Numerical and on-site experimental dynamic analysis of the Italian PEC fast reactor building

International Nuclear Information System (INIS)

Castoldi, A.; Muzzi, F.; Orsi, R.; Panzeri, P.; Pezzoli, P.; Ruggeri, G.; Martelli, A.; Masoni, P.; Brancati, V.

1988-01-01

On-site dynamic tests and three-dimensional numerical analysis have been performed by ISMES on behalf of ENEA on the building of the Italian PEC fast reactor test facility. These studies aimed at evaluating the safety margins in the PEC reactor seismic analysis and at providing data for the optimization of the PEC seismic monitoring system. The paper describes the on-site dynamic tests carried out using various excitation methods (two eccentric back-rotating-mass mechanical vibrator, blasting in bore-hole and hydraulic actuators at the building foundations). It highlights the purposes of the four tests campaigns performed at various construction stages and reports the main experimental results. In connection with the experimental tests, a detailed 3D finite element model was set up for fixed base analysis; from the results of the 3D model a simplified equivalent model of the structure was then derived for soil-structure interaction analysis. The mathematical model was validated and calibrated by using the results of the experimental dynamic tests. The main numerical results and the comparisons with the experimental data are presented. (author)

Load test of the 3701U Building roof deck and support structure

International Nuclear Information System (INIS)

McCoy, R.M.

1994-01-01

The 3701U Building roof area was load tested according to the approved load-test procedure. The 3701U Building is located in the 300 Area of the Hanford Site and has the following characteristics: Roof deck--metal decking supported by steel purlins; Roof membrane--tar and gravel; Roof slope--flat (<10 deg); and Roof elevation--height of about 12.5 ft. The 3701U Building was visited in August 1992 for a visual inspection, but because of insulation an inspection could not be performed. The building was revisited in March 1994 for the purpose of writing this test report. Because the roof could not be inspected, a test was determined to be the best way to qualify the roof for personnel access. The test procedure called for the use of a remotely-controlled robot. The conclusions are that the roof has been qualified for 500-lb total roof load and that the ''No Roof Access'' signs can be changed to ''Roof Access Restricted'' signs

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

J. L. Smith

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Smith, J. L.

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS)

Non-Destructive Testing for Building Diagnostics and Monitoring: Experience Achieved with Case Studies

Directory of Open Access Journals (Sweden)

Tavukçuoğlu Ayşe

2018-01-01

Full Text Available Building inspection on site, in other words in-situ examinations of buildings is a troublesome work that necessitates the use of non-destructive investigation (NDT techniques. One of the main concerns of non-destructive testing studies is to improve in-situ use of NDT techniques for diagnostic and monitoring studies. The quantitative infrared thermography (QIRT and ultrasonic pulse velocity (UPV measurements have distinct importance in that regard. The joint use of QIRT and ultrasonic testing allows in-situ evaluation and monitoring of historical structures and contemporary ones in relation to moisture, thermal, materials and structural failures while the buildings themselves remain intact. For instances, those methods are useful for detection of visible and invisible cracks, thermal bridges and damp zones in building materials, components and functional systems as well as for soundness assessment of materials and thermal performance assessment of building components. In addition, those methods are promising for moisture content analyses in materials and monitoring the success of conservation treatments or interventions in structures. The in-situ NDT studies for diagnostic purposes should start with the mapping of decay forms and scanning of building surfaces with infrared images. Quantitative analyses are shaped for data acquisition on site and at laboratory from representative sound and problem areas in structures or laboratory samples. Laboratory analyses are needed to support in-situ examinations and to establish the reference data for better interpretation of in situ data. Advances in laboratory tests using IRT and ultrasonic testing are guiding for in-situ materials investigations based on measurable parameters. The knowledge and experience on QIRT and ultrasonic testing are promising for the innovative studies on today’s materials technologies, building science and conservation/maintenance practices. Such studies demand a multi

The Pacific Marine Energy Center - South Energy Test Site (PMEC-SETS)

Energy Technology Data Exchange (ETDEWEB)

Batten, Belinda [Oregon State Univ., Corvallis, OR (United States); Hellin, Dan [Oregon State Univ., Corvallis, OR (United States)

2018-02-07

The overall goal of this project was to build on existing progress to establish the Pacific Marine Energy Center South Energy Test Site (PMEC-SETS) as the nation's first fully permitted test site for wave energy converter arrays. Specifically, it plays an essential role in reducing levelized cost of energy for the wave energy industry by providing both the facility and resources to address the challenges of cost reduction.

25 CFR 214.28 - Location of sites for mines and buildings.

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Location of sites for mines and buildings. 214.28 Section... and buildings. In event of disagreement between two or more mineral lessees regarding sites for the location of wells, mines, buildings, plants, etc., the same shall be determined by the superintendent after...

European Diversity : A Building Site Experience

NARCIS (Netherlands)

Chao-Duivis, M.A.B.; Lang, M.; Garcés, J.; Dekker, E.; Ruben, P.A.

2016-01-01

Dutch and French construction law show fundamentally different approaches. This internship report aims to illustrate the impact which legislation has on building site interactions. Part of the research was a 5 week internship for Garcés-de Seta-Bonet, the Catalan architect office awarded with the

Reducing Building HVAC Costs with Site-Recovery Energy

Science.gov (United States)

Pargeter, Stephen J.

2012-01-01

Building owners are caught between two powerful forces--the need to lower energy costs and the need to meet or exceed outdoor air ventilation regulations for occupant health and comfort. Large amounts of energy are wasted each day from commercial, institutional, and government building sites as heating, ventilation, and air conditioning (HVAC)…

Pattern of accidents in building construction sites in Obio Akpor ...

African Journals Online (AJOL)

Background: Building construction workers are engaged in a dangerous job, exposing them ... The leading cause building site accidents include falls from unsafe working ... Data collected in Excel spread sheet were analyzed and presented in ...

On-Site Renewable Energy and Green Buildings: A System-Level Analysis.

Science.gov (United States)

Al-Ghamdi, Sami G; Bilec, Melissa M

2016-05-03

Adopting a green building rating system (GBRSs) that strongly considers use of renewable energy can have important environmental consequences, particularly in developing countries. In this paper, we studied on-site renewable energy and GBRSs at the system level to explore potential benefits and challenges. While we have focused on GBRSs, the findings can offer additional insight for renewable incentives across sectors. An energy model was built for 25 sites to compute the potential solar and wind power production on-site and available within the building footprint and regional climate. A life-cycle approach and cost analysis were then completed to analyze the environmental and economic impacts. Environmental impacts of renewable energy varied dramatically between sites, in some cases, the environmental benefits were limited despite the significant economic burden of those renewable systems on-site and vice versa. Our recommendation for GBRSs, and broader policies and regulations, is to require buildings with higher environmental impacts to achieve higher levels of energy performance and on-site renewable energy utilization, instead of fixed percentages.

Building a sense of virtual community: the role of the features of social networking sites.

Science.gov (United States)

Chen, Chi-Wen; Lin, Chiun-Sin

2014-07-01

In recent years, social networking sites have received increased attention because of the potential of this medium to transform business by building virtual communities. However, theoretical and empirical studies investigating how specific features of social networking sites contribute to building a sense of virtual community (SOVC)-an important dimension of a successful virtual community-are rare. Furthermore, SOVC scales have been developed, and research on this issue has been called for, but few studies have heeded this call. On the basis of prior literature, this study proposes that perceptions of the three most salient features of social networking sites-system quality (SQ), information quality (IQ), and social information exchange (SIE)-play a key role in fostering SOVC. In particular, SQ is proposed to increase IQ and SIE, and SIE is proposed to enhance IQ, both of which thereafter build SOVC. The research model was examined in the context of Facebook, one of the most popular social networking sites in the world. We adopted Blanchard's scales to measure SOVC. Data gathered using a Web-based questionnaire, and analyzed with partial least squares, were utilized to test the model. The results demonstrate that SIE, SQ, and IQ are the factors that form SOVC. The findings also suggest that SQ plays a fundamental role in supporting SIE and IQ in social networking sites. Implications for theory, practice, and future research directions are discussed.

Empirical evidence for site coefficients in building code provisions

Science.gov (United States)

Borcherdt, R.D.

2002-01-01

Site-response coefficients, Fa and Fv, used in U.S. building code provisions are based on empirical data for motions up to 0.1 g. For larger motions they are based on theoretical and laboratory results. The Northridge earthquake of 17 January 1994 provided a significant new set of empirical data up to 0.5 g. These data together with recent site characterizations based on shear-wave velocity measurements provide empirical estimates of the site coefficients at base accelerations up to 0.5 g for Site Classes C and D. These empirical estimates of Fa and Fnu; as well as their decrease with increasing base acceleration level are consistent at the 95 percent confidence level with those in present building code provisions, with the exception of estimates for Fa at levels of 0.1 and 0.2 g, which are less than the lower confidence bound by amounts up to 13 percent. The site-coefficient estimates are consistent at the 95 percent confidence level with those of several other investigators for base accelerations greater than 0.3 g. These consistencies and present code procedures indicate that changes in the site coefficients are not warranted. Empirical results for base accelerations greater than 0.2 g confirm the need for both a short- and a mid- or long-period site coefficient to characterize site response for purposes of estimating site-specific design spectra.

Building and Testing with Gradle

CERN Document Server

Berglund, Tim

2011-01-01

Build and test software written in Java and many other languages with Gradle, the open source project automation tool that's getting a lot of attention. This concise introduction provides numerous code examples to help you explore Gradle, both as a build tool and as a complete solution for automating the compilation, test, and release process of simple and enterprise-level applications. Discover how Gradle improves on the best ideas of Ant, Maven, and other build tools, with standards for developers who want them and lots of flexibility for those who prefer less structure. Use Gradle with Gr

3D modeling of buildings outstanding sites

CERN Document Server

Héno, Rapha?le

2014-01-01

Conventional topographic databases, obtained by capture on aerial or spatial images provide a simplified 3D modeling of our urban environment, answering the needs of numerous applications (development, risk prevention, mobility management, etc.). However, when we have to represent and analyze more complex sites (monuments, civil engineering works, archeological sites, etc.), these models no longer suffice and other acquisition and processing means have to be implemented. This book focuses on the study of adapted lifting means for "notable buildings". The methods tackled in this book cover las

Blasting jobs on the building site of the Temelin nuclear power plant

International Nuclear Information System (INIS)

Voda, J.; Podel, R.

1984-01-01

The problems are discussed of the preparation and implementation on the Temelin nuclear power plant building site of blasting, the volume of drilling and the choice of the drill hammer - all based on experience gained during the construction of the Mochovce nuclear power plant. The amount of explosives used on the Temelin site will be 1400 t. The use of mechanical charging may shorten the preparation of the site by 20 to 30%. Explosive emulsion slurries are being developed from home raw materials whose application will reduce the volume of drilling by 15%. The method of controlled breaking secures adequate quality of peripheral walls and bottom chink but special explosives will have to be used. Seismic effects are discussed of blasting on dwellings, agricultural and industrial buildings in the vicinity of the site, on-site buildings, underground mains and special structures of the nuclear power plant. (E.S.)

Load test of the 277W Building high bay roof deck and support structure

International Nuclear Information System (INIS)

McCoy, R.M.

1994-01-01

The 277W Building high bay roof area was load tested according to the approved load-test procedure, WHC-SD-GN-TP-30015, Revision 1. The 277W Building is located in the 200 West Area of the Hanford Site and has the following characteristics: roof deck -- wood decking supported by 4 x 14 timber purlins; roof membrane -- tar and gravel; roof slope -- flat (<10 deg); and roof elevation -- maximum height of about 63 ft. The 227W Building was visited in March 1994 for a visual inspection. During this inspection, cracked areas were visible in the decking, but it was not possible to determine whether these cracks extended completely through the decking, which is 2-in. thick. The building was revisited in March 1994 for the purpose of writing this test report. Because the roof requires personnel access, a test was determined to be the best way to qualify the roof. The conclusions are that the roof has been qualified for 500-lb total roof load and that the ''No Roof Access'' signs can be changed to ''Roof Access Restricted'' signs

Weldon Spring Site Remedial Action Project approach to building dismantlement and demolition

Energy Technology Data Exchange (ETDEWEB)

Spittler, F.J.

1996-01-01

When remediation began at the Weldon Spring Site Remedial Action Project (WSSRAP), there were 41 buildings on site. Twenty-nine of these buildings were ancillary structures and were not used for processing radioactive material. Most of these have been torn down. The remaining 12 buildings were used for uranium and thorium processing or were major support structures, such as the laboratory. Two of the buildings were major processing operations occurred were successfully demolished in February of this year. Demolition of all structures will be complete in September of this year. To give an understanding of the magnitude of the work, the following is a description of the physical characteristics of the green salt building. This building was used to convert brown oxide (UO3) to green salt (UF4), which is the last intermediate step in purifying the mostly yellow cake feed material into uranium metal.

Weldon Spring Site Remedial Action Project approach to building dismantlement and demolition

International Nuclear Information System (INIS)

Spittler, F.J.

1996-01-01

When remediation began at the Weldon Spring Site Remedial Action Project (WSSRAP), there were 41 buildings on site. Twenty-nine of these buildings were ancillary structures and were not used for processing radioactive material. Most of these have been torn down. The remaining 12 buildings were used for uranium and thorium processing or were major support structures, such as the laboratory. Two of the buildings were major processing operations occurred were successfully demolished in February of this year. Demolition of all structures will be complete in September of this year. To give an understanding of the magnitude of the work, the following is a description of the physical characteristics of the green salt building. This building was used to convert brown oxide (UO3) to green salt (UF4), which is the last intermediate step in purifying the mostly yellow cake feed material into uranium metal

Seismic analysis of the mirror fusion test facility building

International Nuclear Information System (INIS)

Coats, D.W.

1978-01-01

This report describes a seismic analysis of the present Mirror Fusion Test Facility (MFTF) building at the Lawrence Livermore Laboratory. The analysis was conducted to evaluate how the structure would withstand the postulated design-basis earthquake (DBE). We discuss the methods of analysis used and results obtained. Also presented are a detailed description of the building, brief discussions of site geology, seismicity, and soil conditions, the approach used to postulate the DBE, and two methods for incorporating the effects of ductility. Floor spectra for the 2nd, 3rd, and 4th floors developed for preliminary equipment design are also included. The results of the analysis, based on best-estimate equipment loadings, indicate additional bracing and upgrading of connection details are required for the structure to survive the postulated design-basis earthquake. Specific recommendations are made

Terrain and building effects on the transport of radioactive material at a nuclear site

International Nuclear Information System (INIS)

Jeong, Hyojoon; Park, Misun; Jeong, Haesun; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

2014-01-01

Highlights: • This study is to quantify the building and terrain effects on the atmospheric dispersion. • Statistical methods with AERMOD-PRIME and CFD were used. • To assess the risk in nuclear power plants, terrain and building effects have to be considered. - Abstract: This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects

305 Building Cold Test Facility Management Plan

International Nuclear Information System (INIS)

Whitehurst, R.

