG) was responsible for developing and delivering priority tank waste needs. This was accomplished using a standardized needs template developed by the National STCG. The standard template helped improve the needs submission process this year. The TFA received the site needs during December 1996 and January 1997

Technical support non-SLB(GCDF)

International Nuclear Information System (INIS)

DePoorter, G.L.; Burton, B.W.

1982-01-01

The Los Alamos National Laboratory is providing technical support for the Greater Confinement Demonstration Facility (GCDF) at the Nevada Test Site. This technical support consists of computer modeling of the GCDF, design and emplacement of a Shallow Test Plot at NTS, and instrument testing at Los Alamos. Results to date on the computer modeling and the Shallow Test Plot are described

Technical and Economic Comparison MOB location versus Bergermeer Drilling Site. Justification of the Financial section in the Environmental Impact Report (MER)

International Nuclear Information System (INIS)

Dekker, W.; Azeem Khan, F.

2009-09-01

The Environmental Impact Report for the gas storage location Bergermeer has selected the MOB area (mobilization complex or storage site of the Dutch Ministry of Defense) in Bergen as the most environment-friendly alternative (MMA) for the well area. TAQA asked SGS to elaborate the technical and financial aspects of the MMA alternative and to compare them to the preferred alternative. [nl

Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

International Nuclear Information System (INIS)

1987-03-01

The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

Yucca Mountain Climate Technical Support Representative

International Nuclear Information System (INIS)

Sharpe, Saxon E

2007-01-01

The primary objective of Project Activity ORD-FY04-012, 'Yucca Mountain Climate Technical Support Representative', was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding

A publication database for optical long baseline interferometry

Science.gov (United States)

Malbet, Fabien; Mella, Guillaume; Lawson, Peter; Taillifet, Esther; Lafrasse, Sylvain

2010-07-01

Optical long baseline interferometry is a technique that has generated almost 850 refereed papers to date. The targets span a large variety of objects from planetary systems to extragalactic studies and all branches of stellar physics. We have created a database hosted by the JMMC and connected to the Optical Long Baseline Interferometry Newsletter (OLBIN) web site using MySQL and a collection of XML or PHP scripts in order to store and classify these publications. Each entry is defined by its ADS bibcode, includes basic ADS informations and metadata. The metadata are specified by tags sorted in categories: interferometric facilities, instrumentation, wavelength of operation, spectral resolution, type of measurement, target type, and paper category, for example. The whole OLBIN publication list has been processed and we present how the database is organized and can be accessed. We use this tool to generate statistical plots of interest for the community in optical long baseline interferometry.

Site study plan for exploratory shaft monitoring wells, Deaf Smith County Site, Texas: Preliminary Draft

International Nuclear Information System (INIS)

1988-01-01

As part of site characterization studies, two exploratory shafts will be constructed at the Deaf Smith County site, Texas. Twelve wells at five locations have been proposed to monitor potential impacts of shaft construction on water-bearing zones in the Ogallala Formation and the Dockum Group. In addition, tests have been proposed to determine the hydraulic properties of the water-bearing zones for use in design and construction of the shafts. Samples of the Blackwater Draw Formation, Ogallala Formation, and Dockum Group will be obtained during construction of these wells. Visual indentification, laboratory testing, and in situ testing will yield data necessary for Exploratory Shaft Facility design and construction. This activity provides the earliest data on the Blackwater Drew Formation, Ogallala Formation, and Dockum Group near the exploratory shaft locations. Drilling and hydrologic testing are scheduled prior to other subsurface activity at the Exploratory Shaft Facility to establish ground-water baseline conditions. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established Salt Repository Project procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 45 refs., 11 figs., 4 tabs

Site study plan for geochemical analytical requirements and methodologies: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This site study plan documents the analytical methodologies and procedures that will be used to analyze geochemically the rock and fluid samples collected during Site Characterization. Information relating to the quality aspects of these analyses is also provided, where available. Most of the proposed analytical procedures have been used previously on the program and are sufficiently sensitive to yield high-quality analyses. In a few cases improvements in analytical methodology (e.g., greater sensitivity, fewer interferences) are desired. Suggested improvements to these methodologies are discussed. In most cases these method-development activities have already been initiated. The primary source of rock and fluid samples for geochemical analysis during Site Characterization will be the drilling program, as described in various SRP Site Study Plans. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground water baseline conditions have been established. The Technical Field Services Contractor (TFSC) is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 28 refs., 9 figs., 14 tabs

Ecotaxonmic baseline evaluation of the plant species in a ...

African Journals Online (AJOL)

The survey of the flora composition of an ecosystem is important in several environmental baseline studies. An ecotaxonomic assessment was carried out in Ase-Ndoni proposed Rivgas Refinery project site in other to find out the plant species of medicinal and other economic values. The investigation was carried out to ...

ITER site selection studies in Spain

International Nuclear Information System (INIS)

Medrano, M.; Alejaldre, C.; Doncel, J.; Garcia, A.; Ibarra, A.; Jimenez, J.A.; Sanchez de Mora, M.A.; Alcala, F.; Diez, J.E.; Dominguez, M.; Albisu, F.

2003-01-01

The studies carried out to evaluate and select a candidate site for International Thermonuclear Experimental Reactor (ITER) construction in Spain are presented in this paper. The ITER design, completed in July 2001, considered a number of technical requirements that must be fulfilled by the selected site. Several assumptions concerning the ITER site were made in order to carry on the design before final site selection. In the studies undertaken for ITER site selection in Spain, the referred technical requirements and assumptions were applied across the whole of Spain and two areas were identified as being preferential. These areas are on the Mediterranean coast and are situated in the Catalan and Valencian regions. A comparative evaluation based on technical characteristics for the concrete plots, proposed within the preferential areas, has been done. The result of these studies was the selection of a site that was deemed to be the most competitive--Vandellos (Tarragona)--and it was proposed to the European Commission for detailed studies in order to be considered as a possible European site for ITER construction. Another key factor for hosting ITER in Spain, is the licensing process. The present status is summarised in this paper

A long baseline global stereo matching based upon short baseline estimation

Science.gov (United States)

Li, Jing; Zhao, Hong; Li, Zigang; Gu, Feifei; Zhao, Zixin; Ma, Yueyang; Fang, Meiqi

2018-05-01

In global stereo vision, balancing the matching efficiency and computing accuracy seems to be impossible because they contradict each other. In the case of a long baseline, this contradiction becomes more prominent. In order to solve this difficult problem, this paper proposes a novel idea to improve both the efficiency and accuracy in global stereo matching for a long baseline. In this way, the reference images located between the long baseline image pairs are firstly chosen to form the new image pairs with short baselines. The relationship between the disparities of pixels in the image pairs with different baselines is revealed by considering the quantized error so that the disparity search range under the long baseline can be reduced by guidance of the short baseline to gain matching efficiency. Then, the novel idea is integrated into the graph cuts (GCs) to form a multi-step GC algorithm based on the short baseline estimation, by which the disparity map under the long baseline can be calculated iteratively on the basis of the previous matching. Furthermore, the image information from the pixels that are non-occluded under the short baseline but are occluded for the long baseline can be employed to improve the matching accuracy. Although the time complexity of the proposed method depends on the locations of the chosen reference images, it is usually much lower for a long baseline stereo matching than when using the traditional GC algorithm. Finally, the validity of the proposed method is examined by experiments based on benchmark datasets. The results show that the proposed method is superior to the traditional GC method in terms of efficiency and accuracy, and thus it is suitable for long baseline stereo matching.

Progress report: baseline monitoring of indicator species (butterflies) at tallgrass prairie restorations

Science.gov (United States)

Allain, Larry; Vidrine, Malcolm

2014-01-01

This project provides baseline data of butterfly populations at two coastal prairie restoration sites in Louisiana, the Duralde Unit of Lacassine National Wildlife Refuge (hereafter, the Duralde site) and the Cajun Prairie Restoration Project in Eunice (hereafter, the Eunice site). In all, four distinct habitat types representing different planting methods were sampled. These data will be used to assess biodiversity and health of native grasslands and also provide a basis for adaptive management.

Baseline metal concentrations in Paramoera walkeri from East Antarctica

International Nuclear Information System (INIS)

Palmer, Anne S. . E-mail Anne.Palmer@utas.edu.au; Snape, Ian; Stark, Jonathan S.; Johnstone, Glenn J.; Townsend, Ashley T.

2006-01-01

Remediation of the Thala Valley waste disposal site near Casey Station, East Antarctica was conducted in the austral summer of 2003/2004. Biomonitoring of the adjacent marine environment was undertaken using the gammaridean amphipod Paramoera walkeri as a sentinel species [Stark, J.S., Johnstone, G.J., Palmer, A.S., Snape, I., Larner, B.L., Riddle, M.J., in press, doi:10.1016/j.marpolbul.2006.05.020. Monitoring the remediation of a near shore waste disposal site in Antarctica using the amphipod Paramoera walkeri and diffusive gradients in thin films (DGTs). Marine Pollution Bulletin and references therein]. Determination of uptake of metals and hypothesis testing for differences that could be attributed to contamination required the establishment of baseline metal concentrations in P. walkeri. Baseline metal concentrations from two reference locations in the Windmill Islands are presented here. P. walkeri was a found to be a sensitive bioaccumulating organism that recorded spatial and temporal variability at the reference sites. Measurement of metals in P. walkeri required the development of a simple digestion procedure that used concentrated nitric acid. For the first time, rare earth metals were determined with additional clean procedures required to measure ultra low concentrations using magnetic sector ICP-MS. Certified and in-house reference materials were employed to ensure method reliability

Emergency Response Capability Baseline Needs Assessment - Requirements Document

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2016-10-04

This document was prepared by John A. Sharry, LLNL Fire Marshal and LLNL Division Leader for Fire Protection and reviewed by LLNL Emergency Management Department Head James Colson. The document follows and expands upon the format and contents of the DOE Model Fire Protection Baseline Capabilities Assessment document contained on the DOE Fire Protection Web Site, but only addresses emergency response.

Baseline Caesium-137 and Plutonium-239+240 inventory assessment for Central Europe

Science.gov (United States)

Meusburger, Katrin; Borelli, Pasquale; Evrard, Olivier; Ketterer, Michael; Mabit, Lionel; van Oost, Kristof; Alewell, Christine; Panagos, Panos

2017-04-01

Artificial fallout radionuclides (FRNs) such as Caesium-137 and Plutonium-239+240 released as products of the thermonuclear weapons testing that took place from the mid-1950s to the early 1980s and from nuclear power plant accidents (e.g. Chernobyl) are useful tools to quantify soil redistribution. In combination with geostatistics, FRNs may have the potential to bridge the gap between small scale process oriented studies and modelling that simplifies processes and effects over large spatial scales. An essential requirement for the application of FRNs as soil erosion tracers is the establishment of the baseline fallout at undisturbed sites before its comparison to those inventories found at sites undergoing erosion/accumulation. For this purpose, undisturbed topsoil (0-20cm) samples collected in 2009 within the framework of the Land Use/Cover Area frame Survey (LUCAS) have been measured by gamma-spectrometry and ICP-MS to determine 137Cs (n=145) and 239+240Pu (n=108) activities. To restrict the analysis to undisturbed reference sites a geospatial database query selecting only sites having a slope angle <2 degree, outside riparian zones (to avoid depositional sites) and under permanent grassland cover (according to CORINE Land Cover and Landsat) was applied. This study reports preliminary results on the feasibility of establishing a 137Cs and 239+240Pu baseline inventory map for Central Europe. The 137Cs/239+240Pu activity ratios will further allow assessing the rate and the spatial variability of 137Cs Chernobyl fallout. The establishment of such baseline inventory map will provide a unique opportunity to assess soil redistribution for a comparable time-frame (1953-2009) following a harmonised methodological protocol across national boundaries.

Baseline conditions at Olkiluoto

International Nuclear Information System (INIS)

2003-09-01

The main purpose of this report is to establish a reference point - defined as the data collected up until the end of year 2002 - for the coming phases of the Finnish spent nuclear fuel disposal programme. The focus is: to define the current surface and underground conditions at the site, both as regards the properties for which a change is expected and for the properties which are of particular interest for long-term safety or environmental impact; to establish, as far as possible, the natural fluctuation of properties that are potentially affected by construction of the underground laboratory, the ONKALO, and to provide references to data on parameters or use in model development and testing and to use models to assist in understanding and interpreting the data. The emphasis of the baseline description is on bedrock characteristics that are relevant to the long-term safety of a spent fuel repository and, hence, to include the hydrogeological, hydrogeochemical, rock mechanical, tectonic and seismic conditions of the site. The construction of the ONKALO will also affect some conditions on the surface, and, therefore, a description of the main characteristics of the nature and the man-made constructions at Olkiluoto is also given. This report is primarily a road map to the available information on the prevailing conditions at the Olkiluoto site and a framework for understanding of data collected. Hence, it refers to numerous available background reports and other archived information produced over the past 20 years or more, and forms a recapitulation and revaluation of the characterisation data of the Olkiluoto site. (orig.)

Digital Accessible Knowledge and well-inventoried sites for birds in Mexico: baseline sites for measuring faunistic change.

Science.gov (United States)

Peterson, A Townsend; Navarro-Sigüenza, Adolfo G; Martínez-Meyer, Enrique

2016-01-01

Faunal change is a basic and fundamental element in ecology, biogeography, and conservation biology, yet vanishingly few detailed studies have documented such changes rigorously over decadal time scales. This study responds to that gap in knowledge, providing a detailed analysis of Digital Accessible Knowledge of the birds of Mexico, designed to marshal DAK to identify sites that were sampled and inventoried rigorously prior to the beginning of major global climate change (1980). We accumulated DAK records for Mexican birds from all relevant online biodiversity data portals. After extensive cleaning steps, we calculated completeness indices for each 0.05° pixel across the country; we also detected 'hotspots' of sampling, and calculated completeness indices for these broader areas as well. Sites were designated as well-sampled if they had completeness indices above 80% and >200 associated DAK records. We identified 100 individual pixels and 20 broader 'hotspots' of sampling that were demonstrably well-inventoried prior to 1980. These sites are catalogued and documented to promote and enable resurvey efforts that can document events of avifaunal change (and non-change) across the country on decadal time scales. Development of repeated surveys for many sites across Mexico, and particularly for sites for which historical surveys document their avifaunas prior to major climate change processes, would pay rich rewards in information about distributional dynamics of Mexican birds.

INDEPENDENT TECHNICAL REVIEW OF THE BUILDING 100 PLUME, FORMER DOE PINELLAS SITE (YOUNG - RAINEY STAR CENTER), LARGO, FLORIDA

Energy Technology Data Exchange (ETDEWEB)

Eddy-Dilek, C.; Rossabi, J.; Amidon, M.; Riha, B.; Kaback, D.

2010-07-30

Contaminated groundwater associated with Building 100 at the Young-Rainey Science, Technology, and Research Center, formerly the DOE Pinellas plant, is the primary remedial challenge that remains to be addressed at the site. Currently, Building 100 is an active industrial facility that is now owned and operated by the Pinellas county government. Groundwater samples collected from monitoring wells recently installed near the southern boundary of the site suggest that contaminated groundwater has migrated off the plant site. In response to the challenges presented by the Building 100 plume, the Office of Legacy Management (LM) requested assistance from the DOE Office of Groundwater and Soil Remediation (EM-32) to provide a review team to make technical recommendations so that they can efficiently and effectively address characterization and remediation of the plume. The review team was unanimous in the conclusion that a dynamic strategy that combines a phased implementation of direct push samplers, sensors, and tools can be used to better delineate the extent of contamination, control plume migration, and rapidly remediate the contaminated groundwater at the site. The initial efforts of the team focused on reviewing the site history and data, organizing the information into a conceptual model, identifying appropriate technologies, and recommending an integrated strategy. The current groundwater data from the site indicate a two-lobed plume extending to the east and south. To the east vinyl chloride is the primary contaminant of concern, to the south, vinyl chloride and cis1, 2-DCE are the primary contaminants. The limited data that are available suggest that reductive dechlorination of the TCE is already occurring but is not sufficient to prevent offsite migration of low concentrations of TCE daughter products. The team recommends that DOE pursue a strategy that builds on the natural cleansing capacity of the subsurface with reductive methods including biostimulation

International Linear Collider Technical Design Report (Volumes 1 through 4)

Energy Technology Data Exchange (ETDEWEB)

Harrison M.

2013-03-27

The design report consists of four volumes: Volume 1, Executive Summary; Volume 2, Physics; Volume 3, Accelerator (Part I, R and D in the Technical Design Phase, and Part II, Baseline Design); and Volume 4, Detectors.

Technical framework for groundwater restoration

International Nuclear Information System (INIS)

1991-04-01

This document provides the technical framework for groundwater restoration under Phase II of the Uranium Mill Tailings Remedial Action (UMTRA) Project. A preliminary management plan for Phase II has been set forth in a companion document titled ''Preplanning Guidance Document for Groundwater Restoration''. General principles of site characterization for groundwater restoration, restoration methods, and treatment are discussed in this document to provide an overview of standard technical approaches to groundwater restoration

Integrated Baseline System (IBS) Version 2.0: Models guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

The Integrated Baseline System (IBS) is an emergency management planning and analysis tool being developed under the direction of the US Army Nuclear and Chemical Agency. This Models Guide summarizes the IBS use of several computer models for predicting the results of emergency situations. These include models for predicting dispersion/doses of airborne contaminants, traffic evacuation, explosion effects, heat radiation from a fire, and siren sound transmission. The guide references additional technical documentation on the models when such documentation is available from other sources. The audience for this manual is chiefly emergency management planners and analysts, but also data managers and system managers.

ITER technical advisory committee meeting

International Nuclear Information System (INIS)

Fujiwara, M.

1999-01-01

The ITER Technical Advisory Committee (TAC) meeting took place on December 20-22, 1999 at the Naka Joint Work Site. The objective of this meeting was to review the document 'Technical Basis for ITER-FEAT Outline Design (ODR)' issued by the Director on December 10. It was also aimed at providing the ITER Meeting scheduled for January 19-20, 2000 in Tokyo with a technical assessment of ODR and recommendations for the optimization of the anticipated plasma performance and engineering design, based on the guidelines approved by the Council in June 1998 and recommendations of the last TAC meeting

Digital Accessible Knowledge and well-inventoried sites for birds in Mexico: baseline sites for measuring faunistic change

Directory of Open Access Journals (Sweden)

A. Townsend Peterson

2016-09-01

Full Text Available Background Faunal change is a basic and fundamental element in ecology, biogeography, and conservation biology, yet vanishingly few detailed studies have documented such changes rigorously over decadal time scales. This study responds to that gap in knowledge, providing a detailed analysis of Digital Accessible Knowledge of the birds of Mexico, designed to marshal DAK to identify sites that were sampled and inventoried rigorously prior to the beginning of major global climate change (1980. Methods We accumulated DAK records for Mexican birds from all relevant online biodiversity data portals. After extensive cleaning steps, we calculated completeness indices for each 0.05° pixel across the country; we also detected ‘hotspots’ of sampling, and calculated completeness indices for these broader areas as well. Sites were designated as well-sampled if they had completeness indices above 80% and >200 associated DAK records. Results We identified 100 individual pixels and 20 broader ‘hotspots’ of sampling that were demonstrably well-inventoried prior to 1980. These sites are catalogued and documented to promote and enable resurvey efforts that can document events of avifaunal change (and non-change across the country on decadal time scales. Conclusions Development of repeated surveys for many sites across Mexico, and particularly for sites for which historical surveys document their avifaunas prior to major climate change processes, would pay rich rewards in information about distributional dynamics of Mexican birds.

The effect of tracking network configuration on GPS baseline estimates for the CASA Uno experiment

Science.gov (United States)

Wolf, S. Kornreich; Dixon, T. H.; Freymueller, J. T.

1990-01-01

The effect of the tracking network on long (greater than 100 km) GPS baseline estimates was estimated using various subsets of the global tracking network initiated by the first Central and South America (CASA Uno) experiment. It was found that best results could be obtained with a global tacking network consisting of three U.S. stations, two sites in the southwestern Pacific, and two sites in Europe. In comparison with smaller subsets, this global network improved the baseline repeatability, the resolution of carrier phase cycle ambiguities, and formal errors of the orbit estimates.

Early site review report for the Sundesert site, San Diego Gas and Electric Company. Project No. 558

International Nuclear Information System (INIS)

1977-01-01

The purpose of the report is to present the Nuclear Regulatory Commission's evaluation of several of the matters relating to the suitability of the Sundesert site near Blythe, California, on which the San Diego Gas and Electric Company proposes to build the Sundesert Nuclear Plant, Units 1 and 2. The report summarizes the results of the technical evaluation of the suitability of the proposed Sundesert site for a nuclear plant and delineates the scope of the technical matters considered in evaluating the suitability of the site

Choice of baseline climate data impacts projected species' responses to climate change.

Science.gov (United States)

Baker, David J; Hartley, Andrew J; Butchart, Stuart H M; Willis, Stephen G

2016-07-01

Climate data created from historic climate observations are integral to most assessments of potential climate change impacts, and frequently comprise the baseline period used to infer species-climate relationships. They are often also central to downscaling coarse resolution climate simulations from General Circulation Models (GCMs) to project future climate scenarios at ecologically relevant spatial scales. Uncertainty in these baseline data can be large, particularly where weather observations are sparse and climate dynamics are complex (e.g. over mountainous or coastal regions). Yet, importantly, this uncertainty is almost universally overlooked when assessing potential responses of species to climate change. Here, we assessed the importance of historic baseline climate uncertainty for projections of species' responses to future climate change. We built species distribution models (SDMs) for 895 African bird species of conservation concern, using six different climate baselines. We projected these models to two future periods (2040-2069, 2070-2099), using downscaled climate projections, and calculated species turnover and changes in species-specific climate suitability. We found that the choice of baseline climate data constituted an important source of uncertainty in projections of both species turnover and species-specific climate suitability, often comparable with, or more important than, uncertainty arising from the choice of GCM. Importantly, the relative contribution of these factors to projection uncertainty varied spatially. Moreover, when projecting SDMs to sites of biodiversity importance (Important Bird and Biodiversity Areas), these uncertainties altered site-level impacts, which could affect conservation prioritization. Our results highlight that projections of species' responses to climate change are sensitive to uncertainty in the baseline climatology. We recommend that this should be considered routinely in such analyses. © 2016 John Wiley

Modeling of technical soil-erosion control measures and its impact on soil erosion off-site effects within urban areas

Science.gov (United States)

Dostal, Tomas; Devaty, Jan

2013-04-01

The paper presents results of surface runoff, soil erosion and sediment transport modeling using Erosion 3D software - physically based mathematical simulation model, event oriented, fully distributed. Various methods to simulate technical soil-erosion conservation measures were tested, using alternative digital elevation models of different precision and resolution. Ditches and baulks were simulated by three different approaches, (i) by change of the land-cover parameters to increase infiltration and decrease flow velocity, (ii) by change of the land-cover parameters to completely infiltrate the surface runoff and (iii) by adjusting the height of the digital elevation model by "burning in" the channels of the ditches. Results show advantages and disadvantages of each approach and conclude suitable methods for combinations of particular digital elevation model and purpose of the simulations. Further on a set of simulations was carried out to model situations before and after technical soil-erosion conservation measures application within a small catchment of 4 km2. These simulations were focused on quantitative and qualitative assessment of technical soil-erosion control measures impact on soil erosion off-site effects within urban areas located downstream of intensively used agricultural fields. The scenarios were built upon a raster digital elevation model with spatial resolution of 3 meters derived from LiDAR 5G vector point elevation data. Use of this high-resolution elevation model allowed simulating the technical soil-erosion control measures by direct terrain elevation adjustment. Also the structures within the settlements were emulated by direct change in the elevation of the terrain model. The buildings were lifted up to simulate complicated flow behavior of the surface runoff within urban areas, using approach of Arévalo (Arévalo, 2011) but focusing on the use of commonly available data without extensive detailed editing. Application of the technical

The WITCH Model. Structure, Baseline, Solutions.

Energy Technology Data Exchange (ETDEWEB)

Bosetti, V.; Massetti, E.; Tavoni, M.

2007-07-01

WITCH - World Induced Technical Change Hybrid - is a regionally disaggregated hard link hybrid global model with a neoclassical optimal growth structure (top down) and an energy input detail (bottom up). The model endogenously accounts for technological change, both through learning curves affecting prices of new vintages of capital and through R and D investments. The model features the main economic and environmental policies in each world region as the outcome of a dynamic game. WITCH belongs to the class of Integrated Assessment Models as it possesses a climate module that feeds climate changes back into the economy. In this paper we provide a thorough discussion of the model structure and baseline projections. We report detailed information on the evolution of energy demand, technology and CO2 emissions. Finally, we explicitly quantifiy the role of free riding in determining the emissions scenarios. (auth)

Ecological and radioecological studies of nuclear installation sites

International Nuclear Information System (INIS)

Caries, J. C.; Hugon, J.; Grauby, A.

1988-01-01

The site study method consists of a dynamic and estimated analysis and of following up the release impact on all natural or non natural media compartments that take a part in the protection of man and his environment. The stages of knowing a nuclear site include the site preliminary radioecological evaluation, diffusion parameters evaluation, the quantification of factors of radioelements transfer to man, the ecological baseline carrying out, the radioactive baseline establishment, the radioecological synthesis of the results, the site radioactive and ecological control. This method applys to selection and detailed study of site. 1 tab., 7 refs. (F.M.)

Declassification and restoration of nuclear sites; Declassement et restauration des sites nucleaires

Energy Technology Data Exchange (ETDEWEB)

Noynaert, L; Rahier, A; Deboodt, P; Massaut, V

1998-09-01

The report describes the legal and technical aspects of the declassification and restoration of nuclear sites. This involves a number of technical and administrative operations. Different declassification strategies are discussed. The evaluation of the risks and impact on the environment are discussed as well as research and development needs, costs and possible sources for funding.

Geodesy by radio interferometry - Determinations of baseline vector, earth rotation, and solid earth tide parameters with the Mark I very long baseline radio interferometery system

Science.gov (United States)

Ryan, J. W.; Clark, T. A.; Coates, R. J.; Ma, C.; Wildes, W. T.

1986-01-01

Thirty-seven very long baseline radio interferometry experiments performed between 1972 and 1978 are analyzed and estimates of baseline vectors between six sites, five in the continental United States and one in Europe are derived. No evidence of significant changes in baseline length is found. For example, with a statistical level of confidence of approximately 85 percent, upper bounds on such changes within the United States ranged from a low of 10 mm/yr for the 850 km baseline between Westford, Massachusetts, and Green Bank, West Virginia, to a high of 90 mm/yr for the nearly 4000 km baseline between Westford and Goldstone, California. Estimates for universal time and for the x component of the position of the earth's pole are obtained. For the last 15 experiments, the only ones employing wideband receivers, the root-mean-square differences between the derived values and the corresponding ones published by the Bureau International de l'Heure are 0.0012 s and 0.018 arc sec respectively. The average value obtained for the radial Love number for the solid earth is 0.62 + or - 0.02 (estimated standard error).

Long-baseline neutrino oscillation experiments

International Nuclear Information System (INIS)

Crane, D.; Goodman, M.