1994-01-01

This document provides direction for the conduct of business in Building 305 for cold testing tools and equipment. The Cold Test Facility represents a small portion of the overall building, and as such, the work instructions already implemented in the 305 Building will be utilized. Specific to the Cold Test there are three phases for the tools and equipment as follows: 1. Development and feature tests of sludge/fuel characterization equipment, fuel containerization equipment, and sludge containerization equipment to be used in K-Basin. 2. Functional and acceptance tests of all like equipment to be installed and operated in K-Basin. 3. Training and qualification of K-Basin Operators on equipment to be installed and operated in the Basin

Researching for sustained translation from site cluster permeability into building courtyard and interior atrium

Science.gov (United States)

Teddy Badai Samodra, FX; Defiana, Ima; Setyawan, Wahyu

2018-03-01

Many previous types of research have discussed the permeability of site cluster. Because of interaction and interconnected attribute, it will be better that there is its translation into lower context such as building and interior scale. In this paper, the sustainability design performance of both similar designs of courtyard and atrium are investigated continuing the recommendation of site space permeability. By researching related literature review and study through Ecotect Analysis and Ansys Fluent simulations, the pattern transformation and optimum courtyard and atrium design could comply the requirement. The results highlighted that the air movement from the site could be translated at the minimum of 50% higher to the building and indoor environment. Thus, it has potency for energy efficiency when grid, loop, and cul-de-sac site clusters, with 25% of ground coverage, have connectivity with building courtyard compared to the atrium. Energy saving is higher when using low thermal transmittance of transparent material and its lower area percentages for the courtyard walls. In general, it was more energy efficient option as part of a low rise building, while the courtyard building performed better with increasing irregular building height more than 90% of the difference.

Using Joomla Building Powerful and Efficient Web Sites

CERN Document Server

Severdia, Ron

2010-01-01

Why use Joomla? Because with Joomla you don't need to have any technical expertise or web design experience to create effective websites and web apps. Whether you're creating your first website or building a multi-function site for a client, this book provides straightforward, hands-on instruction that makes it easy to learn this open source web content management system. Written by members of the Joomla Leadership Team, Using Joomla helps newcomers quickly learn the basics, while developers with Joomla experience will pick up best practices for building more sophisticated websites. You'll a

The main demands and criteria for building site choice for radioactive waste repositories

International Nuclear Information System (INIS)

Angelova, R.; Sandul, G.A.; Sen'ko, T.Ya.

2002-01-01

There are considered the main demands of building site choice for RAW repositories. At this the accent is placed on geological repositories (underground repositories of geological type) and near surface repositories assigned to disposal of low- and intermediate-level short- and mediate-lived radionuclides. These demands are conditionally separated into two blocks: account of social development of the adjoining territories; account of natural factors characterizing building site. Further there are discussed the questions of anthropogenous influence on a safety functioning of RAW repositories and of urgency of stable development of the adjoining territories. In context of the Ukrainian and other states nuclear laws there is also considered the lawful aspect defining the building site choice for RAW repositories

ANALYSIS OF SUFFICIENCY OF THE BEARING CAPACITY OF BUILDING STRUCTURES OF OPERATING SITES OF MAIN BUILDINGS OF THERMAL POWER PLANTS

Directory of Open Access Journals (Sweden)

Alekseeva Ekaterina Leonidovna

2012-10-01

Full Text Available Upon examination of eleven main buildings of power plants, analysis of defects and damages of building structures was performed. Thereafter, the damageability of principal bearing structures of main buildings of thermal plants was analyzed. It was identified that the fastest growing defects and damages were concentrated in the structures of operating sites. The research of the rate of development of the most frequent damages and defects made it possible to conclude that internal corrosion of the reinforcing steel was the most dangerous defect, as far as the reinforced concrete elements of operating sites were concerned. Methods of mathematical statistics were applied to identify the reinforcing steel development pattern inside reinforced concrete elements of floors of operating sites. It was identified that the probability of corrosion of reinforced concrete elements of operating sites was distributed in accordance with the demonstrative law. Based on these data, calculation of strength of reinforced concrete slabs and metal beams was performed in terms of their regular sections, given the natural loads and the realistic condition of structures. As a result, dependence between the bearing capacity reserve ratio and the corrosion development pattern was identified for reinforced concrete slabs and metal beams of operating sites. In order to analyze the sufficiency of the bearing capacity of building structures of operating sites in relation to their time in commission, equations were derived to identify the nature of dependence between the sufficiency of the bearing capacity of reinforced concrete slabs and metal beams of the operating sites and their time in commission.

Open-field test site

Science.gov (United States)

Gyoda, Koichi; Shinozuka, Takashi

1995-06-01

An open-field test site with measurement equipment, a turn table, antenna positioners, and measurement auxiliary equipment was remodelled at the CRL north-site. This paper introduces the configuration, specifications and characteristics of this new open-field test site. Measured 3-m and 10-m site attenuations are in good agreement with theoretical values, and this means that this site is suitable for using 3-m and 10-m method EMI/EMC measurements. The site is expected to be effective for antenna measurement, antenna calibration, and studies on EMI/EMC measurement methods.

Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies

International Nuclear Information System (INIS)

Lacommare, Kristina S H; Stadler, Michael; Aki, Hirohisa; Firestone, Ryan; Lai, Judy; Marnay, Chris; Siddiqui, Afzal

2008-01-01

The addition of storage technologies such as flow batteries, conventional batteries, and heat storage can improve the economic as well as environmental attractiveness of on-site generation (e.g., PV, fuel cells, reciprocating engines or microturbines operating with or without CHP) and contribute to enhanced demand response. In order to examine the impact of storage technologies on demand response and carbon emissions, a microgrid's distributed energy resources (DER) adoption problem is formulated as a mixed-integer linear program that has the minimization of annual energy costs as its objective function. By implementing this approach in the General Algebraic Modeling System (GAMS), the problem is solved for a given test year at representative customer sites, such as schools and nursing homes, to obtain not only the level of technology investment, but also the optimal hourly operating schedules. This paper focuses on analysis of storage technologies in DER optimization on a building level, with example applications for commercial buildings. Preliminary analysis indicates that storage technologies respond effectively to time-varying electricity prices, i.e., by charging batteries during periods of low electricity prices and discharging them during peak hours. The results also indicate that storage technologies significantly alter the residual load profile, which can contribute to lower carbon emissions depending on the test site, its load profile, and its adopted DER technologies

A Five-Year School Building and Future Sites Program 1966-1970.

Science.gov (United States)

1965

Five-year school building and site needs and related financial requirements are summarized for Milwaukee's schools. Educational policies concerning the school building program are stated, and consideration is given to factors affecting school board needs such as birth rate, public housing projects, urban renewal, highways, and expressways. School…

Studies of tritium dispersion around and close to the buildings on the JET site

International Nuclear Information System (INIS)

Caldwell-Nichols, C.J.

1995-01-01

The dispersion of gases released to the environment at significant distances from the release point can be predicted using propriety computer codes. However during and after the Preliminary Tritium Experiment 1,2 (PTE) at JET in 1991 comparatively high levels of tritium were measured around the buildings and also there was measurable uptake of tritium in the site cooling water. Better assessment of likely tritium concentrations resulting from discharges is required to determine if tritium would tend to concentrate close to the buildings due to the complex air flow patterns around them. Three methods have been considered, namely computational studies, wind tunnel testing and tracer release experiments. A graduated approach has been adopted as each method has its limitations, tracer experiments being particularly expensive. Computational studies indicate that under worst case conditions the maximum ground level concentrations (Bq/m.) per unit stack release rate (Bq/s) is 1.0E-4 but more generally less. The results are presented noting the limitations of this approach. To aid understanding and verify some of the results, wind tunnel tests on a model of the JET site have been undertaken and the results discussed. The need for tracer release studies is considered. 3 refs., 6 figs

On-site experimental dynamic analysis for evaluating the soil-structure interaction and the seismic behaviour of the Italian PEC fast reactor building

International Nuclear Information System (INIS)

Casirati, M.; Castoldi, A.; Panzeri, P.; Pezzoli, P.; Martelli, A.; Masoni, P.; Brancati, V.

1988-01-01

The paper describes the on-site dynamic tests carried out on the PEC fast reactor building, using various excitation methods (two eccentric back-rotating-mass mechanical vibrator, blasting in bore-hole, hydraulic actuators at the building foundations). It points out the purposes of the four tests campaigns performed at various construction stages and reports the main experimental results. These results concern both the design safety margins and the data for the validation of the three-dimensional numerical model of the reactor building, including soil-structure interaction phenomena. (author)

Bioinjection Performance Review for the Building 100 Area and 4.5 Acre Site at the Pinellas County, Florida, Site

Energy Technology Data Exchange (ETDEWEB)

Survochak, Scott [US Department of Energy, Washington, DC (United States). Office of Legacy Management; Daniel, Joe [Navarro Research and Engineering, Oak Ridge, TN (United States)

2016-05-01

This document provides a summary of a review of the performance of bioinjection activities at the Building 100 Area and the 4.5 Acre Site at the Pinellas County, Florida, Site since 2010, determines how best to optimize future injection events, and identifies the approach for the bioinjection event in 2016 at (1) the 4.5 Acre Site and (2) the Essentra property at the Building 100 Area. Because this document describes the next bioinjection event at the 4.5 Acre Site, it also serves as an addendum to the Interim Remedial Action Plan for Emulsified Edible Oil Injection at the 4.5 Acre Site (DOE 2013). In addition, this document revises the injection layout and injection intervals for the Essentra property that were originally described in the Interim Corrective Measure Work Plan for Source and Plume Treatment at the Building 100 Area (DOE 2014), and is a de facto update of that document. Bioinjection consists of injection of emulsified vegetable oil (EVO) and the microorganism Dehalococcoides mccartyi (DHM; formerly known as Dehalococcoides ethenogenes) into the subsurface to enhance biodegradation of trichloroethene (TCE), dichloroethene (DCE), and vinyl chloride (VC). VC is the only contaminant that exceeds its maximum contaminant level (10 micrograms per liter onsite and 1 microgram per liter onsite) on the 4.5 Acre Site and the Essentra property. Bioinjection was conducted at the 4.5 Acre Site in 2010 and 2013. Approximately 49,900 gallons of EVO and DHM were injected at 95 injection points in February 2010, and approximately 22,900 gallons of EVO and DHM were injected at 46 injection points in July 2013. The injection locations are shown on Figure 1. The goal of bioinjection at the 4.5 Acre Site is to decrease contaminant concentrations to maximum contaminant levels along the west and southwest property boundaries (to meet risk–based corrective action requirements) and to minimize the extent of the contaminant plume in the interior of the site. Bioinjection was

Field Measurements of PCB emissions from Building Surfaces Using a New Portable Emission Test Cell

DEFF Research Database (Denmark)

Lyng, Nadja; Haven, Rune; Gunnarsen, Lars Bo

2016-01-01

The purpose of the study was to measure PCB-emission rates from indoor surfaces on-site in contaminated buildings using a newly developed portable emission test cell. Emission rates were measured from six different surfaces; three untreated surfaces and three remediated surfaces in a contaminated...

GES [Ground Engineering System] test site preparation

International Nuclear Information System (INIS)

Cox, C.M.; Mahaffey, M.K.; Miller, W.C.; Schade, A.R.; Toyoda, K.G.

1987-10-01

Activities are under way at Hanford to convert the 309 containment building and its associated service wing to a nuclear test facility for the Ground Engineering System (GES) test. Conceptual design is about 80% complete, encompassing facility modifications, a secondary heat transport system, a large vacuum system, a test article cell and handing system, control and data handling systems, and safety andl auxiliary systems. The design makes extensive use of existing equipment to minimize technical risk and cost. Refurbishment of this equipment is 25% complete. Cleanout of some 1000 m 3 of equipment from the earlier reactor test in the facility is 85% complete. An Environmental Assessment was prepared and revised to incorporate Department of Energy (DOE) comments. It is now in the DOE approval chain, where a Finding of No Significant Impact is expected. During the next year, definite design will be well advanced, long-lead procurements will be initiated, construction planning will be completed, an operator training plan will be prepared, and the site (preliminary) safety analysis report will be drafted

Methods of measurement and evaluation of natural radionuclide contents in buildings, at building sites, and in building materials and water

International Nuclear Information System (INIS)

1998-01-01

The recommendations should serve as guidelines for specifying the scope of measurement and ways of evaluating the measuring results when satisfying the relevant requirements laid down by the Czech Atomic Act (Act No. 18/1997) and Decree No. 184/1997 in the field of natural radiation sources occurring in the environment without deliberate use. The document consists of the following sections: Methodology for the measurement and assessment of natural exposure of persons in dwelling rooms of buildings; Methodology of determination of the radon risk of building sites; Principles of systematic measurement and evaluation of natural radionuclide contents of building materials; and Principles of systematic measurement and evaluation of natural radionuclide contents of supplied water. (P.A.)

Test Method for Rheological Behavior of Mortar for Building Work

Directory of Open Access Journals (Sweden)

Korobko Bogdan

2017-09-01

Full Text Available This paper offers a test method for rheological behavior of mortars with different mobility and different composition, which are used for execution of construction work. This method is based on investigation of the interaction between the valve ball and the mortar under study and allows quick defining of experimental variables for any composition of building mortars. Certain rheological behavior will permit to calculate the design parameters of machines for specific conditions of work performance – mixing (pre-operation, pressure generation, pumping to the work site, workpiece surfacing.

Postirradiation Testing Laboratory (327 Building)

Energy Technology Data Exchange (ETDEWEB)

Kammenzind, D.E.

1997-05-28

A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompass health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct

Load test of the 272E Building high bay roof deck and support structure

International Nuclear Information System (INIS)

McCoy, R.M.