1994-01-01

There is no unambiguous definition for long baseline neutrino oscillation experiments. The term is generally used for accelerator neutrino oscillation experiments which are sensitive to Δm 2 2 , and for which the detector is not on the accelerator site. The Snowmass N2L working group met to discuss the issues facing such experiments. The Fermilab Program Advisory Committee adopted several recommendations concerning the Fermilab neutrino program at their Aspen meeting immediately prior to the Snowmass Workshop. This heightened the attention for the proposals to use Fermilab for a long-baseline neutrino experiment at the workshop. The plan for a neutrino oscillation program at Brookhaven was also thoroughly discussed. Opportunities at CERN were considered, particularly the use of detectors at the Gran Sasso laboratory. The idea to build a neutrino beam from KEK towards Superkamiokande was not discussed at the Snowmass meeting, but there has been considerable development of this idea since then. Brookhaven and KEK would use low energy neutrino beams, while FNAL and CERN would plan have medium energy beams. This report will summarize a few topics common to LBL proposals and attempt to give a snapshot of where things stand in this fast developing field

CASA Uno GPS orbit and baseline experiments

Science.gov (United States)

Schutz, B. E.; Ho, C. S.; Abusali, P. A. M.; Tapley, B. D.

1990-01-01

CASA Uno data from sites distributed in longitude from Australia to Europe have been used to determine orbits of the GPS satellites. The characteristics of the orbits determined from double difference phase have been evaluated through comparisons of two-week solutions with one-week solutions and by comparisons of predicted and estimated orbits. Evidence of unmodeled effects is demonstrated, particularly associated with the orbit planes that experience solar eclipse. The orbit accuracy has been assessed through the repeatability of unconstrained estimated baseline vectors ranging from 245 km to 5400 km. Both the baseline repeatability and the comparison with independent space geodetic methods give results at the level of 1-2 parts in 100,000,000. In addition, the Mojave/Owens Valley (245 km) and Kokee Park/Ft. Davis (5409 km) estimates agree with VLBI and SLR to better than 1 part in 100,000,000.

Tanks Focus Area site needs assessment FY 1998

International Nuclear Information System (INIS)

1998-03-01

This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by four major US Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). This document describes the TFA's process of collecting site needs, analyzing them, and creating technical responses to the sites. It also summarizes the information contained within the TFA needs database, portraying information provided by four major DOE sites with tank waste problems. The overall TFA program objective is to deliver a tank technology program that reduces the current cost, and the operational and safety risks of tank remediation. The TFA's continues to enjoy close, cooperative relationships with each site. During the past year, the TFA has fostered exchanges of technical information between sites. These exchanges have proven to be healthy for all concerned. The TFA recognizes that site technology needs often change, and the TFA must be prepared not only to amend its program in response, but to help the sites arrive at the best technical approach to solve revised site needs

Tanks Focus Area site needs assessment FY 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by four major US Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). This document describes the TFA`s process of collecting site needs, analyzing them, and creating technical responses to the sites. It also summarizes the information contained within the TFA needs database, portraying information provided by four major DOE sites with tank waste problems. The overall TFA program objective is to deliver a tank technology program that reduces the current cost, and the operational and safety risks of tank remediation. The TFA`s continues to enjoy close, cooperative relationships with each site. During the past year, the TFA has fostered exchanges of technical information between sites. These exchanges have proven to be healthy for all concerned. The TFA recognizes that site technology needs often change, and the TFA must be prepared not only to amend its program in response, but to help the sites arrive at the best technical approach to solve revised site needs.

Developing RESRAD-BASELINE for environmental baseline risk assessment

International Nuclear Information System (INIS)

Cheng, Jing-Jy.

1995-01-01

RESRAD-BASELINE is a computer code developed at Argonne developed at Argonne National Laboratory for the US Department of Energy (DOE) to perform both radiological and chemical risk assessments. The code implements the baseline risk assessment guidance of the US Environmental Protection Agency (EPA 1989). The computer code calculates (1) radiation doses and cancer risks from exposure to radioactive materials, and (2) hazard indexes and cancer risks from exposure to noncarcinogenic and carcinogenic chemicals, respectively. The user can enter measured or predicted environmental media concentrations from the graphic interface and can simulate different exposure scenarios by selecting the appropriate pathways and modifying the exposure parameters. The database used by PESRAD-BASELINE includes dose conversion factors and slope factors for radionuclides and toxicity information and properties for chemicals. The user can modify the database for use in the calculation. Sensitivity analysis can be performed while running the computer code to examine the influence of the input parameters. Use of RESRAD-BASELINE for risk analysis is easy, fast, and cost-saving. Furthermore, it ensures in consistency in methodology for both radiological and chemical risk analyses

How a submarine returns to periscope depth: analysing complex socio-technical systems using Cognitive Work Analysis.

Science.gov (United States)

Stanton, Neville A; Bessell, Kevin

2014-01-01

This paper presents the application of Cognitive Work Analysis to the description of the functions, situations, activities, decisions, strategies, and competencies of a Trafalgar class submarine when performing the function of returning to periscope depth. All five phases of Cognitive Work Analysis are presented, namely: Work Domain Analysis, Control Task Analysis, Strategies Analysis, Social Organisation and Cooperation Analysis, and Worker Competencies Analysis. Complex socio-technical systems are difficult to analyse but Cognitive Work Analysis offers an integrated way of analysing complex systems with the core of functional means-ends analysis underlying all of the other representations. The joined-up analysis offers a coherent framework for understanding how socio-technical systems work. Data were collected through observation and interviews at different sites across the UK. The resultant representations present a statement of how the work domain and current activities are configured in this complex socio-technical system. This is intended to provide a baseline, from which all future conceptions of the domain may be compared. The strength of the analysis is in the multiple representations from which the constraints acting on the work may be analysed. Future research needs to challenge the assumptions behind these constraints in order to develop new ways of working. Copyright © 2013 Elsevier Ltd and The Ergonomics Society. All rights reserved.

Baseline characteristics of study sites and women enrolled in a three-arm cluster randomized controlled trial: PMTCT uptake and retention (pure) Malawi.

Science.gov (United States)

van Lettow, Monique; Tweya, Hannock; Rosenberg, Nora E; Trapence, Clement; Kayoyo, Virginia; Kasende, Florence; Kaunda, Blessings; Hosseinipour, Mina C; Eliya, Michael; Cataldo, Fabian; Gugsa, Salem; Phiri, Sam

2017-07-11

Malawi introduced an ambitious public health program known as "Option B+" which provides all HIV-infected pregnant and breastfeeding women with lifelong combination antiretroviral therapy, regardless of WHO clinical stage or CD4 cell count. The PMTCT Uptake and REtention (PURE) study aimed at evaluating the effect of peer-support on care-seeking and retention in care. PURE Malawi was a three-arm cluster randomized controlled trial that compared facility-based and community-based models of peer support to standard of care under Option B+ strategy. Each arm was expected to enroll a minimum of 360 women with a total minimum sample size of 1080 participants. 21 sites (clusters) were selected for inclusion in the study. This paper describes the site selection, recruitment, enrollment process and baseline characteristics of study sites and women enrolled in the trial. Study implementation was managed by 3 partner organizations; each responsible for 7 study sites. The trial was conducted in the South East, South West, and Central West zones of Malawi, the zones where the implementing partners operate. Study sites included 2 district hospitals, 2 mission hospitals, 2 rural hospitals, 13 health centers and 1 private clinic. Enrollment occurred from November 2013 to November 2014, over a median period of 31 weeks (range 17-51) by site. A total of 1269 HIV-infected pregnant (1094) and breastfeeding (175) women, who were eligible to initiate ART under Option B+, were enrolled. Each site reached or surpassed the minimum sample size. Comparing the number of women enrolled versus antenatal cohort reports, sites recruited a median of 90% (IQR 75-100) of eligible reported women. In the majority of sites the ratio of pregnant and lactating women enrolled in the study was similar to the ratio of reported pregnant and lactating women starting ART in the same sites. The median age of all women was 27 (IQR 22-31) years. All women have ≥20 months of possible follow-up time; 96%�

INDEPENDENT REVIEW OF THE X-701B GROUNDWATER REMEDY, PORTSMOUTH, OHIO: TECHNICAL EVALUATION AND RECOMMENDATIONS

Energy Technology Data Exchange (ETDEWEB)

Looney, B.; Eddy-Dilek, C.; Costanza, J.; Rossabi, J.; Early, T.; Skubal, K.; Magnuson, C.

2008-12-15

reviewed baseline data and reports, were provided additional technical information from site personnel, evaluated work plans, determined critical issues and uncertainties, and recommended alternatives. This report documents the findings and recommendations of the independent technical review team.

Technical approach to groundwater restoration

International Nuclear Information System (INIS)

1993-01-01

The Technical Approach to Groundwater Restoration (TAGR) provides general technical guidance to implement the groundwater restoration phase of the Uranium Mill Tailings Remedial Action (UMTRA) Project. The TAGR includes a brief overview of the surface remediation and groundwater restoration phases of the UMTRA Project and describes the regulatory requirements, the National Environmental Policy Act (NEPA) process, and regulatory compliance. A section on program strategy discusses program optimization, the role of risk assessment, the observational approach, strategies for meeting groundwater cleanup standards, and remedial action decision-making. A section on data requirements for groundwater restoration evaluates the data quality objectives (DQO) and minimum data required to implement the options and comply with the standards. A section on sits implementation explores the development of a conceptual site model, approaches to site characterization, development of remedial action alternatives, selection of the groundwater restoration method, and remedial design and implementation in the context of site-specific documentation in the site observational work plan (SOWP) and the remedial action plan (RAP). Finally, the TAGR elaborates on groundwater monitoring necessary to evaluate compliance with the groundwater cleanup standards and protection of human health and the environment, and outlines licensing procedures

Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

International Nuclear Information System (INIS)

Christensen, E.J.; Gordon, D.E.

1983-12-01

The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

A technical approach to groundwater contamination problems

International Nuclear Information System (INIS)

Burton, J.C.; Leser, C.; Rose, C.M.

1993-01-01

Argonne National Laboratory has been performing technical investigations at sites in Nebraska and Kansas that have identified groundwater contamination by carbon tetrachloride. This comprehensive program will ultimately provide the affected communities with safe drinking water. The first step in the program is to evaluate the available data and identify sites that will require an Alternate Water Supply Study (AWSS). The objective of the AWSS is to identify options for providing a safe drinking water supply to all users, in compliance with the Safe Drinking Water Act. The AWSS consists of an engineering and cost evaluation followed by implementation of the selected alternative. For sites with contamination less than a specific concentration, the AWSS is regarded as a satisfactory long term solution, and no further action is taken. For those sites with concentrations above that specific limit, the AWSS implementation is regarded as only a stopgap measure, and the site is selected for additional remedial action. The first step of the remedial action is an Expedited Site Characterization (ESC). The ESC was developed at Argonne to decrease the cost and time of the remedial investigation and feasibility study while producing a high-quality technical investigation. The ESC is designed to characterize the contaminant plume configuration and movement, which requires an understanding of the geological and hydrogeologic controls on groundwater movement as well as the nature and extent of any remaining carbon tetrachloride source in the soils. The ESC program uses a multidisciplinary technical approach that incorporates geology, geochemistry, geohydrology, and geophysics. Field activities include sampling, chemical analysis, and borehole and surface geophysical surveys

Siting guidelines and their role in repository site selection

International Nuclear Information System (INIS)

Hanlon, C.L.

1985-01-01

The first requirement of the Nuclear Waste Policy Act was for the Secretary of Energy to issue general guidelines for siting repositories. The guidelines were to specify detailed geologic considerations that would be the primary criteria for the selection of sites in various host rocks, as well as factors that would qualify or disqualify any site from development as a repository. These guidelines were clearly intended to provide not only the framework for the siting program but also the stimulus for establishing effective communication and consultation among the parties involved in the program. The Act further required that the guidelines be a factor in the development of all future decision documents of the Office of Civilian Radioactive Waste Management, including the environmental assessments that would accompany the nomination of sites for characterization, the site-characterization plans that are to be prepared before the sinking of exploratory shafts at any candidate site, and the environmental impact statement that is to support the recommendation of a site for development as a repository. More than two years after its passage, the intention of the Act for the guidelines has been realized. Concurred in by the Nuclear Regulatory Commission on June 22, 1984, and issued by the Department in November 1984, the guidelines include postclosure technical guidelines that apply to conditions governing the long-term performance of the repository system; preclosure technical guidelines that apply to conditions governing the siting, construction, operation, and closure of the repository; and system guidelines whose objective is to ensure that the regulatory requirements of the Environmental Protection Agency and the Nuclear Regulatory Commission are met

TWRS Privatization Phase 1 Master Site Plan

International Nuclear Information System (INIS)

PARAZIN, R.J.

1999-01-01

The U.S. Department of Energy (DOE) has chosen to accomplish the Tank Waste Remediation System disposal mission via privatization. The disposal mission has been divided into two privatization phases. Phase I, a 'proof of concept' phase, will establish and demonstrate the technical, commercial, and procurement capabilities necessary far privatization to proceed. Once established, privatization will be expanded in the form of a second phase (Phase II) to dispose of the remainder of the tank waste. In conjunction with preparation of the Tank Waste Remediation System (TWRS) Privatization Request for Proposals (RFP)(RL, 1996), a location was selected for the Phase I demonstration facilities (Shord, 1996). The location selected was the area previously developed and characterized for the Grout Disposal Site, adjoining the 200 East Area. The site is of sufficient size for a Private Contractor (PC) to carry out pretreatment, immobilization, and vitrification operations and possesses the required characteristics (e.g., close to feed tanks) to best facilitate the Phase I operations. This overall long-range Master Site Plan (MSP) has been developed to establish a ''baseline'' for the (TWRS) Privatization Phase I (TPPI) PC Site. The MSP depicts the planned layout for the PC Site along with various interfaces between the site and other Hanford utilities and functions. The complete integration of TPPl MSP with overall Hanford Site planning process will assist in establishing the PC site and the necessary priorities to meet the Hanford cleanup mission. The MSP has been developed systematically into a comprehensive, safe, flexible, logical and cost-effective plan. The general philosophy behind the preparation of a MSP for the TPPl program is that it will serve as a single source documentation of the planning for the development of the TPPl complex. The effort will plan temporary and permanent land use, utilities, and traffic flow for the overall program. It will identify needs

40 CFR 35.4005 - What is a Technical Assistance Grant?

Science.gov (United States)

2010-07-01

... public participation in decision making at eligible sites. A TAG allows your group to procure independent... Technical Assistance Grant? A Technical Assistance Grant (TAG) provides money for your group to obtain... how a technical advisor can help your group include, but are not limited to: (a) Reviewing preliminary...

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado: Final report

International Nuclear Information System (INIS)

1990-02-01

This radiologic characterization of tho two inactive uranium millsites at Rifle, Colorado, was conducted by Bendix Field Engineering Corporation (Bendix) for the US Department of Energy (DOE), Grand Junction Projects Office, in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor, Jacobs Engineering Group, Inc. (Jacobs). The purpose of this project is to define the extent of radioactive contamination at the Rifle sites that exceeds US Environmental Protection Agency, (EPA) standards for UMTRA sites. The data presented in this report are required for characterization of the areas adjacent to the tailings piles and for the subsequent design of cleanup activities. An orientation visit to the study area was conducted on 31 July--1 August 1984, in conjunction with Jacobs, to determine the approximate extent of contaminated area surrounding tho piles. During that visit, survey control points were located and baselines were defined from which survey grids would later be established; drilling requirements were assessed; and radiologic and geochemical data were collected for use in planning the radiologic fieldwork. The information gained from this visit was used by Jacobs, with cooperation by Bendix, to determine the scope of work required for the radiologic characterization of the Rifle sites. Fieldwork at Rifle was conducted from 1 October through 16 November 1984

Regional and hemispheric influences on temporal variability in baseline carbon monoxide and ozone over the Northeast US

Science.gov (United States)

Interannual variability in baseline carbon monoxide (CO) and ozone (O3), defined as mixing ratios under minimal influence of recent and local emissions, was studied for seven rural sites in the Northeast US over 2001–2010. Annual baseline CO exhibited statistically signific...

Baseline environmental survey of proposed uranium mining projects of Domiasiat, Meghalaya

International Nuclear Information System (INIS)

Khathing, D.T.; Myrboh, B.; Nongkynrih, P.; War, S.A.; Marbaniang, D.G.; Iongwai, P.S.

2005-01-01

West Khasi Hills District of Meghalaya is identified as having a large and rich deposits of Uranium. However, actual extraction on a commercial scale that may lead to an increase in the socio-economic development of the state in particular and the country in general, is yet to be undertaken. This is due to lack of any baseline environmental survey giving rise to speculative information and causing a fear psychosis in the minds of the locals populace about the negative effects of Uranium mining. A preoperational survey and environmental monitoring of the proposed mining sites and its adjacent areas would establish the baseline status of the natural radioactivity and some chemical constituents in different environmental matrices via. air, water, soil, biota and aquatic ecosystems. The North Eastern Hill University, Shillong, Meghalaya has undertaken the Project funded by DST and BRNS, Department of Atomic Energy, Govt. of India which aims to provide baseline environmental data on ambient air, water and soil quality in and around the proposed Uranium mining site of Domiasiat, West Khasi Hills in the state of Meghalaya. Trace elements (elements like Mg, Zn, Ca, K, Na, Se, As, Fe, Cu, Co, Cr, Ni, Pb, Cd, Mn etc) and the status of the activity in the samples are determined. (author)

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-10-20

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

International Nuclear Information System (INIS)

Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

1995-01-01

The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

K-Basins Sludge Treatment and Packaging at the Hanford Site - 13585

International Nuclear Information System (INIS)

Fogwell, Thomas W.; Honeyman, James O.; Stegen, Gary

2013-01-01

applicable technologies were identified through a commercial procurement process, technical workshops, and review of the numerous previous sludge treatment technology studies. The identified technology approaches were screened using the criteria established in the Decision Plan, and focused bench top feasibility testing was conducted. Engineering evaluations of the costs, schedules, and technical maturity were developed and evaluated. Recommendations were developed based on technical evaluations. The criteria used in the evaluation process were as follows: (1) Safety, (2) Regulatory/stakeholder acceptance, (3) Technical maturity, (4) Operability and maintainability, (5) Life cycle cost and schedule, (6) Potential for beneficial integration with ongoing STP-Phase 1 activities, and (7) Integration with Site-wide RH-TRU processing/packaging, planning, schedule, and approach. The TEAA recommended Warm Water Oxidation (WWO) as the baseline treatment technology and two risk reduction enhancement options for further consideration during development of the process - size reduction and chemical oxidation (Fenton's reagent). The enhancement options would potentially allow a useful reduction in the total operating time required to process the K Basins sludge. The U.S. Department of Energy's Richland Field Office (DOE-RL) has approved this recommended technical approach. The baseline process can be broken down into the following main process steps: (1) STSC transfer from T Plant to the Sludge Treatment and Packaging Facility (STPF). (2) Retrieval of sludge from the STSCs and transfer to the Receipt and Reaction Tank (RRT). (3) Preparation for immobilization by oxidation using heated water (i.e., WWO) for those batches that require it and concentration by evaporating water at about atmospheric pressure in the RRT. (4) Immobilization by using additives to eliminate free liquids and packaging of the treated sludge into drums. (5) Inspection and handling of the filled drums prior to

K-Basins Sludge Treatment and Packaging at the Hanford Site - 13585

Energy Technology Data Exchange (ETDEWEB)

Fogwell, Thomas W. [Fogwell Consulting, P.O. Box 20211, Piedmont, CA 94620 (United States); Honeyman, James O. [CH2M HILL Plateau Remediation Company, P.O. Box 1600 H7-30, Richland, WA (United States); Stegen, Gary [Lucas Engineering and Management Services, Inc., 1201 Jadwin Avenue, Suite 102, Richland, WA 99352 (United States)

2013-07-01

applicable technologies were identified through a commercial procurement process, technical workshops, and review of the numerous previous sludge treatment technology studies. The identified technology approaches were screened using the criteria established in the Decision Plan, and focused bench top feasibility testing was conducted. Engineering evaluations of the costs, schedules, and technical maturity were developed and evaluated. Recommendations were developed based on technical evaluations. The criteria used in the evaluation process were as follows: (1) Safety, (2) Regulatory/stakeholder acceptance, (3) Technical maturity, (4) Operability and maintainability, (5) Life cycle cost and schedule, (6) Potential for beneficial integration with ongoing STP-Phase 1 activities, and (7) Integration with Site-wide RH-TRU processing/packaging, planning, schedule, and approach. The TEAA recommended Warm Water Oxidation (WWO) as the baseline treatment technology and two risk reduction enhancement options for further consideration during development of the process - size reduction and chemical oxidation (Fenton's reagent). The enhancement options would potentially allow a useful reduction in the total operating time required to process the K Basins sludge. The U.S. Department of Energy's Richland Field Office (DOE-RL) has approved this recommended technical approach. The baseline process can be broken down into the following main process steps: (1) STSC transfer from T Plant to the Sludge Treatment and Packaging Facility (STPF). (2) Retrieval of sludge from the STSCs and transfer to the Receipt and Reaction Tank (RRT). (3) Preparation for immobilization by oxidation using heated water (i.e., WWO) for those batches that require it and concentration by evaporating water at about atmospheric pressure in the RRT. (4) Immobilization by using additives to eliminate free liquids and packaging of the treated sludge into drums. (5) Inspection and handling of the filled drums prior

Technical management of difference in CEPR nuclear power project

International Nuclear Information System (INIS)

Guo Ruiting

2014-01-01

The Thesis dissertate the application of technical management of difference in CEPR Nuclear Power Project from EPR technical bases, condition of a nuclear power plant site, engineering and procurement, construction, quality management, schedule management and experience feedback aspects. (author)

[Modular risk analysis for assessing multiple waste sites]: Proceedings

International Nuclear Information System (INIS)

Whelan, G.

1994-01-01

This document contains proceedings from the Integrated Planning Workshop from Strategic Planning to Baselining and Other Objectives. Topics discussed include: stakeholder involvement; regulations; future site use planning; site integration and baseline methods; risk analysis in decision making; land uses; and economics in decision making. Individual records have been processed separately for the database

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

Energy Technology Data Exchange (ETDEWEB)

John Collins

2009-01-01

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

International Nuclear Information System (INIS)

Groom, S.H.

1994-01-01

The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

The Female Athlete Body (FAB) study: Rationale, design, and baseline characteristics.

Science.gov (United States)

Stewart, Tiffany M; Pollard, Tarryn; Hildebrandt, Tom; Beyl, Robbie; Wesley, Nicole; Kilpela, Lisa Smith; Becker, Carolyn Black

2017-09-01

Eating Disorders (EDs) are serious psychiatric illnesses marked by psychiatric comorbidity, medical complications, and functional impairment. Research indicates that female athletes are often at greater risk for developing ED pathology versus non-athlete females. The Female Athlete Body (FAB) study is a three-site, randomized controlled trial (RCT) designed to assess the efficacy of a behavioral ED prevention program for female collegiate athletes when implemented by community providers. This paper describes the design, intervention, and participant baseline characteristics. Future papers will discuss outcomes. Female collegiate athletes (N=481) aged 17-21 were randomized by site, team, and sport type to either FAB or a waitlist control group. FAB consisted of three sessions (1.3h each) of a behavioral ED prevention program. Assessments were conducted at baseline (pre-intervention), post-intervention (3weeks), and six-, 12-, and 18-month follow-ups. This study achieved 96% (N=481) of target recruitment (N=500). Few group differences emerged at baseline. Total sample analyses revealed moderately low baseline instances of ED symptoms and clinical cases. Health risks associated with EDs necessitate interventions for female athletes. The FAB study is the largest existing RCT for female athletes aimed at both reduction of ED risk factors and ED prevention. The methods presented and population recruited for this study represent an ideal intervention for assessing the effects of FAB on both the aforementioned outcomes. We anticipate that findings of this study (reported in future papers) will make a significant contribution to the ED risk factor reduction and prevention literature. Copyright © 2017 Elsevier Inc. All rights reserved.

Remediation management of complex sites using an adaptive site management approach.

Science.gov (United States)

Price, John; Spreng, Carl; Hawley, Elisabeth L; Deeb, Rula

2017-12-15

Complex sites require a disproportionate amount of resources for environmental remediation and long timeframes to achieve remediation objectives, due to their complex geologic conditions, hydrogeologic conditions, geochemical conditions, contaminant-related conditions, large scale of contamination, and/or non-technical challenges. A recent team of state and federal environmental regulators, federal agency representatives, industry experts, community stakeholders, and academia worked together as an Interstate Technology & Regulatory Council (ITRC) team to compile resources and create new guidance on the remediation management of complex sites. This article summarizes the ITRC team's recommended process for addressing complex sites through an adaptive site management approach. The team provided guidance for site managers and other stakeholders to evaluate site complexities and determine site remediation potential, i.e., whether an adaptive site management approach is warranted. Adaptive site management was described as a comprehensive, flexible approach to iteratively evaluate and adjust the remedial strategy in response to remedy performance. Key aspects of adaptive site management were described, including tools for revising and updating the conceptual site model (CSM), the importance of setting interim objectives to define short-term milestones on the journey to achieving site objectives, establishing a performance model and metrics to evaluate progress towards meeting interim objectives, and comparing actual with predicted progress during scheduled periodic evaluations, and establishing decision criteria for when and how to adapt/modify/revise the remedial strategy in response to remedy performance. Key findings will be published in an ITRC Technical and Regulatory guidance document in 2017 and free training webinars will be conducted. More information is available at www.itrc-web.org. Copyright © 2017 Elsevier Ltd. All rights reserved.

Transient Inverse Calibration of Site-Wide Groundwater Model to Hanford Operational Impacts from 1943 to 1996-Alternative Conceptual Model Considering Interaction with Uppermost Basalt Confined Aquifer; FINAL

International Nuclear Information System (INIS)

Vermeul, Vince R; Cole, Charles R; Bergeron, Marcel P; Thorne, Paul D; Wurstner, Signe K

2001-01-01

The baseline three-dimensional transient inverse model for the estimation of site-wide scale flow parameters, including their uncertainties, using data on the transient behavior of the unconfined aquifer system over the entire historical period of Hanford operations, has been modified to account for the effects of basalt intercommunication between the Hanford unconfined aquifer and the underlying upper basalt confined aquifer. Both the baseline and alternative conceptual models (ACM-1) considered only the groundwater flow component and corresponding observational data in the 3-Dl transient inverse calibration efforts. Subsequent efforts will examine both groundwater flow and transport. Comparisons of goodness of fit measures and parameter estimation results for the ACM-1 transient inverse calibrated model with those from previous site-wide groundwater modeling efforts illustrate that the new 3-D transient inverse model approach will strengthen the technical defensibility of the final model(s) and provide the ability to incorporate uncertainty in predictions related to both conceptual model and parameter uncertainty

Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-01-01

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.

Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The work developed baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys employed diving,...

Consideration of the baseline environment in examples of voluntary SEAs from Scotland

International Nuclear Information System (INIS)

Wright, Fiona

2007-01-01

Evidence from analysing and evaluating examples of three voluntary SEAs prepared in Scotland in the mid-late 1990s showed that different spatial and temporal scales were used when providing a baseline environment description. The SEAs analysed were prepared for: a wind farm siting programme that looked at national and short-term impacts; a land use plan that looked at regional and short-term impacts; and a transport plan that examined local and medium-term impacts. It was found that the two SEAs prepared by local government only considered impacts on the baseline environment within their jurisdictional boundaries whilst the SEA prepared by the private business considered impacts on the national baseline. A mixture of baseline data about planning, economic, environmental and social issues were included in the SEAs, however, evidence suggested that each SEA only focussed on those baseline features that might be significantly affected by the proposal. Each SEA also made extensive use of existing baseline information available from a variety of sources including local, and central government records and information from statutory bodies. All of the SEAs acknowledged that baseline data deficiencies existed and in certain cases steps were taken to obtain primary field data to help address these, however, it was also acknowledged that resource restrictions and decision-making deadlines limited the amount of primary baseline data that could be collected

Baseline assessment of benthic communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

Baseline assessment of fish communities of the Flower Garden Banks (2010 - 2013) using technical diving operations: 2011

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The proposed work develop baseline information on fish and benthic communities within the Flower Garden Banks National Marine Sanctuary (FGBNMS). Surveys will employ...