1994-01-01

The 272E Building high bay roof area was load tested according to the approved load-test procedure. The 272E Building is located in the 200 East Area of the Hanford Site and has the following characteristics: Roof deck -- wood decking supported by 4 x 14 timber purlins; Roof membrane -- tar and gravel; Roof slope -- flat (<10 deg); and Roof elevation -- maximum height of about 63 ft. The 272 Building was visited in August 1992 for a visual inspection. During this inspection, cracked areas were visible in the decking, but it was not possible to determine whether these cracks extended completely through the decking, which is 2-in. thick. The building was revisited in March 1994 for the purpose of writing this test report. Because the roof requires personnel access, a test was determine to be the best way to qualify the roof. The pre-test briefing consisted of filling out the pre-test checklist, discussing proper lifting techniques, reviewing the fall-protection plan, reviewing the job hazards analysis, and reviewing the robot travel path. The load-test results consist of visual observations and the test engineer's conclusions. Visual observations found no adverse conditions such as large deflections or permanent deformations. No deflection measurements were recorded because the tar and gravel on roof get displaced by the robot tracks; the result is large variations in deflection measurements. The conclusions are that the roof has been qualified for 500-lb total roof load and that the ''No Roof Access'' signs can be changed to ''Roof Access Restricted'' signs

Resource Conservation and Recovery Act industrial site environmental restoration site characterization plan: Area 23, Building 650 Leachfield

International Nuclear Information System (INIS)

1997-03-01

This plan presents the strategy for the characterization of Corrective Action Unit 94, Area 23, Building 650 Leachfield. It is a land disposal unit, located southeast of Building 650, that was in operation from 1965 to October 1992, with an estimated annual discharge rate of less than 984 liters from designated sinks, floor drains, and emergency decontamination showers in Building 650. The objectives of the planned activities are to: obtain sufficient sample analytical data from which further assessment, remediation, and/or closure strategies may be developed for the site: and obtain sufficient sample analytical data for management of investigation-derived waste (IDW). All references to regulations in this plan are to the versions of the regulations that are current at the time of publication of this plan. The scope of the characterization will include subsurface soil boring (i.e., drilling), in situ sampling of the soil within subsurface soil borings, and sample analysis for both site characterization and waste management purposes

Preoperational test report, vent building ventilation system

International Nuclear Information System (INIS)

Clifton, F.T.

1997-01-01

This represents a preoperational test report for Vent Building Ventilation Systems, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system provides Heating, Ventilation, and Air Conditioning (HVAC) for the W-030 Ventilation Building. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System

Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Corrective Action Unit (CAU) 543: Liquid Disposal Units is listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO) which was agreed to by the state of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). CAU 543 sites are located in Areas 6 and 15 of the Nevada Test Site (NTS), which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven Corrective Action Sites (CASs) (Figure 1): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; and CAS 15-23-03, Contaminated Sump, Piping. All Area 15 CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm, which operated from 1963 to 1981 and was used to support animal experiments involving the uptake of radionuclides. Each of the Area 15 CASs, except CAS 15-23-01, is associated with the disposal of waste effluent from Building 15-06, which was the primary location of the various tests and experiments conducted onsite. Waste effluent disposal from Building 15-06 involved piping, sumps, outfalls, a septic tank with leachfield, underground storage tanks, and an aboveground storage tank (AST). CAS 15-23-01 was associated with decontamination activities of farm equipment potentially contaminated with radiological constituents, pesticides, and herbicides. While the building structures were removed before the investigation took place, all the original tanks, sumps, piping, and concrete building pads remain in place. The Area 6 CAS is located at the Decontamination Facility in Area 6, a facility which operated from 1971 to 2001 and was used to decontaminate vehicles, equipment, clothing, and other materials that had become contaminated during nuclear testing activities. The CAS includes the effluent collection and distribution systems for Buildings

Computer-Based Testing: Test Site Security.

Science.gov (United States)

Rosen, Gerald A.

Computer-based testing places great burdens on all involved parties to ensure test security. A task analysis of test site security might identify the areas of protecting the test, protecting the data, and protecting the environment as essential issues in test security. Protecting the test involves transmission of the examinations, identifying the…

Environmental Assessment and Finding of No Significant Impact: The Nevada Test Site Development Corporations's Desert Rock Sky Park at the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

N/A

2000-03-01

The United States Department of Energy has prepared an Environmental Assessment (DOE/EA-1300) (EA) which analyzes the potential environmental effects of developing operating and maintaining a commercial/industrial park in Area 22 of the Nevada Test Site, between Mercury Camp and U.S. Highway 95 and east of Desert Rock Airport. The EA evaluates the potential impacts of infrastructure improvements necessary to support fill build out of the 512-acre Desert Rock Sky Park. Two alternative actions were evaluated: (1) Develop, operate and maintain a commercial/industrial park in Area 22 of the Nevada Test Site, and (2) taking no action. The purpose and need for the commercial industrial park are addressed in Section 1.0 of the EA. A detailed description of the proposed action and alternatives is in section 2.0. Section 3.0 describes the affected environment. Section 4.0 the environmental consequences of the proposed action and alternative. Cumulative effects are addressed in Section 5.0. Mitigation measures are addressed in Section 6.0. The Department of Energy determined that the proposed action of developing, operating and maintaining a commercial/industrial park in Area 22 of the Nevada Test Site would best meet the needs of the agency.

Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Obi, C.M.

2000-01-01

The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document

Flammability tests for regulation of building and construction materials

Science.gov (United States)

K. Sumathipala

2006-01-01

The regulation of building materials and products for flammability is critical to ensure the safety of occupants in buildings and other structures. The involvement of exposed building materials and products in fires resulting in the loss of human life often spurs an increase in regulation and new test methods to address the problem. Flammability tests range from those...

Test report - 241-AN-274 Caustic Pump Control Building

International Nuclear Information System (INIS)

Paintner, G.P.

1995-05-01

This Acceptance Test Report documents the test results of test procedure WHC-SD-WM-ATP-135 'Acceptance Test Procedure for the 241-AN- 274 Caustic Pump Control Building.' The objective of the test was to verify that the 241-AN-274 Caustic Pump Control Building functions properly based on design specifications per applicable H-2-85573 drawings and associated ECN's. The objective of the test was met

Underground Nuclear Testing Program, Nevada Test Site

International Nuclear Information System (INIS)

1975-09-01

The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

Building virtual pentesting labs for advanced penetration testing

CERN Document Server

Cardwell, Kevin

2014-01-01

Written in an easy-to-follow approach using hands-on examples, this book helps you create virtual environments for advanced penetration testing, enabling you to build a multi-layered architecture to include firewalls, IDS/IPS, web application firewalls, and endpoint protection, which is essential in the penetration testing world. If you are a penetration tester, security consultant, security test engineer, or analyst who wants to practice and perfect penetration testing skills by building virtual pen testing labs in varying industry scenarios, this is the book for you. This book is ideal if yo

Problems Related to the Siting of the Laboratory Building for Civil Engineering Department at the University of Warmia and Mazury in Olsztyn, Poland

Science.gov (United States)

Zagroba, Marek

2016-10-01

This paper deals with the conditions underlying and the problems arising from the siting of a building with specialist laboratories in a developed part of the university campus in Olsztyn, Poland. The topography of the terrain and the need to house civil engineering laboratories in the planned building had an immense impact on the shape of the building and consequently on its foundations, whose dimensions responded to the ground conditions and the specification of various loads they would have to support, including the equipment for the laboratories. The siting of a building as a step in the construction process entails several problems, which are first taken into consideration at the stage of making preliminary concept plans and are subsequently verified while working on the final construction plan. The required information included geotechnical documentation, survey of the ground conditions and the data regarding the predicted loads on the building, necessary to select the right type of foundations. All these problems grow in importance when dealing with such unique buildings like the discussed example of a laboratory building for the Civil Engineering Department, built on a site within a conservation zone on the campus of the University of Warmia and Mazury in Olsztyn, Poland. The specific character of the building and the specialist equipment with which it was to be furnished (a resistance testing machine, a 17-meter-long wave flume) necessitated a series of analyses prior to the siting of the building and selecting suitable foundations. In turn, the fact that the new building was to be erected in the conservation zone meant that collaboration with the Heritage Conservation Office had to be undertaken at the stage of making the plan and continued during the construction works. The Heritage Officer's recommendations concerning the building's shape, divisions, dimensions, materials used, etc., created a situation where the team of designers and architects had to

Description and testing of three moisture sensors for measuring surface wetness on carbonate building stones

Science.gov (United States)

See, R.B.; Reddy, M.M.; Martin, R.G.

1988-01-01

Three moisture sensors were tested as a means for determining the surface wetness on carbonate building stones exposed to conditions that produce deposition of moisture. A relative-humidity probe, a gypsum-coated circuit grid, and a limestone-block resistor were tested as sensors for determining surface wetness. Sensors were tested under laboratory conditions of constant relative humidity and temperature and also under on-site conditions of variable relative humidity and temperature for eight weeks at Newcomb, NY. Laboratory tests indicated that relative humidity alone did not cause sensors to become saturated with water. However, the rates of drying indicated by the sensors after an initial saturation were inversely related to the relative humidity. On-site testing of the relative-humidity probe and the gypsum-coated ciruit grid indicated that they respond to a diurnal wetting and drying cycle; the limestone-block resistor responded only to rainfall.

Postirradiation Testing Laboratory (327 Building)

International Nuclear Information System (INIS)

Kammenzind, D.E.

1997-01-01

A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site's or facility's mission or configuration, a change in the facility's life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompass health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct

Health and safety conditions of building maintenance sites in Nigeria

African Journals Online (AJOL)

To identify the microorganisms, bulk samples were collected on timber buildings classified as maintenance sites over the country and then identify the microorganisms available using the cultivation technique. Eight hundred and fifty nutrient and Sabouraud dextrose agar dishes were prepared. The nutrient agar dishes were ...

Streamlined approach for environmental restoration closure report for Corrective Action Unit 452: Historical underground storage tank release sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

1998-04-01

This report addresses the site characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 25-3101-1, 25-3102-3, and 25-3152-1. The sites are located within the Nevada Test Site in Area 25 at Buildings 3101, 3102, and 3152. The characterization was completed to support administrative closure of the sites. Characterization was completed using drilling equipment to delineate the extent of hydrocarbon impact. Clean closure had been previously attempted at each of these sites using backhoe equipment without success due to adjacent structures, buried utilities, or depth restrictions associated with each site. Although the depth and extent of hydrocarbon impact was determined to be too extensive for clean closure, it was verified through drilling that the sites should be closed through an administrative closure. The Nevada Administrative Code ''A Through K'' evaluation completed for each site supports that there is no significant risk to human health or the environment from the impacted soils remaining at each site

Corrective Action Decision Document/Closure Report for Corrective Action Unit 266: Area 25 Building 3124 Leachfield, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NNSA/NV

2000-02-17

This Corrective Action Decision Document/Closure Report (CADD/CR) was prepared for Corrective Action Unit (CAU) 266, Area 25 Building 3124 Leachfield, in accordance with the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 266 includes Corrective Action Site (CAS) 25-05-09. The Corrective Action Decision Document and Closure Report were combined into one report because sample data collected during the corrective action investigation (CAI) indicated that contaminants of concern (COCs) were either not present in the soil, or present at concentrations not requiring corrective action. This CADD/CR identifies and rationalizes the U.S. Department of Energy, Nevada Operations Office's recommendation that no corrective action was necessary for CAU 266. From February through May 1999, CAI activities were performed as set forth in the related Corrective Action Investigation Plan. Analytes detected during the three-stage CAI of CAU 266 were evaluated against preliminary action levels (PALs) to determine COCs, and the analysis of the data generated from soil collection activities indicated the PALs were not exceeded for total volatile/semivolatile organic compounds, total petroleum hydrocarbons, polychlorinated biphenyls, total Resource Conservation and Recovery Act metals, gamma-emitting radionuclides, isotopic uranium/plutonium, and strontium-90 for any of the samples. However, COCs were identified in samples from within the septic tank and distribution box; and the isotopic americium concentrations in the two soil samples did exceed PALs. Closure activities were performed at the site to address the COCs identified in the septic tank and distribution box. Further, no use restrictions were required to be placed on CAU 266 because the CAI revealed soil contamination to be less than the 100 millirems per year limit established by DOE Order 5400.5.

Corrective Action Decision Document/Closure Report for Corrective Action Unit 266: Area 25 Building 3124 Leachfield, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2000-01-01

This Corrective Action Decision Document/Closure Report (CADD/CR) was prepared for Corrective Action Unit (CAU) 266, Area 25 Building 3124 Leachfield, in accordance with the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 266 includes Corrective Action Site (CAS) 25-05-09. The Corrective Action Decision Document and Closure Report were combined into one report because sample data collected during the corrective action investigation (CAI) indicated that contaminants of concern (COCs) were either not present in the soil, or present at concentrations not requiring corrective action. This CADD/CR identifies and rationalizes the U.S. Department of Energy, Nevada Operations Office's recommendation that no corrective action was necessary for CAU 266. From February through May 1999, CAI activities were performed as set forth in the related Corrective Action Investigation Plan. Analytes detected during the three-stage CAI of CAU 266 were evaluated against preliminary action levels (PALs) to determine COCs, and the analysis of the data generated from soil collection activities indicated the PALs were not exceeded for total volatile/semivolatile organic compounds, total petroleum hydrocarbons, polychlorinated biphenyls, total Resource Conservation and Recovery Act metals, gamma-emitting radionuclides, isotopic uranium/plutonium, and strontium-90 for any of the samples. However, COCs were identified in samples from within the septic tank and distribution box; and the isotopic americium concentrations in the two soil samples did exceed PALs. Closure activities were performed at the site to address the COCs identified in the septic tank and distribution box. Further, no use restrictions were required to be placed on CAU 266 because the CAI revealed soil contamination to be less than the 100 millirems per year limit established by DOE Order 5400.5

New Site Coefficients and Site Classification System Used in Recent Building Seismic Code Provisions

Science.gov (United States)

Dobry, R.; Borcherdt, R.D.; Crouse, C.B.; Idriss, I.M.; Joyner, W.B.; Martin, G.R.; Power, M.S.; Rinne, E.E.; Seed, R.B.

2000-01-01

Recent code provisions for buildings and other structures (1994 and 1997 NEHRP Provisions, 1997 UBC) have adopted new site amplification factors and a new procedure for site classification. Two amplitude-dependent site amplification factors are specified: Fa for short periods and Fv for longer periods. Previous codes included only a long period factor S and did not provide for a short period amplification factor. The new site classification system is based on definitions of five site classes in terms of a representative average shear wave velocity to a depth of 30 m (V?? s). This definition permits sites to be classified unambiguously. When the shear wave velocity is not available, other soil properties such as standard penetration resistance or undrained shear strength can be used. The new site classes denoted by letters A - E, replace site classes in previous codes denoted by S1 - S4. Site classes A and B correspond to hard rock and rock, Site Class C corresponds to soft rock and very stiff / very dense soil, and Site Classes D and E correspond to stiff soil and soft soil. A sixth site class, F, is defined for soils requiring site-specific evaluations. Both Fa and Fv are functions of the site class, and also of the level of seismic hazard on rock, defined by parameters such as Aa and Av (1994 NEHRP Provisions), Ss and S1 (1997 NEHRP Provisions) or Z (1997 UBC). The values of Fa and Fv decrease as the seismic hazard on rock increases due to soil nonlinearity. The greatest impact of the new factors Fa and Fv as compared with the old S factors occurs in areas of low-to-medium seismic hazard. This paper summarizes the new site provisions, explains the basis for them, and discusses ongoing studies of site amplification in recent earthquakes that may influence future code developments.