The ecosystem baseline for particle flux in the Northern Gulf of Mexico

Directory of Open Access Journals (Sweden)

S.L.C. Giering

2018-01-01

Full Text Available Response management and damage assessment during and after environmental disasters such as the Deepwater Horizon (DWH oil spill require an ecological baseline and a solid understanding of the main drivers of the ecosystem. During the DWH event, a large fraction of the spilled oil was transported to depth via sinking marine snow, a routing of spilled oil unexpected to emergency response planners. Because baseline knowledge of particle export in the Northern Gulf of Mexico and how it varies spatially and temporally was limited, we conducted a detailed assessment of the potential drivers of deep (~1400 m depth particle fluxes during 2012–2016 using sediment traps at three contrasting sites in the Northern Gulf of Mexico: near the DWH site, at an active natural oil seep site, and at a site considered typical for background conditions. The DWH site, located ~70 km from the Mississippi River Delta, showed flux patterns that were strongly linked to the Mississippi nitrogen discharge and an annual subsequent surface bloom. Fluxes carried clear signals of combustion products, which likely originated from pyrogenic sources that were transported offshore via the Mississippi plume. The seep and reference sites were more strongly influenced by the open Gulf of Mexico, did not show a clear seasonal flux pattern, and their overall sedimentation rates were lower than those at the DWH site. At the seep site, based on polycyclic aromatic hydrocarbon data, we observed indications of three different pathways for “natural” oiled-snow sedimentation: scavenging by sinking particles at depth, weathering at the surface before incorporation into sinking particles, and entry into the food web and subsequent sinking in form of detritus. Overall, sedimentation rates at the three sites were markedly different in quality and quantity owing to varying degrees of riverine and oceanic influences, including natural seepage and contamination by combustion products.

Development of emergency response training focusing on non-technical skills. (2) Extraction of non-technical skills

International Nuclear Information System (INIS)

Matsui, Yuko; Hikono, Masaru; Iwasaki, Mari; Morita, Mizuho

2017-01-01

This study aimed at characterizing a non-technical skill exercise for on-site managers in charge of initial response at an emergency response center by extracting and clarifying the behavior examples of non-technical skills shown in the exercise scenario. From video observations, the non-technical skill examples were identified from seven of the eight nontechnical skill categories which had been defined when the training program was developed. Especially, they included many skills of 'Communication', 'Situation Understanding' and 'Organizational management'. At the same time, the limitation when extracting the cases by observations was identified. The extracted non-technical skill cases are expected to be used for characterizing exercise scenarios, as well as provide knowledge to raise the awareness of exercise participants. (author)

Hanford Site Composite Analysis Technical Approach Description: Radionuclide Inventory and Waste Site Selection Process.

Energy Technology Data Exchange (ETDEWEB)

Nichols, Will E.; Mehta, Sunil

2017-09-13

The updated Hanford Site Composite Analysis will provide an all-pathways dose projection to a hypothetical future member of the public from all planned low-level radioactive waste disposal facilities and potential contributions from all other projected end-state sources of radioactive material left at Hanford following site closure. Its primary purpose is to support the decision-making process of the U.S. Department of Energy (DOE) under DOE O 435.1-1, Radioactive Waste Management (DOE, 2001), related to managing low-level waste disposal facilities at the Hanford Site.

Internal dosimetry technical basis manual

International Nuclear Information System (INIS)

1990-01-01

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs

Internal dosimetry technical basis manual

Energy Technology Data Exchange (ETDEWEB)

1990-12-20

The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

Disposal of spent fuel in Olkiluoto bedrock. Programme for research, development and technical design for the pre-construction phase

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

assessment will be the cornerstone of the long-term safety case, but the argumentation for safety will also be based on broader technical and scientific evidence. A substantial part of the programme activities will be staged according to the progress of the planned underground rock characterisation facility, ONKALO, at Olkiluoto. The plan is to start the construction of ONKALO in 2003-2004. Before that Posiva will complete the documentation concerning the: baseline description of the Olkiluoto site; technical design description of the planned underground rock characterisation facility; plan for underground investigations and review of the rock characteristics that are important for the long-term safety of disposal together with an assessment of how the ONKALO project would affect these. Later, at the end of 2005, Posiva will publish an interim progress report of the disposal programme. The report will also contain a more detailed description of the activities planned for the latter half of the programme period. (orig.)

Disposal of spent fuel in Olkiluoto bedrock. Programme for research, development and technical design for the pre-construction phase

International Nuclear Information System (INIS)

2000-12-01

will be the cornerstone of the long-term safety case, but the argumentation for safety will also be based on broader technical and scientific evidence. A substantial part of the programme activities will be staged according to the progress of the planned underground rock characterisation facility, ONKALO, at Olkiluoto. The plan is to start the construction of ONKALO in 2003-2004. Before that Posiva will complete the documentation concerning the: baseline description of the Olkiluoto site; technical design description of the planned underground rock characterisation facility; plan for underground investigations and review of the rock characteristics that are important for the long-term safety of disposal together with an assessment of how the ONKALO project would affect these. Later, at the end of 2005, Posiva will publish an interim progress report of the disposal programme. The report will also contain a more detailed description of the activities planned for the latter half of the programme period. (orig.)

How to solve nuclear siting problems

International Nuclear Information System (INIS)

Inhaber, H.

1992-01-01

In recent years, finding sites for nuclear facilities, both reactors and waste repositories, has become more of a problem. While all agree that the difficulties are more than technical, a technical solution is presently pursued. The reverse Dutch auction generates a solution to siting. It produces a volunteer community or state, at the same time retaining public safety and environmental standards. No coercion is required. Elements of the system already exist in a number of public policy areas. (orig.) [de

Bioremediation of mixed microbial mats: System development of mixed contaminants for application at the Savannah River Site. Annual technical progress report, October 1, 1995--September 30, 1996

International Nuclear Information System (INIS)

Bender, J.; Phillips, P.

1996-01-01

The fundamental objective of this project is to develop and field test the mixed microbial mat bioremediation system for decontamination of target sites at SRS. Although microbial mats have performed well in several pilot projects in the past, atypical problems and site characteristics at SRS demand special field designs. In the interest of designing a pilot and locating it at an appropriate site, the project investigators have worked closely with the technical staff at the SREL. We have concluded that the diverse characteristics of contaminations at SRS may dictate testing several pilot designs during the course of this project

75 FR 35781 - Centana Intrastate Pipeline, LLC; Notice of Baseline Filing

Science.gov (United States)

2010-06-23

... the Web site that enables subscribers to receive e-mail notification when a document is added to a subscribed docket(s). For assistance with any FERC Online service, please e-mail [email protected] Intrastate Pipeline, LLC submitted a baseline filing of its Transport Statement of Operating Conditions for...

Global Nuclear Energy Partnership Waste Treatment Baseline

International Nuclear Information System (INIS)

Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John

2008-01-01

The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

Global Nuclear Energy Partnership Waste Treatment Baseline

Energy Technology Data Exchange (ETDEWEB)

Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

2008-07-01

The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

Global Nuclear Energy Partnership Waste Treatment Baseline

Energy Technology Data Exchange (ETDEWEB)

Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

2008-05-01

The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

Evolution of EPA/DOE technical cooperation in remediation of radiation/mixed waste contaminated sites

International Nuclear Information System (INIS)

Dyer, Robert S.; Garcia-Frias, Beverly; Wolbarst, Anthony B.; Coe, Larry J.

1992-01-01

The EPA Office of Radiation Programs (ORP) and the DOE Office of Environmental Restoration and Waste Management (EM) are cooperating in efforts related to restoration of radioactive and mixed waste sites. The impetus for these efforts derived from DOE's need to perform restoration activities according to CERCLA/RCRA requirements, and from ORP's role as a supplier of radiation expertise to federal agencies. These activities include: assessing remediation technology, developing radioanalytical protocols; matching cleanup technologies to soil characteristics; developing a process for the evaluation, selection, and appropriate use of groundwater models; reviewing incinerator practices; and addressing technical issues associated with the WIPP. Cooperative projects planned for the future include: evaluation of methodologies for streamlining the restoration process; assessment of the applicability of process knowledge for waste characterization; evaluation of recycling of radioactive metals; and expansion of selected environmental protection initiatives at the International Atomic Energy Agency (IAEA). Public acceptance is a crucial component of the remediation process. An underlying objective of these cooperative initiatives is to address issues of concern to the public in an open and honest fashion. (author)

Tanks Focus Area Site Needs Assessment - FY 2001

Energy Technology Data Exchange (ETDEWEB)

Allen, Robert W.; Josephson, Gary B.; Westsik, Joseph H.; Nickola, Cheryl L.

2001-04-30

The TFA uses a systematic process for developing its annual program that draws from the tanks science and technology development needs expressed by the five DOE tank waste sites. TFA's annual program development process is iterative and involves the following steps: Collection of site needs; Needs analysis; Development of technical responses and initial prioritization; Refinement of the program for the next fiscal year; Formulation of the Corporate Review Budget (CRB); Preparation of Program Execution Guidance (PEG) for the next FY Revision of the Multiyear Program Plan (MYPP). This document describes the outcomes of the first phase of this process, from collection of site needs to the initial prioritization of technical activities. The TFA received site needs in October - December 2000. A total of 170 site needs were received, an increase of 30 over the previous year. The needs were analyzed and integrated, where appropriate. Sixty-six distinct technical responses were drafted and prioritized. In addition, seven strategic tasks were approved to compete for available funding in FY 2002 and FY 2003. Draft technical responses were prepared and provided to the TFA Site Representatives and the TFA User Steering Group (USG) for their review and comment. These responses were discussed at a March 15, 2001, meeting where the TFA Management Team established the priority listing in preparation for input to the DOE Office of Science and Technology (OST) budget process. At the time of publication of this document, the TFA continues to finalize technical responses as directed by the TFA Management Team and clarify the intended work scopes for FY 2002 and FY 2003.

HFM web-site linked to the technical & administrative databases

CERN Document Server

Szeberenyi, A

2013-01-01

The EuCARD project has been using various databases to store scientific and contractual information, as well as working documents. This report documents the methods used during the life of the project and the strategy chosen to archive the technical and administrative material after the project completion. Special care is given to provide easy and open access for the foreground produced, especially for the EuCARD-2 community at large, including its network partners worldwide.

Technical Training: Places available

CERN Multimedia

Monique Duval

2005-01-01

The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: LabVIEW Real-Time (F) : 7 - 9.6.2005 (3 jours) LabVIEW Migration 6 to 7: 14.6.2005 (1 day) IT3T/1 - Read your mail and more with Outlook 2003 : 14.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/2 - Creating, managing and using distribution lists with Simba2 : 16.6.2005 (IT Technical Training Tutorial, free of charge) FrontPage 2003 - niveau 2 : 16 & 17.6.2005 (2 jours) Utilisation de fichiers PDF avec ACROBAT 6.0 : 20.6.2005 (1journée) Introduction to ANSYS: 21 - 24.6.2005 (4 days) IT3T/3 - Working remotely with Windows XP : 28.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/4 - Editing Websites with Frontpage 2003 : 30.6.2005 (IT Technical Training Tutorial, free of charge) WORD 2003 (Short Course I) - HowTo... Work with repetitive tasks /AutoText, AutoFormat, AutoC...

Baseline Risk Assessment Supporting Closure at Waste Management Area C at the Hanford Site Washington

International Nuclear Information System (INIS)

Singleton, Kristin M.

2015-01-01

The Office of River Protection under the U.S. Department of Energy is pursuing closure of the Single-Shell Tank (SST) Waste Management Area (WMA) C under the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO). A baseline risk assessment (BRA) of current conditions is based on available characterization data and information collected at WMA C. The baseline risk assessment is being developed as a part of a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI)/Corrective Measures Study (CMS) at WMA C that is mandatory under Comprehensive Environmental Response, Compensation, and Liability Act and RCRA corrective action. The RFI/CMS is needed to identify and evaluate the hazardous chemical and radiological contamination in the vadose zone from past releases of waste from WMA C. WMA C will be under Federal ownership and control for the foreseeable future, and managed as an industrial area with restricted access and various institutional controls. The exposure scenarios evaluated under these conditions include Model Toxics Control Act (MTCA) Method C, industrial worker, maintenance and surveillance worker, construction worker, and trespasser scenarios. The BRA evaluates several unrestricted land use scenarios (residential all-pathway, MTCA Method B, and Tribal) to provide additional information for risk management. Analytical results from 13 shallow zone (0 to 15 ft. below ground surface) sampling locations were collected to evaluate human health impacts at WMA C. In addition, soil analytical data were screened against background concentrations and ecological soil screening levels to determine if soil concentrations have the potential to adversely affect ecological receptors. Analytical data from 12 groundwater monitoring wells were evaluated between 2004 and 2013. A screening of groundwater monitoring data against background concentrations and Federal maximum concentration levels was used to determine vadose zone

Baseline Risk Assessment Supporting Closure at Waste Management Area C at the Hanford Site Washington

Energy Technology Data Exchange (ETDEWEB)

Singleton, Kristin M. [Washington River Protection Solutions LLC, Richland, WA (United States)

2015-01-07

The Office of River Protection under the U.S. Department of Energy is pursuing closure of the Single-Shell Tank (SST) Waste Management Area (WMA) C under the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO). A baseline risk assessment (BRA) of current conditions is based on available characterization data and information collected at WMA C. The baseline risk assessment is being developed as a part of a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI)/Corrective Measures Study (CMS) at WMA C that is mandatory under Comprehensive Environmental Response, Compensation, and Liability Act and RCRA corrective action. The RFI/CMS is needed to identify and evaluate the hazardous chemical and radiological contamination in the vadose zone from past releases of waste from WMA C. WMA C will be under Federal ownership and control for the foreseeable future, and managed as an industrial area with restricted access and various institutional controls. The exposure scenarios evaluated under these conditions include Model Toxics Control Act (MTCA) Method C, industrial worker, maintenance and surveillance worker, construction worker, and trespasser scenarios. The BRA evaluates several unrestricted land use scenarios (residential all-pathway, MTCA Method B, and Tribal) to provide additional information for risk management. Analytical results from 13 shallow zone (0 to 15 ft. below ground surface) sampling locations were collected to evaluate human health impacts at WMA C. In addition, soil analytical data were screened against background concentrations and ecological soil screening levels to determine if soil concentrations have the potential to adversely affect ecological receptors. Analytical data from 12 groundwater monitoring wells were evaluated between 2004 and 2013. A screening of groundwater monitoring data against background concentrations and Federal maximum concentration levels was used to determine vadose zone

Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986. Volume 1, Site geohydrology and waste sites

Energy Technology Data Exchange (ETDEWEB)

Heffner, J.D. [ed.] [Exploration Resources, Inc., Athens, GA (United States)

1991-11-01

This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy`s (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon`s 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined.

High-Level software requirements specification for the TWRS controlled baseline database system

International Nuclear Information System (INIS)

Spencer, S.G.

1998-01-01

This Software Requirements Specification (SRS) is an as-built document that presents the Tank Waste Remediation System (TWRS) Controlled Baseline Database (TCBD) in its current state. It was originally known as the Performance Measurement Control System (PMCS). Conversion to the new system name has not occurred within the current production system. Therefore, for simplicity, all references to TCBD are equivalent to PMCS references. This SRS will reference the PMCS designator from this point forward to capture the as-built SRS. This SRS is written at a high-level and is intended to provide the design basis for the PMCS. The PMCS was first released as the electronic data repository for cost, schedule, and technical administrative baseline information for the TAAS Program. During its initial development, the PMCS was accepted by the customer, TARS Business Management, with no formal documentation to capture the initial requirements

Disposal of mixed waste: Technical, institutional, and policy factors

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Letourneau, M.J.; Case, J.T.

1996-01-01

In conjunction with the affected States as part of their interactions required by the Federal Facilities Compliance Act, the Department of Energy has been developing a process for a disposal configuration for its mixed low-level waste (MLLW). This effort, spanning more than two years, has reduced the potential disposal sites from 49 to 15. The remaining 15 sites have been subjected to a performance evaluation to determine their strengths and weaknesses for disposal of MLLW. The process has included institutional and policy factors as well as strictly technical analyses, and technical analyses must be supported by technical analyses, and technical analyses must be performed within a framework which includes some institutional considerations, with the institutional considerations selected for inclusion largely a matter of policy. While the disposal configuration process is yet to be completed, the experience to date offers a viable approach for solving some of these issues. Additionally, several factors remain to be addressed before an MLLW disposal configuration can be developed

Characterization of Sediments from the Soil Desiccation Pilot Test (SDPT) Site in the BC Cribs and Trenches Area

Energy Technology Data Exchange (ETDEWEB)

Um, Wooyong; Truex, Michael J.; Valenta, Michelle M.; Iovin, Cristian; Kutnyakov, Igor V.; Chang, Hyun-shik; Clayton, Ray E.; Serne, R. Jeffrey; Ward, Anderson L.; Brown, Christopher F.; Geiszler, Keith N.; Clayton, Eric T.; Baum, Steven R.; Smith, David M.

2009-09-25

This technical report documents the results of laboratory geochemical and hydrologic measurements of sediments collected from new borehole 299-E13-65 (C7047) and comparison of the results with those of nearby borehole 299-13E-62 (C5923) both drilled in the BC Cribs and Trenches Area. The total and water-leachable concentrations of key contaminants will be used to update contaminant-distribution conceptual models and to provide more data for improving baseline risk predictions and remedial alternative selections. Improved understanding of subsurface conditions and methods to remediate these principal contaminants can be also used to evaluate the application of specific technologies to other contaminants across the Hanford Site.

Technical issues in the geologic disposal of radioactive wastes

International Nuclear Information System (INIS)

Weart, W.D.

1980-01-01

The status of technical understanding regarding radioactive waste repositories in geologic media is improving at a rapid rate. Within a few years the knowledge regarding non-salt repositories will be on a par with that which now exists for salt. To date there is no technical reason to doubt that geologic repositories in several different geologic media can be safely implemented to provide long-term isolation of radioactive wastes. Indeed, for bedded salt, there is now sufficient knowledge to allow all the identified phenomena to be bounded with satisfactory resultant consequences. It is possible to now proceed with technical confidence in an orderly development of a bedded-salt repository at a satisfactory site. This development would call for in-situ experiments, at the earliest possible stage, to confirm or validate the predictions made for the site. These in-situ experiments will be necessary for each repository in a different rock type. If, for non-technical reasons, repository development is delayed, field test facilities should be located as soon as possible in geologic settings typical of proposed repositories. Extensive testing to resolve generic issues will allow subsequent development of repositories to proceed more rapidly with only minimal in-situ testing required to resolve site-specific concerns

School-to-Work Transition of Career and Technical Education Graduates

Science.gov (United States)

Packard, Becky Wai-Ling; Leach, Miki; Ruiz, Yedalis; Nelson, Consuelo; DiCocco, Hannah

2012-01-01

This study analyzed the career development of career and technical education (CTE) high school graduates during their school-to-work transition, specifically their adaptability in the face of barriers. Forty graduates (22 men, 18 women) from working-class backgrounds participated in baseline surveys at graduation and phenomenological interviews 1…

Opportunities for Research in the UK for decommissioning and disposal

International Nuclear Information System (INIS)

Smart, N.

2008-01-01

The NDA remit as set out within the Energy Act includes - 'promote, and where necessary fund, research relevant to nuclear clean up'. The NDA need to underpin delivery and / or accelerate programmes to fulfil the overall mission and technical underpinning of these activities is critical. In this paper we will present consideration of the investment required in nuclear waste Research and Development. Firstly, NDA set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, the proposed technical baseline underpinning the LTP activities; furthermore we required technology gaps / opportunities in the technical baselines to be outlined in a R and D requirements section to the LTP. Criteria were established to categorise the R and D in three areas: - 'needs' - those development activities needed to underpin the proposed technical solutions - 'risks' - those activities required to reduce / eliminate key risks to the proposed technical solutions - 'opportunities' - innovations / changes to the technical baselines The purpose of production of the technical baselines and underpinning R and D requirements is to establish an auditable trail through the LTP from programme components into how the programme will be delivered. NDA believes the production of the technical baselines and R and D requirements will be of benefit to the Site License Companies (SLC) in terms of ensuring a focus on overall programme delivery and not just short term activities. Furthermore, we can ensure that investment in technology is targeted at priority areas, with common issues and requirements identified and solutions on a broader scale will be achievable. (authors)

Baseline Risk Assessment for the F-Area Burning/Rubble Pits and Rubble Pit

Energy Technology Data Exchange (ETDEWEB)

Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1996-03-01

This document provides an overview of the Savannah River Site (SRS) and a description of the F-Area Burning/Rubble Pits (BRPs) and Rubble Pit (RP) unit. It also describes the objectives and scope of the baseline risk assessment (BRA).

ITER technical advisory committee meeting

International Nuclear Information System (INIS)

Fujiwara, M.

2001-01-01

The 17th Meeting of the ITER Technical Advisory Committee (TAC-17) was held on February 19-22, the ITER Garching Work Site in Germany. The objective of the meeting was to review the Draft Final Design Report of ITER-FEAT and assess the ability of the self-consistent overall design both to satisfy the technical objectives previously defined and to meet the cost limitations. TAC-17 was also organized to confirm that the design and critical elements, with emphasis on the key recommendations made at previous TAC meetings, are such as to extend the confidence in starting ITER construction. It was also intended to provide the ITER Council, scheduled to meet on 27 and 28 February in Toronto, with a technical assessment and key recommendations of the above mentioned report

Constraining proposed combinations of ice history and Earth rheology using VLBI determined baseline length rates in North America

Science.gov (United States)

Mitrovica, J. X.; Davis, J. L.; Shapiro, I. I.

1993-01-01

We predict the present-day rates of change of the lengths of 19 North American baselines due to the glacial isostatic adjustment process. Contrary to previously published research, we find that the three dimensional motion of each of the sites defining a baseline, rather than only the radial motions of these sites, needs to be considered to obtain an accurate estimate of the rate of change of the baseline length. Predictions are generated using a suite of Earth models and late Pleistocene ice histories, these include specific combinations of the two which have been proposed in the literature as satisfying a variety of rebound related geophysical observations from the North American region. A number of these published models are shown to predict rates which differ significantly from the VLBI observations.

Turbidity monitoring at select MDOT construction sites.

Science.gov (United States)

2012-06-01

The objective of this project was to establish baseline turbidity conditions at select construction : sites by establishing a water quality monitoring program and documenting MDOT approved : BMPs on site. In 2009 the United States Environmental Prote...

Overview and technical and practical aspects for use of geostatistics in hazardous-, toxic-, and radioactive-waste-site investigations

International Nuclear Information System (INIS)

Bossong, C.R.; Karlinger, M.R.; Troutman, B.M.; Vecchia, A.V.

1999-01-01

Technical and practical aspects of applying geostatistics are developed for individuals involved in investigation at hazardous-, toxic-, and radioactive-waste sites. Important geostatistical concepts, such as variograms and ordinary, universal, and indicator kriging, are described in general terms for introductory purposes and in more detail for practical applications. Variogram modeling using measured ground-water elevation data is described in detail to illustrate principles of stationarity, anisotropy, transformations, and cross validation. Several examples of kriging applications are described using ground-water-level elevations, bedrock elevations, and ground-water-quality data. A review of contemporary literature and selected public domain software associated with geostatistics also is provided, as is a discussion of alternative methods for spatial modeling, including inverse distance weighting, triangulation, splines, trend-surface analysis, and simulation

Yucca Mountain Project technical status report (TSR), October 1989--March 1990

International Nuclear Information System (INIS)

1990-01-01

This Yucca Mountain Project Technical Status Report (TSR) on site characterization is the second in a series of reports that will be issued at approximately six-month intervals during site characterization. In addition, progress made toward the initiation and conduct of new site characterization activities is included. For this report, information on the technical progress made by Yucca Mountain Project participating organizations has been compiled covering the period from October 1989, through March 31, 1990. The status report consists of three sections: an introductory section; a section on the status of site characterization, which includes preparatory activities, sites programs, repository design, seals system design, waste package design, and performance assessment; and a reference section, which provides a complete listing of all published documents cited in the text. 59 refs

Data Management Guide: Integrated Baseline System (IBS). Version 2.1

Energy Technology Data Exchange (ETDEWEB)

Bower, J.C. [Bower Software Services, Kennewick, Washington (United States); Burford, M.J.; Downing, T.R.; Moise, M.C.; Williams, J.R. [Pacific Northwest Lab., Richland, WA (United States)

1995-01-01

The Integrated Baseline System (IBS) is an emergency management planning and analysis tool that is being developed under the direction of the US Army Nuclear and Chemical Agency (USANCA). The IBS Data Management Guide provides the background, as well as the operations and procedures needed to generate and maintain a site-specific map database. Data and system managers use this guide to manage the data files and database that support the administrative, user-environment, database management, and operational capabilities of the IBS. This document provides a description of the data files and structures necessary for running the IBS software and using the site map database.

Using the baseline environmental management report (BEMR) to examine alternate program scenarios

International Nuclear Information System (INIS)

Kristofferson, K.

1995-01-01

The US Department of Energy's (DOE) Office of Environmental Management (EM) released the first Baseline Environmental Management Report (BEMR) in March, 1995. The Congressionally-mandated report provides life-cycle cost estimates, tentative schedules, and projected activities necessary to complete DOE's Environmental Management Program. This ''base case'' estimate is based on current program assumptions and the most likely set of activities. However, since the future course of the Environmental Management Program depends upon a number of fundamental technical and policy choices, alternate program scenarios were developed. These alternate cases show the potential cost impacts of changing assumptions in four key areas: future land use, program funding and scheduling, technology development, and waste management configurations. Several cost and program evaluation tools were developed to support the analysis of these alternate cases. The objective of this paper is to describe the analytical tool kit developed to support the development of the 1995 Baseline Report and to discuss the application of these tools to evaluate alternate program scenarios

Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-07-01

At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

International Nuclear Information System (INIS)

1990-01-01

At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

Back pain in seniors: the Back pain Outcomes using Longitudinal Data (BOLD) cohort baseline data.