Biogen water of the Irtysh river - the principal population health factor suffered from the nuclear test on the Semipalatinsk test site

International Nuclear Information System (INIS)

Inyushin, V.M.; Yurenkov, V.V.

2001-01-01

Authors notes, that Semipalatinsk test site activity together with other factors changes a water quality. The principal consequence of nuclear tests is build up in new cells by the 'pathogenous' water in plants, animals and human . 'Pathogenous water' is generating at steady changes of electronic strictures (spin performances) at ionizing radiation effect, radionuclides and other factors of nuclear explosions. These factors were did not known to a world-wide science. The second of very important phenomenon of nuclear explosions consequences at the Semipalatinsk test site is reduce of the hydro-plasma in the water sources the Irtysh River basin. This was proved with direct studies microcurrents density in the water as well as analysis of electronic and ionic structures with the plasma-graphic help. The water having the pathogenous memory - building up in the cells - reduces the immune status, negatively reflects on the vital functions, decreasing the resistance to unfavorable effects. It is offered for remediation of the 'pathogenous water' to use the bio-genized water as most adequate one to endogenous water of living cells. Mass usage of the bio-genized water takes out genetic consequences of nuclear explosions and increase of an immunity level. The 'Bio-genization' of the Irtysh River water is concludes a few stages

Nevada Test Site Environmental Report 2004

International Nuclear Information System (INIS)

BECHTEL NEVADA

2005-01-01

The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders

Development of software tools for supporting building clearance and site release at UKAEA

International Nuclear Information System (INIS)

Jessop, G.; Pearl, M.

2002-01-01

UKAEA sites generally have complex histories and have been subject to a diverse range of nuclear operations. Most of the nuclear reactors, laboratories, workshops and other support facilities are now redundant and a programme of decommissioning works in accordance with IAEA guidance is in progress. Decommissioning is being carried out in phases with post- operative activities, care and maintenance and care and surveillance periods between stages to allow relatively short-lived radioactivity to decay. This reduces dose levels to personnel and minimises radioactive waste production. Following on from these stages is an end point phase which corresponds to the point at which the risks to human health and the environment are sufficiently low so that the buildings / land can be released for future use. Unconditional release corresponds to meeting the requirement for 'de-licensing'. Although reaching a de-licensable end point is the desired aim for UKAEA sites, it is recognised that this may take hundreds of years for parts of some UKAEA sites, or may never be attainable at a reasonable cost to the UK taxpayer. Thus on these sites, long term risk management systems are in place to minimise the impact on health, safety and the environment. In order to manage these short, medium and long term liabilities, UKAEA has developed a number of software tools based on good practice guidance. One of these tools in particular is being developed to address building clearance and site release. This tool, IMAGES (Information Management and Geographical Information System) integrates systematic data capture, with database management and spatial assessment (through a Geographical Information System). Details of IMAGES and its applications are discussed in the paper. This paper outlines the approach being adopted by UKAEA for building and site release and the integrated software system, IMAGES, being used to capture, collate, interpret and report results. The key to UKAEA's strategy for

Double tracks test site characterization report

International Nuclear Information System (INIS)

1996-05-01

This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy's (DOE) Streamlined Approach for Environmental Restoration (SAFER)

A Framework for Fully Automated Performance Testing for Smart Buildings

DEFF Research Database (Denmark)

Markoska, Elena; Johansen, Aslak; Lazarova-Molnar, Sanja

2018-01-01

, setup of performance tests has been manual and labor-intensive and has required intimate knowledge of buildings’ complexity and systems. The emergence of the concept of smart buildings has provided an opportunity to overcome this restriction. In this paper, we propose a framework for automated......A significant proportion of energy consumption by buildings worldwide, estimated to ca. 40%, has yielded a high importance to studying buildings’ performance. Performance testing is a mean by which buildings can be continuously commissioned to ensure that they operate as designed. Historically...... performance testing of smart buildings that utilizes metadata models. The approach features automatic detection of applicable performance tests using metadata queries and their corresponding instantiation, as well as continuous commissioning based on metadata. The presented approach has been implemented...

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

A. T. Urbon

2001-09-01

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 326, Areas 6 and 27 Release Sites. This CAU is currently listed in the January 2001, Appendix III of the Federal Facilities Agreement and Consent Order (FFACO) (FFACO, 1996). CAU 326 is located on the Nevada Test Site (NTS) and consists of the following four Corrective Action Sites (CASS) (Figure 1): CAS 06-25-01--Is a rupture in an underground pipe that carried heating oil (diesel) from the underground heating oil tank (Tank 6-CP-1) located to the west of Building CP-70 to the boiler in Building CP-1 in the Area 6 Control Point (CP) compound. CAS 06-25-02--A heating oil spill that is a result of overfilling an underground heating oil tank (Tank 6-DAF-5) located at the Area 6 Device Assembly Facility (DAF). CAS 06-25-04--A release of waste oil that occurred while removing used oil to from Tank 6-619-4. Tank 6-619-4 is located northwest of Building 6-619 at the Area 6 Gas Station. CAS 27-25-01--Consists of an excavation that was created in an attempt to remove impacted stained soil from the Site Maintenance Yard in Area 27. Approximately 53.5 cubic meters (m{sup 3}) (70 cubic yards [yd{sup 3}]) of soil impacted by total petroleum hydrocarbons (TPH) and polychlorinated biphenyls (PCBs) was excavated before the excavation activities were halted. The excavation activities were stopped because the volume of impacted soil exceeded estimated quantities and budget.

Nevada Test Site Environmental Report 2004

Energy Technology Data Exchange (ETDEWEB)

BECHTEL NEVADA

2005-10-01

The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

Removal site evaluation report on Building 7602 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report for Building 7602 at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the facility pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and whether remedial site evaluations or removal actions are, therefore, required. The scope of the project included (1) a search for, and review of, readily available historical records regarding operations and use of the facility (including hazardous substance usage and existing contamination); (2) interviews with facility personnel concerning current and past practices; and (3) a brief walk-through to visually inspect the facility and identify existing hazard areas requiring maintenance actions, removal actions, or remedial evaluation. The results of the removal site evaluation indicate that areas associated with Building 7602 pose no imminent hazards requiring maintenance actions. Adequate engineering and administrative controls are in place and enforced within the facility to ensure worker and environmental protection. Current actions that are being taken to prevent further release of contamination and ensure worker safety within Building 7602 are considered adequate until decontamination and decommissioning activities begin. Given the current status and condition of Building 7602, this removal site evaluation is considered complete and terminated

Corrective action investigation plan for Corrective Action Unit Number 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

International Nuclear Information System (INIS)

1997-01-01

This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at Corrective Action Unit (CAU) Number 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (140 miles) northwest of Las Vegas, Nevada. CAU Number 423 is comprised of only one Corrective Action Site (CAS) which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (240 feet) northwest. The UDP was used between approximately 1965 and 1990 to dispose of waste fluids from the Building 03-60 automotive maintenance shop. It is likely that soils surrounding the UDP have been impacted by oil, grease, cleaning supplies and solvents as well as waste motor oil and other automotive fluids released from the UDP

Corrective action investigation plan for Corrective Action Unit Number 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-27

This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at Corrective Action Unit (CAU) Number 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (140 miles) northwest of Las Vegas, Nevada. CAU Number 423 is comprised of only one Corrective Action Site (CAS) which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (240 feet) northwest. The UDP was used between approximately 1965 and 1990 to dispose of waste fluids from the Building 03-60 automotive maintenance shop. It is likely that soils surrounding the UDP have been impacted by oil, grease, cleaning supplies and solvents as well as waste motor oil and other automotive fluids released from the UDP.

Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

G. N. Doyle

2002-02-01

Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada Test Site, Nevada; TOPICAL

International Nuclear Information System (INIS)

A. T. Urbon

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 326, Areas 6 and 27 Release Sites. This CAU is currently listed in the January 2001, Appendix III of the Federal Facilities Agreement and Consent Order (FFACO) (FFACO, 1996). CAU 326 is located on the Nevada Test Site (NTS) and consists of the following four Corrective Action Sites (CASS) (Figure 1): CAS 06-25-01-Is a rupture in an underground pipe that carried heating oil (diesel) from the underground heating oil tank (Tank 6-CP-1) located to the west of Building CP-70 to the boiler in Building CP-1 in the Area 6 Control Point (CP) compound. CAS 06-25-02-A heating oil spill that is a result of overfilling an underground heating oil tank (Tank 6-DAF-5) located at the Area 6 Device Assembly Facility (DAF). CAS 06-25-04-A release of waste oil that occurred while removing used oil to from Tank 6-619-4. Tank 6-619-4 is located northwest of Building 6-619 at the Area 6 Gas Station. CAS 27-25-01-Consists of an excavation that was created in an attempt to remove impacted stained soil from the Site Maintenance Yard in Area 27. Approximately 53.5 cubic meters (m(sup 3)) (70 cubic yards[yd(sup 3)]) of soil impacted by total petroleum hydrocarbons (TPH) and polychlorinated biphenyls (PCBs) was excavated before the excavation activities were halted. The excavation activities were stopped because the volume of impacted soil exceeded estimated quantities and budget

Care of personnel on the building site of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Kurial, P.

1984-01-01

The accommodation is described of workers on the building site of the Dukovany nuclear power plant. The quality is appraised of accommodation, catering and refreshments. There is a health care unit on site and 15 beds are reserved at the Trebic hospital for emergency cases. Trade union and youth organizations look after sports and cultural activities. (E.S.)

Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

International Nuclear Information System (INIS)

Gwin, Jeremy; Frenette, Douglas

2010-01-01

This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 - Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or ''clean,'' building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, ''Final Status Survey Plan for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201'') was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

1999-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

Environmental assessment for double tracks test site, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

1996-04-01

The U.S. Department of Energy, Nevada Operations Office (DOE/NV), with appropriate approvals from the U.S. Air Force (USAF), proposes to conduct environmental restoration operations at the Double Tracks test site located on the Nellis Air Force Range (NAFR) in Nye County, Nevada. This environmental assessment (EA) evaluates the potential environmental consequences of four alternative actions for conducting the restoration operation and of the no action alternative. The EA also identifies mitigation measures, where appropriate, designed to protect natural and cultural resources and reduce impacts to human health and safety. The environmental restoration operation at the Double Tracks test site would serve two primary objectives. First, the proposed work would evaluate the effectiveness of future restoration operations involving contamination over larger areas. The project would implement remediation technology options and evaluate how these technologies could be applied to the larger areas of contaminated soils on the Nevada Test Site (NTS), the Tonopah Test Range (TTR), and the NAFR. Second, the remediation would provide for the removal of plutonium contamination down to or below a predetermined level which would require cleanup of 1 hectare (ha) (2.5 acres), for the most likely case, or up to 3.0 ha (7.4 acres) of contaminated soil, for the upper bounding case

Assessment of the Nevada Test Site as a Site for Distributed Resource Testing and Project Plan: March 2002

Energy Technology Data Exchange (ETDEWEB)

Horgan, S.; Iannucci, J.; Whitaker, C.; Cibulka, L.; Erdman, W.

2002-05-01

The objective of this project was to evaluate the Nevada Test Site (NTS) as a location for performing dedicated, in-depth testing of distributed resources (DR) integrated with the electric distribution system. In this large scale testing, it is desired to operate multiple DRs and loads in an actual operating environment, in a series of controlled tests to concentrate on issues of interest to the DR community. This report includes an inventory of existing facilities at NTS, an assessment of site attributes in relation to DR testing requirements, and an evaluation of the feasibility and cost of upgrades to the site that would make it a fully qualified DR testing facility.

Site characterization report for Building 3515 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

International Nuclear Information System (INIS)

1994-08-01

Building 3515 at Oak Ridge National Laboratory (ORNL), also known as the Fission Product Pilot Plant, is a surplus facility in the main plant area to the east of the South Tank Farm slated for decontamination and decommissioning (D ampersand D). The building consists of two concrete cells (north and south) on a concrete pad and was used to extract radioisotopes of ruthenium, strontium, cesium, cerium, rhenium and other elements from aqueous fission product waste. Site characterization activities of the building were initiated. The objective of the site characterization was to provide information necessary for engineering evaluation and planning of D ampersand D approaches, planning for personal protection of D ampersand D workers, and estimating waste volumes from D ampersand D activities. This site characterization report documents the investigation with a site description, a summary of characterization methods, chemical and radiological sample analysis results, field measurement results, and waste volume estimates

Work plan addendum for David Witherspoon, Inc., 901 Site Building Characterization, Knoxville, Tennessee

International Nuclear Information System (INIS)

1997-01-01

This building characterization plan was developed as an addendum to the existing site characterization work plan documents, which are in Appendix B of the David Witherspoon, Inc., (DWI) preliminary remedial investigation (RI)/feasibility study (FS). All building characterization activities will be conducted in accordance with the rules of the Hazardous Substance Remedial Action Program under the direction of the Tennessee Department of Environment and Conservation, Division of Superfund (TN Rules 1200-1-3) and its implementing regulations. Additional rules of the state of Tennessee, Comprehensive Environmental Response, Compensation, and Liability Act of 1980, and the U.S. Environmental Protection Agency guidance were consulted during development of this plan. Activities at the DWI site were concerned with scrap metal processing and scrap metal resale

Site Release Report for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

International Nuclear Information System (INIS)

K.E. Rasmuson

2002-01-01

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope and aspect were chosen for comparison to

Site Release Reports for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

Energy Technology Data Exchange (ETDEWEB)

K.E. Rasmuson

2002-04-02

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope

Building a successful board-test strategy

CERN Document Server

Scheiber, Stephen

2001-01-01

Written in a clear and thoughtful style, Building a Successful Board-Test Strategy, Second Edition offers an integrated approach to the complicated process of developing the test strategies most suited to a company's profile and philosophy. This book also provides comprehensive coverage of the specifics of electronic test equipment as well as those broader issues of management and marketing that shape a manufacturer's ""image of quality.""In this new edition, the author adds still more ""war stories,"" relevant examples from his own experience, which will guide his readers in their dec

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada Test Site, Nevada, Revision 1

International Nuclear Information System (INIS)

2008-01-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. The Test Cell C (TCC) Facility is located in Area 25 of the Nevada Test Site (NTS) approximately 25 miles northwest of Mercury, Nevada (Figure 1). CAU 116 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) of 1996 (as amended February 2008) and consists of two Corrective Action Sites (CASs): (1) CAS 25-23-20, Nuclear Furnace Piping; and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 is described in the FFACO as the TCC Facility but actually includes Building 3210 and attached concrete shield wall only. CAU 116 will be closed by demolishing Building 3210, the attached concrete shield wall, and the nuclear furnace piping. In addition, as a best management practice (BMP), Building 3211 (moveable shed) will be demolished due to its close proximity to Building 3210. This will aid in demolition and disposal operations. Radiological surveys will be performed on the demolition debris to determine the proper disposal pathway. As much of the demolition debris as space allows will be placed into the Building 3210 basement structure. After filling to capacity with demolition debris, the basement structure will be mounded or capped and closed with administrative controls. Prior to beginning demolition activities and according to an approved Sampling and Analysis Plan (SAP), representative sampling of surface areas that are known, suspected, or have the potential to contain hazardous constituents such as lead or polychlorinated biphenyls (PCBs) will be performed throughout all buildings and structures. Sections 2.3.2, 4.2.2.2, 4.2.2.3, 4.3, and 6.2.6.1 address the methodologies employed that assure the solid debris placed in the basement structure will not contain contaminants of concern (COCs) above hazardous waste levels. The anticipated post

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

International Nuclear Information System (INIS)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

2005-01-01

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

Remediation of the site of a former active handling building at UKAEA- Winfrith

International Nuclear Information System (INIS)

Armitage, Jack; Brown, Nick; Cornell, Rowland; Jessop, Gareth

2007-01-01

Available in abstract form only. Full text of publication follows: Since July 2000, NUKEM Limited has been carrying out the decommissioning of the former Active Handling Building, A59 at Winfrith, Dorset, United Kingdom (UK) under contract from the nuclear site licence holder, United Kingdom Atomic Energy Authority, (UKAEA). The building contained two heavily shielded suites of caves originally used to carry out remote examination of irradiated nuclear fuel elements and other supporting facilities which have all been decontaminated ready to permit building demolition. The demolition of the building structure and the removal of one cave line was completed during 2006 and the second cave line was demolished by March 2007. The remaining operations to be completed concern removal of the building slab and remediation of underlying soils to the final end point, free for unrestricted use without planning or nuclear regulatory control. Within the building base slab there are a range of contaminated items including secondary drain pipes, filter pits, storage hole liners and ventilation ducts which all have to be recovered for disposal along with around 4,000 m 3 of surrounding concrete. In order to characterise the slab before its removal, supporting information has been obtained from site investigation work including a collimated low resolution, high sensitivity gamma survey using the GroundhogTM system of the foundation slab and the recovery and analysis of 27 cores obtained by drilling through the slab into the underlying soil. During removal of the slab it will be necessary to employ a variety of monitoring techniques to locate and remove the contaminated sections and then expose and monitor the underlying soil for evidence of any residual radioactivity. (authors)

The occupational safety on the construction sites of the farm production buildings in Finland

Directory of Open Access Journals (Sweden)

M. Hellstedt

2013-09-01

Full Text Available The size of farms has increased considerably during Finland's EU membership. The growth has meant big investments in the new production buildings. The buildings have been switched to big industrialhall- like constructions from small-scale ones which have contained own timber and own work contribution. The objective of the project financed by Farmers' Social Insurance Institution was to improve occupational safety on farm building construction and renovation sites by disseminating current safety practices and by developing ways of action which are better than the prevailing ones. The project consisted of a literature review, statistical analysis, as well as a farmer and designer interviews. In the statistical analysis the MATA occupational injuries insurance claims database on farmers’ claims during construction and renovation work for the years 2005 - 2008 was compared with the register of Federation of Accident Insurance Institutions on the construction workers' injuries. In comparing the reasons of the accidents a clear difference was found; poor scaffoldings and ladders are still the main culprits on farm accidents. Farmer interviews were used to assess occupational safety measures on the construction site, occurred injuries and their types, nearmiss situations and the underlying factors which have led to the injuries. Also construction safety deficiencies as well as the direct and indirect costs caused for instance because of the delay in completion of construction project were discussed. Designer interviews aimed to find out how occupational safety and health considerations are taken into account in farm building planning and counseling, and how this experience of the designers should be utilized in order to improve safety at the construction sites on farms. Farmers knew their obligations on occupational safety poorly. The situation was further worsened by the fact that on the site the supervisor tasks were only nominally executed. The

Nevada Test Site annual site environmental report, 1989

Energy Technology Data Exchange (ETDEWEB)

Wruble, D T; McDowell, E M [eds.

1990-11-01

Prior to 1989 annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the offsite radiological surveillance program conducted by the US Environmental Protection Agency (EPA), Environmental Monitoring Systems Laboratory, Las Vegas, Nevada, were reported separately by that Agency. Beginning with this 1989 annual Site environmental report for the NTS, these two documents are being combined into a single report to provide a more comprehensive annual documentation of the environmental protection program conducted for the nuclear testing program and other nuclear and non-nuclear activities at the Site. The two agencies have coordinated preparation of this combined onsite and offsite report through sharing of information on environmental releases and meteorological, hydrological, and other supporting data used in dose-estimate calculations. 57 refs., 52 figs., 65 tabs.

SP-100 Test Site

International Nuclear Information System (INIS)

Cox, C.M.; Mahaffey, M.K.; Miller, W.C.

1988-01-01

Preparatory activities are well under way at Hanford to convert the 309 Containment Building and its associated service wing to a 2.5 MWt nuclear test facility for the SP-100 Ground Engineering System (GES) test. Preliminary design is complete, encompassing facility modifications, a secondary heat transport system, a large vacuum system to enclose the high temperature reactor, a test assembly cell and handling system, control and data processing systems, and safety and auxiliary systems. The design makes extensive use of existing equipment to minimize technical risk and cost. Refurbishment of this equipment is 75% complete. The facility has been cleared of obstructing equipment from its earlier reactor test. Current activities are focusing on definitive design and preparation of the Preliminary Safety Analysis Report (PSAR) aimed at procurement and construction approvals and schedules to achieve reactor criticality by January 1992. 6 refs

Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2007-10-01

The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders.

Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

International Nuclear Information System (INIS)

Cathy Wills

2007-01-01

The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders

Nevada Test Site Environmental Report 2003

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada

2004-10-01

The Nevada Test Site Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada Test Site contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada Test Site Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

Build an Inexpensive Wind Tunnel to Test CO2 Cars

Science.gov (United States)

McCormick, Kevin

2012-01-01

As part of the technology education curriculum, the author's eighth-grade students design, build, test, and race CO2 vehicles. To help them in refining their designs, they use a wind tunnel to test for aerodynamic drag. In this article, the author describes how to build a wind tunnel using inexpensive, readily available materials. (Contains 1…

Non-Invasive Seismic Methods for Earthquake Site Classification Applied to Ontario Bridge Sites

Science.gov (United States)

Bilson Darko, A.; Molnar, S.; Sadrekarimi, A.

2017-12-01

How a site responds to earthquake shaking and its corresponding damage is largely influenced by the underlying ground conditions through which it propagates. The effects of site conditions on propagating seismic waves can be predicted from measurements of the shear wave velocity (Vs) of the soil layer(s) and the impedance ratio between bedrock and soil. Currently the seismic design of new buildings and bridges (2015 Canadian building and bridge codes) requires determination of the time-averaged shear-wave velocity of the upper 30 metres (Vs30) of a given site. In this study, two in situ Vs profiling methods; Multichannel Analysis of Surface Waves (MASW) and Ambient Vibration Array (AVA) methods are used to determine Vs30 at chosen bridge sites in Ontario, Canada. Both active-source (MASW) and passive-source (AVA) surface wave methods are used at each bridge site to obtain Rayleigh-wave phase velocities over a wide frequency bandwidth. The dispersion curve is jointly inverted with each site's amplification function (microtremor horizontal-to-vertical spectral ratio) to obtain shear-wave velocity profile(s). We apply our non-invasive testing at three major infrastructure projects, e.g., five bridge sites along the Rt. Hon. Herb Gray Parkway in Windsor, Ontario. Our non-invasive testing is co-located with previous invasive testing, including Standard Penetration Test (SPT), Cone Penetration Test and downhole Vs data. Correlations between SPT blowcount and Vs are developed for the different soil types sampled at our Ontario bridge sites. A robust earthquake site classification procedure (reliable Vs30 estimates) for bridge sites across Ontario is evaluated from available combinations of invasive and non-invasive site characterization methods.

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Colloid research for the Nevada Test Site

International Nuclear Information System (INIS)

Bryant, E.A.

1992-05-01

Research is needed to understand the role of particulates in the migration of radionuclides away from the sites of nuclear tests at the Nevada Test Site. The process of testing itself may produce a reservoir of particles to serve as vectors for the transport of long-lived radionuclides in groundwater. Exploratory experiments indicate the presence of numerous particulates in the vicinity of the Cambric test but a much lower loading in a nearby well that has been pumped continuously for 15 years. Recent groundwater colloid research is briefly reviewed to identify sampling and characterization methods that may be applicable at the Nevada Test Site

Ongoing research experiments at the former Soviet nuclear test site in eastern Kazakhstan

Science.gov (United States)

Leith, William S.; Kluchko, Luke J.; Konovalov, Vladimir; Vouille, Gerard

2002-01-01

Degelen mountain, located in EasternKazakhstan near the city of Semipalatinsk, was once the Soviets most active underground nuclear test site. Two hundred fifteen nuclear tests were conducted in 181 tunnels driven horizontally into its many ridges--almost twice the number of tests as at any other Soviet underground nuclear test site. It was also the site of the first Soviet underground nuclear test--a 1-kiloton device detonated on October 11, 1961. Until recently, the details of testing at Degelen were kept secret and have been the subject of considerable speculation. However, in 1991, the Semipalatinsk test site became part of the newly independent Republic of Kazakhstan; and in 1995, the Kazakhstani government concluded an agreement with the U.S. Department of Defense to eliminate the nuclear testing infrastructure in Kazakhstan. This agreement, which calls for the "demilitarization of the infrastructure directly associated with the nuclear weapons test tunnels," has been implemented as the "Degelen Mountain Tunnel Closure Program." The U.S. Defense Threat Reduction Agency, in partnership with the Department of Energy, has permitted the use of the tunnel closure project at the former nuclear test site as a foundation on which to support cost-effective, research-and-development-funded experiments. These experiments are principally designed to improve U.S. capabilities to monitor and verify the Comprehensive Test Ban Treaty (CTBT), but have provided a new source of information on the effects of nuclear and chemical explosions on hard, fractured rock environments. These new data extends and confirms the results of recent Russian publications on the rock environment at the site and the mechanical effects of large-scale chemical and nuclear testing. In 1998, a large-scale tunnel closure experiment, Omega-1, was conducted in Tunnel 214 at Degelen mountain. In this experiment, a 100-ton chemical explosive blast was used to test technologies for monitoring the

Integration and consistency testing of groundwater flow models with hydro-geochemistry in site investigations in Finland

International Nuclear Information System (INIS)

Pitkaenen, P.; Loefman, J.; Korkealaakso, J.; Koskinen, L.; Ruotsalainen, P.; Hautojaervi, A.; Aeikaes, T.

1999-01-01

In the assessment of the suitability and safety of a geological repository for radioactive waste the understanding of the fluid flow at a site is essential. In order to build confidence in the assessment of the hydrogeological performance of a site in various conditions, integration of hydrological and hydrogeochemical methods and studies provides the primary method for investigating the evolution that has taken place in the past, and for predicting future conditions at the potential disposal site. A systematic geochemical sampling campaign was started since the beginning of 1990's in the Finnish site investigation programme. This enabled the initiating of integration and evaluation of site scale hydrogeochemical and groundwater flow models. Hydrogeochemical information has been used to screen relevant external processes and variables for definition of the initial and boundary conditions in hydrological simulations. The results obtained from interpretation and modelling hydrogeochemical evolution have been employed in testing the hydrogeochemical consistency of conceptual flow models. Integration and testing of flow models with hydrogeochemical information are considered to improve significantly the hydrogeological understanding of a site and increases confidence in conceptual hydrogeological models. (author)

Testing in support of on-site storage of residues in the Pipe Overpack Container

International Nuclear Information System (INIS)

Ammerman, D.J.; Bobbe, J.G.; Arviso, M.

1997-02-01

The disposition of the large back-log of plutonium residues at the Rocky Flats Environmental Technology Site (Rocky Flats) will require interim storage and subsequent shipment to a waste repository. Current plans call for disposal at the Waste Isolation Pilot Plant (WIPP) and the transportation to WIPP in the TRUPACT-II. The transportation phase will require the residues to be packaged in a container that is more robust than a standard 55-gallon waste drum. Rocky Flats has designed the Pipe Overpack Container to meet this need. It is desirable to use this same waste packaging for interim on-site storage in non-hardened buildings. To meet the safety concerns for this storage the Pipe Overpack Container has been subjected to a series of tests at Sandia National Laboratories in Albuquerque, New Mexico. In addition to the tests required to qualify the Pipe Overpack Container as a waste container for shipment in the TRUPACT-II several tests were performed solely for the purpose of qualifying the container for interim storage. This report will describe these tests and the packages response to the tests. 12 figs., 3 tabs

Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 2

International Nuclear Information System (INIS)

1997-11-01

The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This report contains Appendix B which provides all of the laboratory summary data sheets for the Area 6 SCEPs closure activities

Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This report contains Appendix B which provides all of the laboratory summary data sheets for the Area 6 SCEPs closure activities.

Nevada Test Site Environmental Report 2007 Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

PASLINK and dynamic outdoor testing of building components

NARCIS (Netherlands)

Baker, P.H.; Dijk, H.A.L. van

2008-01-01

The PASLINK test facilities and analysis procedures aim to obtain the thermal and solar characteristics of building components under real dynamic outdoor conditions. Both the analysis and the test methodology have evolved since the start of the PASSYS Project in 1985. A programme of upgrading the

Towards Smart Buildings Performance Testing as a Service

DEFF Research Database (Denmark)

Markoska, Elena; Lazarova-Molnar, Sanja

2018-01-01

to buildings’ energy consumption. In this paper we propose a methodology for continuous performance testing of smart buildings as a service. We discuss the automatic discovery and instantiation of performance tests, as well as usage of results for discovery of potential faults and ways to improve buldings...