Science.gov (United States)

Jarvik, Jeffrey G; Comstock, Bryan A; Heagerty, Patrick J; Turner, Judith A; Sullivan, Sean D; Shi, Xu; Nerenz, David R; Nedeljkovic, Srdjan S; Kessler, Larry; James, Kathryn; Friedly, Janna L; Bresnahan, Brian W; Bauer, Zoya; Avins, Andrew L; Deyo, Richard A

2014-04-23

Back pain represents a substantial burden globally, ranking first in a recent assessment among causes of years lived with disability. Though back pain is widely studied among working age adults, there are gaps with respect to basic descriptive epidemiology among seniors, especially in the United States. Our goal was to describe how pain, function and health-related quality of life vary by demographic and geographic factors among seniors presenting to primary care providers with new episodes of care for back pain. We examined baseline data from the Back pain Outcomes using Longitudinal Data (BOLD) registry, the largest inception cohort to date of seniors presenting to a primary care provider for back pain. The sample included 5,239 patients ≥ 65 years old with a new primary care visit for back pain at three integrated health systems (Northern California Kaiser-Permanente, Henry Ford Health System [Detroit], and Harvard Vanguard Medical Associates [Boston]). We examined differences in patient characteristics across healthcare sites and associations of patient sociodemographic and clinical characteristics with baseline patient-reported measures of pain, function, and health-related quality of life. Patients differed across sites in demographic and other characteristics. The Detroit site had more African-American patients (50%) compared with the other sites (7-8%). The Boston site had more college graduates (68%) compared with Detroit (20%). Female sex, lower educational status, African-American race, and older age were associated with worse functional disability as measured by the Roland-Morris Disability Questionnaire. Except for age, these factors were also associated with worse pain. Baseline pain and functional impairment varied substantially with a number of factors in the BOLD cohort. Healthcare site was an important factor. After controlling for healthcare site, lower education, female sex, African-American race, and older age were associated with worse

DOE management of high-level waste at the Hanford Site

International Nuclear Information System (INIS)

1993-01-01

Approximately 60 million gallons of high-level radioactive waste--caustic liquids, slurries, saltcakes, and sludges--are stored in underground tanks at the Department of Energy's Hanford Site. At least one-third of the tanks are known to have leaked waste into the enviroranent, and there are many unresolved tank safety issues. In order to resolve the environmental and safety concerns, the Department plans to retrieve the waste, immobilize it, and dispose of it in a permanent geologic repository. Processing all of the tank waste in this manner could cost $40 billion, including $1.2 billion to construct the Hanford Waste Vitrification Plant. The purpose of our audit was to examine the reasons for cost estimate increases and schedule delays on the Hanford vitrification program. We also wanted to report on outstanding technical, safety, and environmental issues that could make the project even more costly and further delay its completion. We found that the Department managed the Hanford remediation system as a number of separate projects not fully integrated into one major system acquisition. Total costs have, therefore, been obscured, and the Department has not yet clearly defined system requirements or developed overall cost and schedule baselines. This lack of visibility could result in additional cost growth and schedule delays. We also noted a vast array of technical uncertainties, including tank safety and inadequate information about the makeup of tank waste, that could significantly affect the program's cost and ultimate success. To increase visibility of program cost and schedule, we are recommending that all separate projects relating to tank waste be included in a single major system acquisition, and that the Department complete its ongoing baselining effort to the extent practical before making major funding commitments. Management concurred with our finding and recommendations

77 FR 71430 - New Agency Information Collection Activity Under OMB Review: Public Transportation Baseline...

Science.gov (United States)

2012-11-30

... DEPARTMENT OF HOMELAND SECURITY Transportation Security Administration New Agency Information Collection Activity Under OMB Review: Public Transportation Baseline Assessment for Security Enhancement... voluntary site visits with security and operating officials of public transportation systems. This program...

Involving technical professionals in community relations

International Nuclear Information System (INIS)

Meyer, K.A.; Meyer, L.

1994-01-01

The Weldon Spring site Remedial Action Project (WSSRAP), a U.S. Department of Energy (DOE) environmental restoration project, has developed a successful community relations program that differs from the traditional approach and has built a general consensus about the DOE's work at the Weldon Spring site. The WSSRAP has a small, dedicated Community Relations Department that is heavily supported by technical professionals who receive intensive training in preparatory and presentation skills, role-playing, and critiquing of performances. This training allows the public to speak directly with the individuals responsible for remediation activities. The media, in turn, has access to technical individuals with good presentation skills, and WSSRAP managers can be confident that interactions are handled professionally. This approach results in a satisfied client. The WSSRAP's community relations program is a high-quality, cost-effective program that could be easily implemented by other facilities

Active sites in char gasification: Final technical report

Energy Technology Data Exchange (ETDEWEB)

Wojtowicz, M.; Lilly, W.D.; Perkins, M.T.; Hradil, G.; Calo, J.M.; Suuberg, E.M.

1987-09-01

Among the key variables in the design of gasifiers and combustors is the reactivity of the chars which must be gasified or combusted. Significant loss of unburned char is unacceptable in virtually any process; the provision of sufficient residence time for complete conversion is essential. A very wide range of reactivities are observed, depending upon the nature of the char in a process. The current work focuses on furthering the understanding of gasification reactivities of chars. It has been well established that the reactivity of char to gasification generally depends upon three principal factors: (1) the concentration of ''active sites'' in the char; (2) mass transfer within the char; and (3) the type and concentration of catalytic impurities in the char. The present study primarily addresses the first factor. The subject of this research is the origin, nature, and fate of active sites in chars derived from parent hydrocarbons with coal-like structure. The nature and number of the active sites and their reactivity towards oxygen are examined in ''model'' chars derived from phenol-formaldehyde type resins. How the active sites are lost by the process of thermal annealing during heat treatment of chars are studied, and actual rate for the annealing process is derived. Since intrinsic char reactivities are of primary interest in the present study, a fair amount of attention was given to the model char synthesis and handling so that the effect of catalytic impurities and oxygen-containing functional groups in the chemical structure of the material were minimized, if not completely eliminated. The project would not be considered complete without comparing characteristic features of synthetic chars with kinetic behavior exhibited by natural chars, including coal chars.

Epibenthic Assessment of a Renewable Tidal Energy Site

Directory of Open Access Journals (Sweden)

Emma V. Sheehan

2013-01-01

Full Text Available Concern over global climate change as a result of fossil fuel use has resulted in energy production from renewable sources. Marine renewable energy devices provide clean electricity but can also cause physical disturbance to the local environment. There is a considerable paucity of ecological data at potential marine renewable energy sites that is needed to assess potential future impacts and allow optimal siting of devices. Here, we provide a baseline benthic survey for the Big Russel in Guernsey, UK, a potential site for tidal energy development. To assess the suitability of proposed sites for marine renewable energy in the Big Russel and to identify potential control sites, we compared species assemblages and habitat types. This baseline survey can be used to select control habitats to compare and monitor the benthic communities after installation of the device and contribute towards the optimal siting of any future installation.

Shifting environmental baselines in the Red Sea.

Science.gov (United States)

Price, A R G; Ghazi, S J; Tkaczynski, P J; Venkatachalam, A J; Santillan, A; Pancho, T; Metcalfe, R; Saunders, J

2014-01-15

The Red Sea is among the world's top marine biodiversity hotspots. We re-examined coastal ecosystems at sites surveyed during the 1980s using the same methodology. Coral cover increased significantly towards the north, mirroring the reverse pattern for mangroves and other sedimentary ecosystems. Latitudinal patterns are broadly consistent across both surveys and with results from independent studies. Coral cover showed greatest change, declining significantly from a median score of 4 (1000-9999 m(2)) to 2 (10-99m(2)) per quadrat in 2010/11. This may partly reflect impact from coastal construction, which was evident at 40% of sites and has significantly increased in magnitude over 30 years. Beach oil has significantly declined, but shore debris has increased significantly. Although substantial, levels are lower than at some remote ocean atolls. While earlier reports have suggested that the Red Sea is generally healthy, shifting environmental baselines are evident from the current study. Copyright © 2013 Elsevier Ltd. All rights reserved.

Compliance monitoring for remediated sites

International Nuclear Information System (INIS)

1999-10-01

Throughout the world, many countries have experienced problems associated with pollution of the environment. Poorly managed practices in nuclear fuel cycle, medicine, industry, weapons production and testing, research and development activities, as well as accidents, and poor disposal practices have produced a large array of radioactively contaminated facilities and sites. Structures, biota, soils, rocks, and both surface and groundwaters have become contaminated with radionuclides and other associated contaminants, a condition that raises serious concern due to potential health effects to the exposed human populations and the environment. In response to the needs of its Member States in dealing with the problems of radioactive contamination in the environment, the IAEA has established an Environmental Restoration Project. The principal aspects of current IAEA efforts in this area include (1) gathering information and data, performing analyses, and publishing technical summaries, and other documents on key technical aspects of environmental restoration; (2) conducting a Co-ordinated Research Project on Environmental Restoration; and (3) providing direct technical assistance to Member States through technical co-operation programmes. The transfer of technologies to Member States in need of applicable methodologies and techniques for the remediation of contaminated sites is a principal objective of this project

Site characterization report for the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1982-11-01

This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues

Low-level siting, Edgemont, South Dakota

International Nuclear Information System (INIS)

Andrews, L.J.

1984-01-01

The siting of a low-level radwaste disposal facility and characterization activities to date in Edgemont, South Dakota are discussed. By using past and present experience the author sets forth the major problem, the social and political considerations, community acceptance, media and public officials' attitudes, criteria for acceptance and significance of countywide vote in support of facility. Characterization activities, site selection planning and criteria, above-grade and below-grade technical evaluation, NRC interface, 10 CFR Part 61 related to technical work, as well as community acceptance and license application are covered. The paper deals with specific problems, solutions and ongoing activities

Baseline Screening Mammography: Performance of Full-Field Digital Mammography Versus Digital Breast Tomosynthesis.

Science.gov (United States)

McDonald, Elizabeth S; McCarthy, Anne Marie; Akhtar, Amana L; Synnestvedt, Marie B; Schnall, Mitchell; Conant, Emily F

2015-11-01

Baseline mammography studies have significantly higher recall rates than mammography studies with available comparison examinations. Digital breast tomosynthesis reduces recalls when compared with digital mammographic screening alone, but many sites operate in a hybrid environment. To maximize the effect of screening digital breast tomosynthesis with limited resources, choosing which patient populations will benefit most is critical. This study evaluates digital breast tomosynthesis in the baseline screening population. Outcomes were compared for 10,728 women who underwent digital mammography screening, including 1204 (11.2%) baseline studies, and 15,571 women who underwent digital breast tomosynthesis screening, including 1859 (11.9%) baseline studies. Recall rates, cancer detection rates, and positive predictive values were calculated. Logistic regression estimated the odds ratios of recall for digital mammography versus digital breast tomosynthesis for patients undergoing baseline screening and previously screened patients, adjusted for age, race, and breast density. In the baseline subgroup, recall rates for digital mammography and digital breast tomosynthesis screening were 20.5% and 16.0%, respectively (p = 0.002); digital breast tomosynthesis screening in the baseline subgroup resulted in a 22% reduction in recall compared with digital mammography, or 45 fewer patients recalled per 1000 patients screened. Digital breast tomosynthesis screening in the previously screened patients resulted in recall reduction of 14.3% (p tomosynthesis than from digital mammography alone.

ITER technical meeting on nuclear analysis

International Nuclear Information System (INIS)

Khripunov, V.

2000-01-01

The ITER technical meeting on nuclear analysis was organized on 24-25 February 2000 at the ITER Joint Work Site in Garching. It was clear from the meeting that continuous nuclear analysis is a fundamental part of the design process

Fusion power demonstration: baseline report

International Nuclear Information System (INIS)

Henning, C.D.; Logan, B.G.; Neef, W.S.

1984-01-01

An overview is given of the FPD project. A technical discussion of the primary independent plasma parameters, the physics constraints that limited the allowed combinations of those parameters for ignition, and the basic plasma scaling laws that govern FPD plasma parameters are described. Plans are detailed for phased construction and operation of FPD. The components for FPD are based on those designed for the Mirror Advanced Reactor Study (MARS). Although FPD costs are based on the MARS first-of-a-kind estimates, FPD contains design modifications made to reduce these costs. The preliminary results of siting and safety studies are described. An essential element of FPD design is the ability to perform remote maintenance on the equipment. The key research and development issues associated with the design and implementation of an FPD facility are highlighted

Reference manual for toxicity and exposure assessment and risk characterization. CERCLA Baseline Risk Assessment

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, 1980) (CERCLA or Superfund) was enacted to provide a program for identifying and responding to releases of hazardous substances into the environment. The Superfund Amendments and Reauthorization Act (SARA, 1986) was enacted to strengthen CERCLA by requiring that site clean-ups be permanent, and that they use treatments that significantly reduce the volume, toxicity, or mobility of hazardous pollutants. The National Oil and Hazardous Substances Pollution Contingency Plan (NCP) (USEPA, 1985; USEPA, 1990) implements the CERCLA statute, presenting a process for (1) identifying and prioritizing sites requiring remediation and (2) assessing the extent of remedial action required at each site. The process includes performing two studies: a Remedial Investigation (RI) to evaluate the nature, extent, and expected consequences of site contamination, and a Feasibility Study (FS) to select an appropriate remedial alternative adequate to reduce such risks to acceptable levels. An integral part of the RI is the evaluation of human health risks posed by hazardous substance releases. This risk evaluation serves a number of purposes within the overall context of the RI/FS process, the most essential of which is to provide an understanding of ``baseline`` risks posed by a given site. Baseline risks are those risks that would exist if no remediation or institutional controls are applied at a site. This document was written to (1) guide risk assessors through the process of interpreting EPA BRA policy and (2) help risk assessors to discuss EPA policy with regulators, decision makers, and stakeholders as it relates to conditions at a particular DOE site.

Reference manual for toxicity and exposure assessment and risk characterization. CERCLA Baseline Risk Assessment

International Nuclear Information System (INIS)

1995-03-01

The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, 1980) (CERCLA or Superfund) was enacted to provide a program for identifying and responding to releases of hazardous substances into the environment. The Superfund Amendments and Reauthorization Act (SARA, 1986) was enacted to strengthen CERCLA by requiring that site clean-ups be permanent, and that they use treatments that significantly reduce the volume, toxicity, or mobility of hazardous pollutants. The National Oil and Hazardous Substances Pollution Contingency Plan (NCP) (USEPA, 1985; USEPA, 1990) implements the CERCLA statute, presenting a process for (1) identifying and prioritizing sites requiring remediation and (2) assessing the extent of remedial action required at each site. The process includes performing two studies: a Remedial Investigation (RI) to evaluate the nature, extent, and expected consequences of site contamination, and a Feasibility Study (FS) to select an appropriate remedial alternative adequate to reduce such risks to acceptable levels. An integral part of the RI is the evaluation of human health risks posed by hazardous substance releases. This risk evaluation serves a number of purposes within the overall context of the RI/FS process, the most essential of which is to provide an understanding of ''baseline'' risks posed by a given site. Baseline risks are those risks that would exist if no remediation or institutional controls are applied at a site. This document was written to (1) guide risk assessors through the process of interpreting EPA BRA policy and (2) help risk assessors to discuss EPA policy with regulators, decision makers, and stakeholders as it relates to conditions at a particular DOE site

Declassification and restoration of nuclear sites

International Nuclear Information System (INIS)

Noynaert, L.; Rahier, A.; Deboodt, P.; Massaut, V.