A Cold War Battlefield: Frenchman Flat Historic District, Nevada Test Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

Johnson, William Gray [DRI; Holz, Barbara A [DRI; Jones, Robert [DRI

2000-08-01

This report provides the U.S. Department of Energy, Nevada Operations Office with the documentation necessary to establish the Frenchman Flat Historic District on the Nevada Test Site (NTS). It includes a list of historic properties that contribute to the eligibility of the district for inclusion in the National Register of Historic Places (NRHP) and provides contextual information establishing its significance. The list focuses on buildings, structures and features associated with the period of atmospheric testing of nuclear weapons on the NTS between 1951 and 1962. A total of 157 locations of buildings and structures were recorded of which 115 are considered to be eligible for the NRHP. Of these, 28 have one or more associated features which include instrumentation supports, foundations, etc. The large majority of contributing structures are buildings built to study the blast effects of nuclear weaponry. This has resulted in a peculiar accumulation of deteriorated structures that, unlike most historic districts, is best represented by those that are the most damaged. Limitations by radiological control areas, surface exposure and a focus on the concentration of accessible properties on the dry lake bed indicate additional properties exist which could be added to the district on a case-by-case basis.

Study on the leak rate test for HANARO reactor building

International Nuclear Information System (INIS)

Choi, Y. S.; Kim, Y. K.; Kim, M. J.; Park, J. M.; Woo, J. S.

2002-01-01

The reactor building of HANARO adopts the confinement concept, which allows a certain amount of air leakage. In order to restrict the air leakage through the confinement boundary, negative pressure of at least 2.5 mmWG is maintained in normal operating condition while maintaining 25 mmWG of negative pressure in abnormal condition, the inside air filtered by a train of charcoal filter is released to the atmosphere through the stack. In this situation, if the emergency ventilation system is not operable, the reactor building is isolated from the outside then the trapped air inside will be leaked out through the building by ground release concept. As the leak rate may be affected by an effect of wind velocity outside the reactor building, the air tightness of confinement should be maintained to limit the leak rate below the allowable value. The local leak rate test method was used since the beginning of the commissioning until July 1999. However it has been pointed out as a defect that the method is so susceptible to the change of temperature and atmospheric pressure during testing. For more accurate leak rate testing, we have introduced a new test method. We have periodically carried out the new leak rate testing and the results indicate that the bad effect by the temperature and atmospheric pressure change is considerably reduced, which gives more stable leak rate measurement

Determination of hydraulic conductivity coefficient in NSD site, Serpong, based on in-situ permeability test method

International Nuclear Information System (INIS)

Heri Syaeful; Sucipta

2013-01-01

In line with the increase of amount of radioactive waste, PTLR-BATAN plans to build the Near Surface Disposal (NSD) facility, especially in the preliminary stages is the Demo Plant of NSD facility. NSD is a low to medium level radioactive waste storage concept. Most important aspect in the site study for planning NSD is hydrogeological aspect especially related to the migration of radionuclides to the environment. In the study of radionuclide migration, a preliminary parameter which is required to know is the hydraulic conductivity in order to deliver the soil and rock hydraulic conductivity values in the site then conducted the in-situ permeability test. Based on the test, obtained soil and rock hydraulic conductivity values ranging from 10 -6 to 10 -2 cm/sec. The greatest hydraulic conductivity value located in the gravelly silt soil units which is in the site, constitute as aquifer, with depth ranging from 8 - 24 m, with hydraulic conductivity value reached 10 -2 cm/sec. (author)

The nightly build and test system for LCG AA and LHCb software

CERN Document Server

Kruzelecki, K; Degaudenzi, H

2010-01-01

The core software stack both from the LCG Application Area and LHCb consists of more than 25 C++/Fortran/Python projects build for about 20 different configurations on Linux, Windows and MacOSX. To these projects, one can also add about 70 external software packages (Boost, Python, Qt, CLHEP, ...) which have also to be build for the same configurations. It order to reduce the time of the development cycle and increase the quality insurance, a framework has been developed for the daily (nightly actually) build and test of the software. Performing the build and the tests on several configurations and platform allows to increase the efficiency of the unit and integration tests. Main features: - flexible and fine grained setup (full, partial build) through a web interface; - possibility to build several “slots” with different configurations; - precise and highly granular reports on a web server; - support for CMT projects (but not only) with their cross-dependencies; - scalable client-server architecture for ...

Radiation consequences of the nuclear tests on the Semipalatinsk test site

International Nuclear Information System (INIS)

Logachev, V.A.; Logacheva, L.A.

2001-01-01

In the paper the results of retrospective evaluation for radiation situation and radiation doses of population in the zones of the Semipalatinsk test site activity influence are presented. For the measurements the data obtained during analysis, study and summarizing of the archival materials including information on nuclear tests on this site and results of radiation surveys, those were carried out after each test were used. The information testifying most substantial environment contamination taking place after four surface explosions (29.08.1949, 24.09.1951, 12.08.1953, 24.08.1956) is presented as well. After these dose-forming explosions the irradiation doses of the population inhabiting out the regime zone have been exceeded the maximum permissible levels. Results of analysis of archival materials were used for assessment of doses of internal and external irradiation of residents of inhabited points situated on the both the territory of the Republic of Kazakhstan - mainly close to the test site - and the territories of a number of regions of the Russian Federation are locating on the little distance from the tests site

Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site

International Nuclear Information System (INIS)

Bohrman, D.E.; Ingram, E.M.

1993-09-01

This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7)

Fiscal 1996 research report on the PV power generation field test project for public facilities. Evaluation and analysis of collected data for every site (1/2); 1996 nendo kokyo shisetsu nadoyo taiyoko hatsuden field test jigyo ni okeru shushu data hyoka kaiseki. Kaku site betsu (1/2)

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

As a part of the PV power generation field test project, this report summarizes the monthly collected data for every site in fiscal 1996. The test sites include various public facilities such as park, school, university, museum, Shinkansen platform, laboratory, technical center, training building, local governmental hotel, health athletic center, community center, joint purchase center, consumers' cooperative (CO-OP), school meals provision center, prefectural office building, police station garage, water purification plant, general disaster prevention center, and health center. Collected data items are as follows: total solar irradiation (kWh/m{sup 2}), average air temperature, array power, system power, load power, power system supply load, reverse power flow, self supply load (kWh for every item), system disinterconnection time (min), system operation time (min), equivalent array/system operation time, array/system performance ratio, system use factor, system generation efficiency, effective inverter efficiency, and inverter load factor. (NEDO)

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

T. M. Fitzmaurice

2001-08-01

This Streamlined Approach for Environmental restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 330, Areas 6,22, and 23 Tanks and Spill Sites. The CAUs are currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO). This CAU is located at the Nevada Test Site (NTS) (Figure 1). CAU 330 consists of the following Corrective Action Sites (CASs): (1) CAS 06-02-04 - Consists of an underground tank and piping. This CAS is close to an area that was part of the Animal Investigation Program (AIP), conducted under the U.S. Public Health Service. Its purpose was to study and perform tests on the cattle and wild animals in and around the NTS that were exposed to radionuclides. It is unknown if this tank was part of these operations. (2) CAS 22-99-06 - Is a fuel spill that is believed to be a waste oil release which occurred when Camp Desert Rock was an active facility. This CAS was originally identified as being a small depression where liquids were poured onto the ground, located on the west side of Building T-1001. This building has been identified as housing a fire station, radio station, and radio net remote and telephone switchboard. (3) CAS 23-01-02 - Is a large aboveground storage tank (AST) farm that was constructed to provide gasoline and diesel storage in Area 23. The site consists of two ASTs, a concrete foundation, a surrounding earthen berm, associated piping, and unloading stations. (4) CAS 23-25-05 - Consists of an asphalt oil spill/tar release that contains a wash covered with asphalt oil/tar material, a half buried 208-liter (L) (55-gallon [gal]) drum, rebar, and concrete located in the vicinity.

Nevada Test Site Environmental Report 2009

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

The Nevada Test Site Environmental Report 2009 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada Test Site Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada Test Site (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Streamlined approach for environmental restoration closure report for Corrective Action Unit No. 456: Underground storage tank release site 23-111-1, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

1998-04-01

The underground storage tank (UST) release site 23-111-1 is located in Mercury, Nevada. The site is in Area 23 of the Nevada Test Site, (NTS) located on the north side of Building 111. The tank associated with the release was closed in place using cement grout on September 6, 1990. The tank was not closed by removal due to numerous active underground utilities, a high-voltage transformer pad, and overhead power lines. Soil samples collected below the tank bottom at the time of tank closure activities exceeded the Nevada Administrative Code Action Level of 100 milligrams per kilogram (mg/kg) for petroleum hydrocarbons. Maximum concentrations detected were 119 mg/kg. Two passive venting wells were subsequently installed at the tank ends to monitor the progress of biodegradation at the site. Quarterly air sampling from the wells was completed for approximately one year, but was discontinued since data indicated that considerable biodegradation was not occurring at the site

Nevada Test Site Environmental Report 2009, Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

ATLAS barrel toroid integration and test area in building 180

CERN Multimedia

Maximilien Brice

2003-01-01

The ATLAS barrel toroid system consists of eight coils, each of axial length 25.3 m, assembled radially and symmetrically around the beam axis. The coils are of a flat racetrack type with two 'double-pancake' windings made of 20.5 kA aluminium-stabilized niobium-titanium superconductor. The barrel toroid is being assembled in building 180 on the Meyrin site. In the first phase of assembly, the coils are packed into their aluminium-alloy casing. These photos show the double-pancake coils from ANSALDO and the coil casings from ALSTOM. In the foreground is the tooling from COSMI used to turn over the coil casings during this first phase. In the right background is the yellow lifting gantry manufactured at JINR-Dubna, Russia which will transport the coil casings to a heating table for prestressing. Two test benches with magnetic mirror are also visible.

Conversion of Semipalatinsk test site

International Nuclear Information System (INIS)

Cherepnin, Yu. S.

1997-01-01

The conversion of the former defense enterprises of STS (Semipalatinsk Test Sate) started under very difficult conditions, when not only research and production activity, but all social life of Kurchatov city were conversed which was caused by a fast curtailment and restationing of Russian military units from the test site. A real risk of a complete destruction of the whole research and production structure of the city existed. From this point of view, the decision of the Republic of Kazakhstan Government to create the National Nuclear Center on the base of the test site research enterprises was actual and timely. During 1993, three research institutes of NNC RK - Institute of Atomic Energy, Institute of Geophysics Research and Institute of Radiation Safety and Environment were established. This decision, under conditions of the Ussr disintegration and liquidation of the test site military divisions, allowed to preserve the qualified personnel, to provide and follow-up the operation of nuclear dangerous facilities, to develop and start the realization of the full scale conversion program.At present time, directions and structure of basic research work in NNC RK are as follows: - liquidation of nuclear explosions consequences; - liquidation of technological infrastructure used for preparation and conduction of nuclear weapon testing; - creation of technology, equipment and places for acceptance and storage of radioactive wastes; - working out of atomic energy development conception in Kazakhstan; - study of reactor core melt behavior under severe accidents in NPP; - development of methods and means of nuclear testing detection, continuous monitoring of nuclear explosions; - experimental work on a study of structure materials behavior of ITER thermonuclear reactor; - creation of industries requiring a lage implementation of science

Database on radioecological situation in Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

1999-01-01

One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

Damping in building structures during earthquakes: test data and modeling

International Nuclear Information System (INIS)

Coats, D.W. Jr.

1982-01-01

A review and evaluation of the state-of-the-art of damping in building structures during earthquakes is presented. The primary emphasis is in the following areas: 1) the evaluation of commonly used mathematical techniques for incorporating damping effects in both simple and complex systems; 2) a compilation and interpretation of damping test data; and 3) an evaluation of structure testing methods, building instrumentation practices, and an investigation of rigid-body rotation effects on damping values from test data. A literature review provided the basis for evaluating mathematical techiques used to incorporate earthquake induced damping effects in simple and complex systems. A discussion on the effectiveness of damping, as a function of excitation type, is also included. Test data, from a wide range of sources, has been compiled and interpreted for buidings, nuclear power plant structures, piping, equipment, and isolated structural elements. Test methods used to determine damping and frequency parameters are discussed. In particular, the advantages and disadvantages associated with the normal mode and transfer function approaches are evaluated. Additionally, the effect of rigid-body rotations on damping values deduced from strong-motion building response records is investigated. A discussion of identification techniques typically used to determine building parameters (frequency and damping) from strong motion records is included. Finally, an analytical demonstration problem is presented to quantify the potential error in predicting fixed-base structural frequency and damping values from strong motion records, when rigid-body rotations are not properly accounted for

VS30 – A site-characterization parameter for use in building Codes, simplified earthquake resistant design, GMPEs, and ShakeMaps

Science.gov (United States)

Borcherdt, Roger D.

2012-01-01

VS30, defined as the average seismic shear-wave velocity from the surface to a depth of 30 meters, has found wide-spread use as a parameter to characterize site response for simplified earthquake resistant design as implemented in building codes worldwide. VS30 , as initially introduced by the author for the US 1994 NEHRP Building Code, provides unambiguous definitions of site classes and site coefficients for site-dependent response spectra based on correlations derived from extensive borehole logging and comparative ground-motion measurement programs in California. Subsequent use of VS30 for development of strong ground motion prediction equations (GMPEs) and measurement of extensive sets of VS borehole data have confirmed the previous empirical correlations and established correlations of SVS30 with VSZ at other depths. These correlations provide closed form expressions to predict S30 V at a large number of additional sites and further justify S30 V as a parameter to characterize site response for simplified building codes, GMPEs, ShakeMap, and seismic hazard mapping.

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 330: Areas 6, 22, and 23 Tanks and Spill Sites, Nevada Test Site, Nevada; TOPICAL

International Nuclear Information System (INIS)

T. M. Fitzmaurice

2001-01-01

This Streamlined Approach for Environmental restoration (SAFER) plan addresses the action necessary for the closure of Corrective Action Unit (CAU) 330, Areas 6,22, and 23 Tanks and Spill Sites. The CAUs are currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO). This CAU is located at the Nevada Test Site (NTS) (Figure 1). CAU 330 consists of the following Corrective Action Sites (CASs): (1) CAS 06-02-04 - Consists of an underground tank and piping. This CAS is close to an area that was part of the Animal Investigation Program (AIP), conducted under the U.S. Public Health Service. Its purpose was to study and perform tests on the cattle and wild animals in and around the NTS that were exposed to radionuclides. It is unknown if this tank was part of these operations. (2) CAS 22-99-06 - Is a fuel spill that is believed to be a waste oil release which occurred when Camp Desert Rock was an active facility. This CAS was originally identified as being a small depression where liquids were poured onto the ground, located on the west side of Building T-1001. This building has been identified as housing a fire station, radio station, and radio net remote and telephone switchboard. (3) CAS 23-01-02 - Is a large aboveground storage tank (AST) farm that was constructed to provide gasoline and diesel storage in Area 23. The site consists of two ASTs, a concrete foundation, a surrounding earthen berm, associated piping, and unloading stations. (4) CAS 23-25-05 - Consists of an asphalt oil spill/tar release that contains a wash covered with asphalt oil/tar material, a half buried 208-liter (L) (55-gallon[gal]) drum, rebar, and concrete located in the vicinity

Closure plan for Corrective Action Unit 94: Building 650 Leachfield, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

1998-03-01

The Building 650 Leachfield, Corrective Action Unit (CAU) 94, will be clean closed by removal in accordance with the Resource Conservation and Recover Act (RCRA) operational permit and the Federal Facility Agreement and Consent Order. Historically, laboratory effluent was discharged through pipelines leading from the Radiochemistry Laboratory in Building 650 to a distribution box and a series of pipes dispersed across the leachfield. Effluent from the laboratory contained both hazardous and radioactive constituents. Discharge of hazardous and radioactive waste began in 1965. Discharge of radioactive waste ended in 1979 and hazardous waste discharge ended in 1987. From 1987 to 1993 the leachfield was used for the disposal of non-hazardous waste water. The piping leading to the leachfield was sealed in 1993

Corrective Action Plan for CAU No. 95: Area 15 EPA Farm Laboratory Building, Decontamination and Demolition Closure Activities - Nevada Test Site. Rev. 0

International Nuclear Information System (INIS)

Olson, A.L.; Nacht, S.J.

1997-11-01

This Corrective Action Plan (CAP) provides the selected corrective action alternative and proposes the closure implementation methodology for the Environmental Protection Agency (EPA) Farm Laboratory Building 15-06 located in Area 15 of the Nevada Test Site (NTS), Nye County, Nevada. The facility is part of the Environmental Restoration Project managed by the U.S. Department of Energy/Nevada Operations Office (DOE/NV) under the Decontamination and Decommissioning (D ampersand D) Subproject which serves to manage and dispose of surplus facilities at the NTS in a manner that will protect personnel, the public, and the environment. It is identified as Corrective Action Unit (CAU) 95 in Appendix III of the Federal Facilities Agreement and Consent Order (FFACO). In July 1997, the DOE/NV verbally requested approval from the Nevada Division of Environmental Protection (NDEP) for the closure schedule to be accelerated. Currently, field activities are anticipated to be completed by September 30, 1997. In order to meet this new schedule NDEP has agreed to review this document as expeditiously as possible. Comments will be addressed in the Closure Report after field activities have been completed, unless significant issues require resolution during closure activities

Corrective Action Plan for CAU No. 95: Area 15 EPA Farm Laboratory Building, Decontamination and Demolition Closure Activities - Nevada Test Site. Rev. 0

Energy Technology Data Exchange (ETDEWEB)

Olson, A.L.; Nacht, S.J.

1997-11-01

This Corrective Action Plan (CAP) provides the selected corrective action alternative and proposes the closure implementation methodology for the Environmental Protection Agency (EPA) Farm Laboratory Building 15-06 located in Area 15 of the Nevada Test Site (NTS), Nye County, Nevada. The facility is part of the Environmental Restoration Project managed by the U.S. Department of Energy/Nevada Operations Office (DOE/NV) under the Decontamination and Decommissioning (D&D) Subproject which serves to manage and dispose of surplus facilities at the NTS in a manner that will protect personnel, the public, and the environment. It is identified as Corrective Action Unit (CAU) 95 in Appendix III of the Federal Facilities Agreement and Consent Order (FFACO). In July 1997, the DOE/NV verbally requested approval from the Nevada Division of Environmental Protection (NDEP) for the closure schedule to be accelerated. Currently, field activities are anticipated to be completed by September 30, 1997. In order to meet this new schedule NDEP has agreed to review this document as expeditiously as possible. Comments will be addressed in the Closure Report after field activities have been completed, unless significant issues require resolution during closure activities.

Closure report for CAU 339: Area 12 Fleet Operations steam-cleaning discharge area, Nevada Test Site

International Nuclear Information System (INIS)

1997-12-01

This Closure Report (CR) provides documentation of the completed corrective action at the Area 12 Fleet Operations site located in the southeast portion of the Area 12 Camp at the Nevada Test Site (NTS). Field work was performed in July 1997 as outlined in the Corrective Action Plan (CAP). The CAP was approved by the Nevada Division of Environmental Protection (NDEP) in June 1997. This site is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Site (CAS) Number 12-19-01 and is the only CAS in Corrective Action Unit (CAU) 339. The former Area 12 Fleet Operations Building 12-16 functioned as a maintenance facility for light- and heavy-duty vehicles from approximately 1965 to January 1993. Services performed at the site included steam-cleaning, tire service, and preventative maintenance on vehicles and equipment. Past activities impacted the former steam-cleaning discharge area with volatile organic compounds (VOCs) and total petroleum hydrocarbons (TPH) as oil

Nevada Test Site Environmental Report 2008 Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2009-09-01

This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Hanford Site Emergency Alerting System siren testing report

International Nuclear Information System (INIS)

Weidner, L.B.

1997-01-01

The purpose of the test was to determine the effective coverage of the proposed upgrades to the existing Hanford Site Emergency Alerting System (HSEAS). The upgrades are to enhance the existing HSEAS along the Columbia River from the Vernita Bridge to the White Bluffs Boat Launch as well as install a new alerting system in the 400 Area on the Hanford Site. Five siren sites along the Columbia River and two sites in the 400 Area were tested to determine the site locations that will provide the desired coverage

The nightly build and test system for LCG AA and LHCb software

International Nuclear Information System (INIS)

Kruzelecki, Karol; Roiser, Stefan; Degaudenzi, Hubert

2010-01-01

The core software stack both from the LCG Application Area and LHCb consists of more than 25 C++/Fortran/Python projects built for about 20 different configurations on Linux, Windows and MacOSX. To these projects, one can also add about 70 external software packages (Boost, Python, Qt, CLHEP, ...) which also have to be built for the same configurations. It order to reduce the time of the development cycle and assure the quality, a framework has been developed for the daily (in fact nightly) build and test of the software. Performing the build and the tests on several configurations and platforms increases the efficiency of the unit and integration tests. Main features: - flexible and fine grained setup (full, partial build) through a web interface; - possibility to build several 'slots' with different configurations; - precise and highly granular reports on a web server; - support for CMT projects (but not only) with their cross-dependencies; - scalable client-server architecture for the control machine and its build machines; - copy of the results in a common place to allow early view of the software stack. The nightly build framework is written in Python for portability and it is easily extensible to accommodate new build procedures.

Nondestructive testing methods in building industry '83. Part 1

International Nuclear Information System (INIS)

1983-10-01

The conference heard 52 papers of which 11 were incorporated in INIS. The subject of these was the use of radiometric methods and instruments for nondestructive testing of building materials and ways of testing the quality of concrete during nuclear power plant construction. (J.P.)

Development of OSSA(Operation Service Support Agreement) Simulator and Site Acceptance Test

Energy Technology Data Exchange (ETDEWEB)

Park, DaeSeung; Ahn, Sung-Jin; Lee, Jong-Beom [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

Building the nuclear power plant is on the schedule, remaining question is who could operate the NPP after the construction is finished. OSSA is known as Operation Service Support Agreement, it is the contract between KHNP(Korea Hydro and Nuclear Power Co.,) and ENEC(Emirates Nuclear Energy Corporation) for United Arab Emirates Nuclear Power Plant operations support. The contract is mostly about the safety and reliability operations and as well as of the training of UAE operators to have better experiences. UAE operators needed to be trained and tested before they come to UAE for operate the NPP. The OSSA simulator was built because operator shall not make any mistakes even if the plant is not yet constructed. Simulator Training is a key for getting experiences without operating the actual plant, because the nuclear power plant never used as the test in real situations. Operators’ requirement is to have more than 2 years at site experiences and also they have to be trained 5 to 8 months of the training. The experience such as the site acceptance test will lead the future nuclear industry to meet the global standard and to lead the safety of the NPP. Under the OSSA agreement 400 KHNP experts will support the operations. Most of the operators were trained at the OSSA simulator which is most reliable simulator that can demonstrate satisfactory performance for the simulator.

Lifting Wing in Constructing Tall Buildings —Aerodynamic Testing

Directory of Open Access Journals (Sweden)

Ian Skelton

2014-05-01

Full Text Available This paper builds on previous research by the authors which determined the global state-of-the-art of constructing tall buildings by surveying the most active specialist tall building professionals around the globe. That research identified the effect of wind on tower cranes as a highly ranked, common critical issue in tall building construction. The research reported here presents a design for a “Lifting Wing,” a uniquely designed shroud which potentially allows the lifting of building materials by a tower crane in higher and more unstable wind conditions, thereby reducing delay on the programmed critical path of a tall building. Wind tunnel tests were undertaken to compare the aerodynamic performance of a scale model of a typical “brick-shaped” construction load (replicating a load profile most commonly lifted via a tower crane against the aerodynamic performance of the scale model of the Lifting Wing in a range of wind conditions. The data indicate that the Lifting Wing improves the aerodynamic performance by a factor of up to 50%.

Reactor building pressure proof test (PPT) and leak rate test (LRT) of Qinshan phase III (CANDU) project

International Nuclear Information System (INIS)

Gu Jun; Shi Jinqi; Fan Fuping

2004-12-01

As the first reactor building (R/B) without stainless steel liner in china, TQNPC studied the containment characteristics, such as strong concrete absorb/release air effect, poor containment penetration. etc. And carefully prepared test scheme and emergency response, creatively introduced the instrument air self-supply system in reactor building, developed the special measurement and analysis system for PPT and LRT, organized work under high-pressure on large-scale in the test. Finally got the containment leak rate result and the test-cost-time value is the best in all same type tests. (authors)

Nevada Test Site Resource Management Plan: Annual summary, January 2000

International Nuclear Information System (INIS)

2000-01-01

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan

Nevada Test Site Resource Management Plan: Annual summary, January 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-01-01

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan.

Nevada Test Site Environmental Report 2007

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

Nevada Test Site Environmental Report 2007

International Nuclear Information System (INIS)

Cathy Wills

2008-01-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report

LHCb: The nightly build and test system for LCG AA and LHCb software

CERN Multimedia

Kruzelecki, K; Degaudenzi, H

2009-01-01

The core software stack both from the LCG Application Area and LHCb consists of more than 25 C++/Fortran/Python projects build for about 20 different configurations on Linux, Windows and MacOSX. To these projects, one can also add about 20 external software packages (Boost, Python, Qt, CLHEP, ...) which have also to be build for the same configurations. It order to reduce the time of the development cycle and increase the quality insurance, a framework has been developed for the daily (nightly actually) build and test of the software. Performing the build and the tests on several configurations and platform allows to increase the efficiency of the unit and integration tests. Main features: - flexible and fine grained setup (full, partial build) through a web interface - possibility to build several "slots" with different configurations - precise and highly granular reports on a web server - support for CMT projects (but not only) with their cross-dependencies. - scalable client -server architecture for the co...

An Experimental Test of Factors Attracting Deer Mice into Buildings.

Science.gov (United States)

Kuenzi, Amy J; Douglass, Richard

2009-09-01

Deer mice (Peromyscus maniculatus) are the principal reservoir host of Sin Nombre virus (SNV). Deer mice use a wide variety of habitats including peridomestic settings in and around human dwellings, their presence in and around homes has been implicated as a risk factor for acquiring Hantavirus Pulmonary Syndrome. Deer mice are believed to enter buildings in order to gain access to a variety of resources including food, bedding material, and better thermal microclimates. However, no one has experimentally tested which factors influence mice use of buildings. We conducted experiments using small simulated buildings to determine the effects of two factors, i.e., food and bedding material, on mouse activity in these buildings. We also examined if these effects varied with time of year. We found that deer mice entered our buildings regardless of the presence or absence of food or bedding. However, the amount of activity in buildings was affected by what they contained. We found significantly higher indices of activity in buildings containing food compared to both empty buildings (control) and buildings containing bedding material. Time of year did not affect activity in buildings.

The Beishan underground research laboratory for geological disposal of high-level radioactive waste in China: Planning, site selection, site characterization and in situ tests

Directory of Open Access Journals (Sweden)

Ju Wang

2018-06-01

Full Text Available With the rapid development of nuclear power in China, the disposal of high-level radioactive waste (HLW has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories (URLs play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China's URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area, located in Gansu Province of northwestern China, has been selected as the final site for China's first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations, including borehole drilling, geological mapping, geophysical surveying, hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological, hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel (BET, which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone (EDZ, and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction. According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned. Keywords: Beishan, Xinchang site, Granite

Structural safety of HDR reactor building during large scale vibration tests

International Nuclear Information System (INIS)

Stangenberg, F.; Zinn, R.

1985-01-01

In the second phase of the HDR investigations, a high shaker excitation of the building is planned using a large shaker which will be located on the operating floor and will be brought up to speed in a balanced condition and then unbalanced and decoupled from the drive system. With decreasing speed the shaker comes in resonance with the building frequencies and its energy is transferred to the building. In this paper the structural safety of the reactor building during the projected shaker tests is analysed. Dynamic response calculations with coupling between building and shaker by simultaneously integrating the equilibrium equations of both building and shaker are presented. The resulting building stresses, soil pressures etc. are compared with allowable values. (orig.)