1998-09-01

The report describes the legal and technical aspects of the declassification and restoration of nuclear sites. This involves a number of technical and administrative operations. Different declassification strategies are discussed. The evaluation of the risks and impact on the environment are discussed as well as research and development needs, costs and possible sources for funding

Base-line studies for DAE establishments

International Nuclear Information System (INIS)

Puranik, V.D.

2012-01-01

The Department of Atomic Energy has establishments located in various regions of the country and they include front-end fuel cycle facilities, nuclear power stations, back-end fuel cycle facilities and facilities for research and societal applications. These facilities handle naturally occurring radionuclides such as uranium, thorium and a variety of man-made radionuclides. These radionuclides are handled with utmost care so that they do not affect adversely the occupational workers or the members of public residing nearby. There is safety culture of the highest standard existing in all DAE establishments and it matches with the international standards. In addition, there is a perpetual environmental monitoring program carried out by the Environmental Survey Laboratories (ESLs) located at all DAE establishments. The environmental data generated by such program is studied regularly by experts to ensure compliance with the regulatory requirements. The regulatory requirements in the country are of international standards and ensure adequate protection of workers and members of public. In addition to such continued monitoring program and studies being carried out for the ongoing projects, base-line studies are carried out for all the new projects of the DAE. The purpose of the base-line studies is to establish a detailed base-line data set for a new DAE location well before the foundation stone is laid, so that the data collected when there is no departmental activity can be compared with the data generated later by the ESL. The data so generated is site specific and it varies from place to place depending upon the location of the site, e.g., inland or coastal, the presence of water bodies and pattern of irrigation, the geological characteristics of the location, the local culture and habits of the people, population density and urban or rural background. The data to be recorded as base-line data is generated over a period of at least one year covering all the seasons

Tillman Creek Mitigation Site As-Build Report.

Energy Technology Data Exchange (ETDEWEB)

Gresham, Doug [Otak, Inc.

2009-05-29

This as-built report describes site conditions at the Tillman Creek mitigation site in South Cle Elum, Washington. This mitigation site was constructed in 2006-2007 to compensate for wetland impacts from the Yakama Nation hatchery. This as-built report provides information on the construction sequence, as-built survey, and establishment of baseline monitoring stations.

New Reactor Siting, Licensing and Construction Experience. Proceedings of the 2. CNRA International Workshop on 'New Reactor Siting, Licensing and Construction Experience'

International Nuclear Information System (INIS)

2013-01-01

This report documents the proceedings from the 2. Workshop on New Reactor Siting, Licensing and Construction Experience. A total of 45 specialists from 16 countries and international organisations attended. The meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the US Nuclear Regulatory Commission (U.S.NRC). The objectives of the workshop were to provide a forum to exchange information on lessons learned from siting, licensing and constructing new nuclear power plants around the world. Key focus areas included siting practices and regulatory positions that have been enhanced as a result of the Fukushima accident; lessons learned from licensing and design review approaches and challenges, construction experience and recommendations for regulatory oversight; and regulatory cooperation on generic and design specific issues through the MDEP specific working groups. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to regulatory cooperation on generic and design specific issues, MDEP working groups (EPR, AP1000), vendor inspection co-operation, digital I and C, and codes and standards. The second technical session was intended to discuss and share regulatory positions on siting practices and enhancements as a result of lessons learned from Fukushima accident. The third technical session addressed the construction experience and regulatory oversight of new reactor construction activities. And the fourth technical session included presentations on the lessons learned from regulatory licensing reviews of new reactor designs

Hanford Site Environmental Management Specification

International Nuclear Information System (INIS)

DAILY, J.L.

2001-01-01

The US Department of Energy, Richland Operations Office (RL) has established a document hierarchy as part of its integrated management system. The Strategic Plan defines the vision, values, missions, strategic goals, high-level outcomes, and the basic strategies in achieving those outcomes. As shown in Figure 1-1, the Site Specification derives requirements from the Strategic Plan and documents the top-level mission technical requirements for the work involved in the RL Hanford Site cleanup and infrastructure activities under the responsibility of the U.S. Department of Energy, Office of Environmental Management (EM). It also provides the basis for all contract technical requirements. Since this is limited to the EM work, neither the Fast Flux Test Facility (FFTF) nor the Pacific Northwest National Laboratory (PNNL) non-EM science activities are included. Figure 1-1 also shows the relationship between this Site Specification and the other Site management and planning documents. Similarly, the documents, orders, and laws referenced in this document represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents

Environmental restoration and remediation technical data management plan

International Nuclear Information System (INIS)

Key, K.T.; Fox, R.D.

1994-02-01

The tasks performed in the Remedial Investigation/Feasibility Study (RI/FS) work plan for each Hanford Site operable unit must meet the requirements of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al 1992). An extensive amount of data will be generated in the evaluation and remediation of hazardous waste sites at the Site. The data must be of sufficient quality, as they will be used to evaluate the need, select the method(s), and support the full remediation of the waste sites as stipulated in the Tri-Party Agreement. In particular, a data management plan (DMP) is to be included in an RI/FS work plan for managing the technical data obtained during the characterization of an operable unit, as well as other data related to the study of the operable unit. Resource Conservation and Recovery Act of 1976 (RCRA) sites are involved in the operable unit. Thus, the data management activities for the operable unit should be applied consistently to RCRA sites in the operable unit as well. This DMP provides common direction for managing-the environmental technical data of all defined operable units at the Hanford Site during the RI/FS activities. Details specific to an operable unit will be included in the actual work plan of that operable unit

Independent technical review of the Hanford Tank Farm Operations

International Nuclear Information System (INIS)

1992-07-01

The Independent Technical Assessment of the Hanford Tank Farm Operations was commissioned by the Assistant Secretary for Environmental Restoration and Waste Management on November 1, 1991. The Independent Technical Assessment team conducted on-site interviews and inspections during the following periods: November 18 to 22,1991; April 13 to 17; and April 27 to May 1, 1992. Westinghouse Hanford Company is the management and operating contractor for the Department of Energy at the Hanford site. The Hanford Tank Farm Operations consists of 177 underground storage tanks containing 61 million gallons of high-level radioactive mixed wastes from the chemical reprocessing of nuclear fuel. The Tank Farm Operations also includes associated transfer lines, ancillary equipment, and instrumentation. The Independent Technical Assessment of the Hanford Tank Farm Operations builds upon the prior assessments of the Hanford Waste Vitrification System and the Hanford Site Tank Waste Disposal Strategy.The objective of this technical assessment was to determine whether an integrated and sound program exists to manage the tank-waste storage and tankfarm operations consistent with the Assistant Secretary for Environmental Restoration and Waste Management's guidance of overall risk minimization. The scope of this review includes the organization, management, operation, planning, facilities, and mitigation of the safety-concerns of the Hanford Tank Waste Remediation System. The assessments presented in the body of this report are based on the detailed observations discussed in the appendices. When the assessments use the term ''Hanford'' as an organizational body it means DOE-RL and Westinghouse Hanford Company as a minimum, and in many instances all of the stake holders for the Hanford site

Near Regional and Site Investigations of the Temelin NPP Site

International Nuclear Information System (INIS)

Prachar, Ivan; Vacek, Jiri; Heralecky, Pavel

2011-01-01

The Temelin NPP is worldwide through heated discussion with nuclear energetic opposition. In addition this discussion goes beyond a border of the Czech Republic. On the other side, results of several international supervisions shown that Temelin NPP is fully comparable with the safest nuclear power plants in the world regarding its technical design and safety functions. This presentation deals with the near regional and site investigations of the Temelin NPP Site. It must be noted that although the Temelin site is situated in the area with low seismicity, item of seismicity is a basic argument against Temelin NPP and therefore a detail seismic hazard assessment was performed

Requirements on the provisional safety analyses and technical comparison of safety measures

International Nuclear Information System (INIS)

2010-04-01

The concept of a Geological Underground Repository (SGT) was adopted by the Swiss Federal Council on April 2 nd , 2008. It fixes the goals and the safety technical criteria as well as the procedures for the choice of the site for an underground repository. Those responsible for waste management evaluate possible site regions according to the present status of geological knowledge and based on the safety criteria defined in SGT as well as on technical feasibility. In a first step, they propose geological repository sites for high level (HAA) and for low and intermediate level (SMA) radioactive wastes and justify their choice in a report delivered to the Swiss Federal Office of Energy. The Swiss Federal Council reviews the choices presented and, in the case of positive evaluation, approves them and considers them as an initial orientation. In a second step, based on the possible sites according to step 1, the waste management institution responsible has to reduce the repositories chosen for HAA and SMA by taking into account safety aspects, technical feasibility as well as space planning and socio-economical aspects. In making this choice, safety aspects have the highest priority. The criteria used for the evaluation in the first step have to be defined using provisional quantitative safety analyses. On the basis of the whole appraisal, including space planning and socio-economical aspects, those responsible for waste management propose at least two repository sites for HAA- and SMA-waste. Their selection is then reviewed by the authorities and, in the case of a positive assesment, the selection is taken as an intermediate result. The remaining sites are further studied to examine site choice and the delivery of a request for a design license. If necessary, the requested geological knowledge has to be confirmed by new investigations. Based on the results of the choosing process and a positive evaluation by the safety authorities, the Swiss Federal Council has to

Sixth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Saji, G.; Baker, D.

1997-01-01

The article summarizes the topics of the Sixth Technical Meeting on Safety and Environment which was held to review the first draft of the Non-Site Specific Safety Report (NSSR-2) and the draft of the ITER Final Design Report Safety Assessment (FDR-Safety) during October 27 - November 4, 1997 at the ITER San Diego Joint Work Site

Development of an approach to correcting MicroPEM baseline drift.

Science.gov (United States)

Zhang, Ting; Chillrud, Steven N; Pitiranggon, Masha; Ross, James; Ji, Junfeng; Yan, Beizhan

2018-07-01

Fine particulate matter (PM 2.5 ) is associated with various adverse health outcomes. The MicroPEM (RTI, NC), a miniaturized real-time portable particulate sensor with an integrated filter for collecting particles, has been widely used for personal PM 2.5 exposure assessment. Five-day deployments were targeted on a total of 142 deployments (personal or residential) to obtain real-time PM 2.5 levels from children living in New York City and Baltimore. Among these 142 deployments, 79 applied high-efficiency particulate air (HEPA) filters in the field at the beginning and end of each deployment to adjust the zero level of the nephelometer. However, unacceptable baseline drift was observed in a large fraction (> 40%) of acquisitions in this study even after HEPA correction. This drift issue has been observed in several other studies as well. The purpose of the present study is to develop an algorithm to correct the baseline drift in MicroPEM based on central site ambient data during inactive time periods. A running baseline & gravimetric correction (RBGC) method was developed based on the comparison of MicroPEM readings during inactive periods to ambient PM 2.5 levels provided by fixed monitoring sites and the gravimetric weight of PM 2.5 collected on the MicroPEM filters. The results after RBGC correction were compared with those using HEPA approach and gravimetric correction alone. Seven pairs of duplicate acquisitions were used to validate the RBGC method. The percentages of acquisitions with baseline drift problems were 42%, 53% and 10% for raw, HEPA corrected, and RBGC corrected data, respectively. Pearson correlation analysis of duplicates showed an increase in the coefficient of determination from 0.75 for raw data to 0.97 after RBGC correction. In addition, the slope of the regression line increased from 0.60 for raw data to 1.00 after RBGC correction. The RBGC approach corrected the baseline drift issue associated with MicroPEM data. The algorithm developed

Safeguards for final disposal of spent nuclear fuel. Methods and technologies for the Olkiluoto site

International Nuclear Information System (INIS)

Okko, O.

2003-05-01

The final disposal of the nuclear material shall introduce new safeguards concerns which have not been addressed previously in IAEA safeguards approaches for spent fuel. The encapsulation plant to be built at the site will be the final opportunity for verification of spent fuel assemblies prior to their transfer to the geological repository. Moreover, additional safety and safeguards measures are considered for the underground repository. Integrated safeguards verification systems will also concentrate on environmental monitoring to observe unannounced activities related to possible diversion schemes at the repository site. The final disposal of spent nuclear fuel in geological formation will begin in Finland within 10 years. After the geological site investigations and according to legal decision made in 2001, the final repository of the spent nuclear fuel shall be located at the Olkiluoto site in Eurajoki. The next phase of site investigations contains the construction of an underground facility, called ONKALO, for rock characterisation purposes. The excavation of the ONKALO is scheduled to start in 2004. Later on, the ONKALO may form a part of the final repository. The plans to construct the underground facility for nuclear material signify that the first safeguards measures, e.g. baseline mapping of the site area, need to take prior to the excavation phase. In order to support the development and implementation of the regulatory control of the final disposal programme, STUK established an independent expert group, LOSKA. The group should support the STUK in the development of the technical safeguards requirements, in the implementation of the safeguards and in the evaluation of the plans of the facility operator. This publication includes four background reports produced by this group. The first of these 'NDA verification of spent fuel, monitoring of disposal canisters, interaction of the safeguards and safety issues in the final disposal' describes the new

ITER technical basis

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties.

ITER technical basis

International Nuclear Information System (INIS)

2002-01-01

Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

The US Department of Energy hydrogen baseline survey: assessing knowledge and opinions about hydrogen technology