Corrective Action Investigation Plan for Corrective Action Unit 500: Test Cell A Septic System, Nevada Test Site, Nevada, Revision 0, DOE/NV--528 UPDATED WITH TECHNICAL CHANGE No.1

Energy Technology Data Exchange (ETDEWEB)

ITLV

1998-12-01

This Corrective Action Investigation Plan (CAIP) addresses one of three leachfield systems associated with Test Cell A, which is located in Area 25 at the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (see Leachfield Work Plan Figure 1-1). Corrective Action Unit 500 is comprised of the Test Cell A Septic System (CAS 25-04-05) and the associated leachfield system presented in Figure 1-1 (FFACO, 1996). The leachfield is located 60 meters (m) (200 feet [ft]) southeast of the Building 3124 gate, and approximately 45 m (150 ft) southwest of Building 3116 at Test Cell A. Test Cell A operated during the 1960s to support nuclear rocket reactor testing as part of the Nuclear Rocket Development Station (NRDS) (SNPO, 1970). Various operations within Buildings 3113B (Mechanical Equipment Room), 3115 (Helium Compressor Station), 3116 (Pump House), a water tank drain and overflow, a ''yard and equipment drain system'' outside of Building 3116, and a trailer have resulted in potentially hazardous effluent releases to the leachfield system (DOE, 1988a). The leachfield system components include discharge lines, manways, a septic tank, an outfall line, a diversion chamber, and a 15 by 30 m (50 by 100 ft) leachfield (see Leachfield Work Plan Figure 3-1 for explanation of terminology). In addition, engineering drawings show an outfall system that may or may not be connected to the CAU 500 leachfield. In general, effluent contributed to the leachfield was sanitary wastewater associated with floor drains, toilet and lavatory facilities in Building 3113B and floor drains in the remaining source buildings. The surface and subsurface soils in the vicinity of the collection system, outfall, and leachfield may have been impacted by effluent containing contaminants of potential concern (COPCs) generated by support activities associated with Test Cell A reactor testing operations.

Reactor building integrity testing: A novel approach at Gentilly 2 - principles and methodology

International Nuclear Information System (INIS)

Collins, N.; Lafreniere, P.

1991-01-01

In 1987, Hydro-Quebec embarked on an ambitious development program to provide the Gentilly 2 nuclear power station with an effective, yet practical reactor building Integrity Test. The Gentilly 2 Integrity Test employs an innovative approach based on the reference volume concept. It is identified as the Temperature Compensation Method (TCM) System. This configuration has been demonstrated at both high and low test pressure and has achieved extraordinary precision in the leak rate measurement. The Gentilly 2 design allows the Integrity Test to be performed at a nominal 3 kPa(g) test pressure during an (11) hour period with the reactor at full power. The reactor building Pressure Test by comparison, is typically performed at high pressure 124 kPa(g)) in a 7 day window during an annual outage. The Integrity Test was developed with the goal of demonstrating containment availability. Specifically it was purported to detect a leak or hole in the 'bottled-up' reactor building greater in magnitude than an equivalent pipe of 25 mm diameter. However it is considered feasible that the high precision of the Gentilly 2 TCM System Integrity Test and a stable reactor building leak characteristic will constitute sufficient grounds for the reduction of the Pressure Test frequency. It is noted that only the TCM System has, to this date, allowed a relevant determination of the reactor building leak rate at a nominal test pressure of 3 kPa(g). Classical method tests at low pressure have lead to inconclusive results due to the high lack of precision

Creating Ribo-T: (Design, Build, Test)n.

Science.gov (United States)

Carlson, Erik D

2015-11-20

Engineering biology is especially challenging given our relatively poor ability to rationally design within life's complex design landscape. Thus, moving through the engineering "design, build, test" cycle multiple times accumulates system knowledge and hopefully yields a successful design. Here I discuss the engineering process behind our recently published work creating a ribosome with tethered subunits, Ribo-T.

Remaining Sites Verification Package for the 1607-F7, 141-M Building Septic Tank. Attachment to Waste Site Reclassification Form 2006-040

International Nuclear Information System (INIS)

Dittmer, L.M.

2006-01-01

The 1607-F7, 141-M Building Septic Tank waste site was a septic tank and drain field that received sanitary sewage from the former 141-M Building. Remedial action was performed in August and November 2005. The results of verification sampling demonstrate that residual contaminant concentrations support future unrestricted land uses that can be represented by a rural-residential scenario. These results also show that residual concentrations support unrestricted future use of shallow zone soil and that contaminant levels remaining in the soil are protective of groundwater and the Columbia River

Corrective Action Investigation Plan for Corrective Action Unit No. 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

DOE/NV

1997-10-01

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV), the State of Nevada Division of Environmental Protection (NDEP), and the US Department of Defense. The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUS) or Corrective Action Sites (CASs) (FFACO, 1996). As per the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU No. 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada (Figures 1-1 and 1-2). Corrective Action Unit No. 423 is comprised of only one CAS (No. 03-02-002-0308), which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (m) (240 feet [ft]) northwest as shown on Figure 1-3.

Closure Report for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2009-01-01

Corrective Action Unit (CAU) 107 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Low Impact Soil Sites' and consists of the following 15 Corrective Action Sites (CASs), located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site: CAS 01-23-02, Atmospheric Test Site - High Alt; CAS 02-23-02, Contaminated Areas (2); CAS 02-23-03, Contaminated Berm; CAS 02-23-10, Gourd-Amber Contamination Area; CAS 02-23-11, Sappho Contamination Area; CAS 02-23-12, Scuttle Contamination Area; CAS 03-23-24, Seaweed B Contamination Area; CAS 03-23-27, Adze Contamination Area; CAS 03-23-28, Manzanas Contamination Area; CAS 03-23-29, Truchas-Chamisal Contamination Area; CAS 04-23-02, Atmospheric Test Site T4-a; CAS 05-23-06, Atmospheric Test Site; CAS 09-23-06, Mound of Contaminated Soil; CAS 10-23-04, Atmospheric Test Site M-10; and CAS 18-23-02, U-18d Crater (Sulky). Closure activities were conducted from February through April 2009 according to the FFACO (1996; as amended February 2008) and Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 107 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2009). The corrective action alternatives included No Further Action and Closure in Place with Administrative Controls. Closure activities are summarized.

Site Characterization Plan for decontamination and decommissioning of Buildings 3506 and 3515 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-09-01

Buildings 3506, the Waste Evaporator Facility, and 3515, the Fission Product Pilot Plant, at Oak Ridge National Laboratory (ORNL), are scheduled for decontamination and decommissioning (D and D). This Site Characterization Plan (SCP) presents the strategy and techniques to be used to characterize Buildings 3506/3515 for the purpose of planning D and D activities. The elements of the site characterization for Buildings 3506/3515 are planning and preparation, field investigation, and characterization reporting. Other level of effort activities will include management and oversight, project controls, meetings, and progress reporting. The objective of the site characterization is to determine the nature and extent of radioactive and hazardous materials and other industrial hazards in and around the buildings. This information will be used in subsequent planning to develop a detailed approach for final decommissioning of the facilities: (1) to evaluate decommissioning alternatives and design the most cost-effective D and D approach; (2) to determine the level and type of protection necessary for D and D workers; and (3) to estimate the types and volumes of wastes generated during D and D activities. The current D and D characterization scope includes the entire building, including the foundation and equipment or materials within the building. To estimate potential worker exposure from the soil during D and D, some subfoundation soil sample collection is planned. Buildings 3506/3515 are located in the ORNL main plant area, to the west and east, respectively, of the South Tank Farm. Building 3506 was built in 1949 to house a liquid waste evaporator and was subsequently used for an incinerator experiment. Partial D and D was done prior to abandonment, and most equipment has been removed. Building 3515 was built in 1948 to house fission product separation equipment. In about 1960, all entrances were sealed with concrete block and mortar. Building 3515 is expected to be

Nevada Test Site closure program

International Nuclear Information System (INIS)

Shenk, D.P.

1994-08-01

This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada Test Site. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use

Nevada Test Site Environmental Report 2008

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2009-09-01

The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

BIOMETRICAL CHARACTERIZATION OF TEST SITES FOR MAIZE BREEDING

Directory of Open Access Journals (Sweden)

Domagoj Šimić

2003-12-01

Full Text Available Yield stability of genotypes and analysis of genotype×environment interaction (GEI as important objects in analyses of multienvironment trials are well documented in Croatia. However, little is known about suitability and biometrical characters of the sites where genotypes should be tested. Objectives of this study were in combined analysis of balanced maize trials i to compare test sites in joint linear regression analysis and ii to compare several stability models by clustering test sites in order to assess biometrical suitability of particular test sites. Partitioning of GEI sum of squares according to the symmetrical joint linear regression analysis revealed highly significant Tukey's test, heterogeneity of environmental regressions and residual deviations. Mean grain yields, within-macroenvironment error mean squares, and stability parameters varied considerably among 16 macroenvironments. The highest grain yields were recorded in Osijek in both years and in Varaždin in 1996, with more than 11 t ha-1 . It seems that Feričanci would be optimum test site with relatively high and consistent yield and high values of entry mean squares indicating satisfactory differentiation among cultivars. However, four clustering methods generally did not correspond. According to three out of four clustering methods, two macroenvironments of Feričanci provide similar results. Employing other methods such as shifted multiplicative models, which effectively eliminate significant rank-change interaction, appears to be more reasonable.

Corrective Action Decision Document/Closure Report for Corrective Action Unit 370: T-4 Atmospheric Test Site, Nevada Test Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2009-05-01

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 370, T-4 Atmospheric Test Site, located in Area 4 at the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric Test Site T-4. The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 370 due to the implementation of the corrective action of closure in place with administrative controls. To achieve this, corrective action investigation (CAI) activities were performed from June 25, 2008, through April 2, 2009, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 370: T-4 Atmospheric Test Site and Record of Technical Change No. 1.

Full-scale and in-situ tests on the structures and sites of Kozloduy and Belene NPPs

International Nuclear Information System (INIS)

Simeonov, S.

1995-01-01

This paper includes a detailed list of full scale and in-situ tests that were carried out on the structures and the sites of Kozloduy and Belene nuclear power plants. This involves reactor buildings and turbine halls of the five Kozloduy units, foundations of deaerator and turbine of unit 1, boreholes near channels for additional technical water supply, boreholes near units 2, 3 and 5, boreholes near the concrete center. Special measurement profile and gravel embankment of Belene NPP are included as well

Methodology applied in Cuba for siting, designing, and building a radioactive waste repository under safety conditions

International Nuclear Information System (INIS)

Orbera, L.; Peralta, J.L.; Franklin, R.; Gil, R.; Chales, G.; Rodriguez, A.

1993-01-01

The work presents the methodology used in Cuba for siting, designing, and building a radioactive waste repository safely. This methodology covers both the technical and socio-economic factors, as well as those of design and construction so as to have a safe siting for this kind of repository under Cuba especial condition. Applying this methodology will results in a safe repository

Field Test Data for Detecting Vibrations of a Building Using High-Speed Video Cameras

Science.gov (United States)

2017-10-01

ARL-TR-8185 ● OCT 2017 US Army Research Laboratory Field Test Data for Detecting Vibrations of a Building Using High-Speed Video...Field Test Data for Detecting Vibrations of a Building Using High-Speed Video Cameras by Caitlin P Conn and Geoffrey H Goldman Sensors and...June 2016 – October 2017 4. TITLE AND SUBTITLE Field Test Data for Detecting Vibrations of a Building Using High-Speed Video Cameras 5a. CONTRACT

An authoring tool for building both mobile adaptable tests and web-based adaptive or classic tests

NARCIS (Netherlands)

Romero, C.; Ventura, S.; Hervás, C.; De Bra, P.M.E.; Wade, V.; Ashman, H.; Smyth, B.

2006-01-01

This paper describes Test Editor, an authoring tool for building both mobile adaptable tests and web-based adaptive or classic tests. This tool facilitates the development and maintenance of different types of XML-based multiple- choice tests for using in web-based education systems and wireless

Methods of Usability Testing in Libraries Web Sites

Directory of Open Access Journals (Sweden)

Eman Fawzy

2006-03-01

Full Text Available A Study about libraries' web sites evaluation, that is the Usability, the study talking about methods of usability testing and define it, and its important in web sites evaluation, then details the methods of usability: questionnaire, core groups, testing experimental model, cards arrangement, and composed evaluation.

Towards Smart Buildings Performance Testing as a Service

DEFF Research Database (Denmark)

Markoska, Elena; Lazarova-Molnar, Sanja

2018-01-01

Energy consumption in buildings accounts for ca. 40% of the world’s total energy consumption, yielding a call for attention to their performance and improvement of their behavior. The concept of performance testing has been developed as an approach to control, potentially lower, and bring awarene...

Building dismantlement and site remediation at the Apollo Fuel Plant: When is technology the answer?

International Nuclear Information System (INIS)

Walton, L.

1995-01-01

The Apollo fuel plant was located in Pennsylvania on a site known to have been used continuously for stell production from before the Civil War until after World War II. Then the site became a nuclear fuel chemical processing plants. Finally it was used to convert uranium hexafluoride to various oxide fuel forms. After the fuel manufacturing operations were teminated, the processing equipment was partially decontaminated, removed, packaged and shipped to a licensed low-level radioactive waste burial site. The work was completed in 1984. In 1990 a detailed site characterization was initiated to establishe the extent of contamination and to plan the building dismantlement and soil remediation efforts. This article discusses the site characterization and remedial action at the site in the following subsections: characterization; criticality control; mobile containment; soil washing; in-process measurements; and the final outcome of the project

Factors and Drivers Effecting the Decision of Using Off-Site Manufacturing (OSM Systems in House Building Industry

Directory of Open Access Journals (Sweden)

Hussein Elnaas

2014-01-01

Full Text Available Much has been written on Off-site Manufacturing (OSM in construction, particularly regarding the perceived benefits and barriers to implementation. However, there seems to be a wide misunderstanding of the state of OSM associated with the concept of decision by many of those involved in decision making process within the house building industry. This has led to a demand for guidance’s on decision making process for construction project leaders particularly at early project stages. Choosing a construction method for a project will require an optimum decision strategy which involves careful understanding, measurement and evaluation of a number of decision factors that can have the most influence on successful decision action. This paper, therefore, aims to identify the key decision factors to be considered at evaluation stage when choosing to use Off-Site Manufacturing (OSM as a construction strategy in house building projects. This will reveal the key drivers for change in the industry towards the use of OSM in house building.

Streamlined Approach for Environmental Restoration Work Plan for Corrective Action Unit 461: Joint Test Assembly Sites and Corrective Action Unit 495: Unconfirmed Joint Test Assembly Sites Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

Jeff Smith

1998-08-01

This Streamlined Approach for Environmental Restoration plan addresses the action necessary for the clean closure of Corrective Action Unit 461 (Test Area Joint Test Assembly Sites) and Corrective Action Unit 495 (Unconfirmed Joint Test Assembly Sites). The Corrective Action Units are located at the Tonopah Test Range in south central Nevada. Closure for these sites will be completed by excavating and evaluating the condition of each artillery round (if found); detonating the rounds (if necessary); excavating the impacted soil and debris; collecting verification samples; backfilling the excavations; disposing of the impacted soil and debris at an approved low-level waste repository at the Nevada Test Site

What are become Moruroa and Fangataufa? The dismantling of tests sites did not happen

International Nuclear Information System (INIS)

2005-01-01

Officially, the nuclear test sites of French polynesia have been dismantled. It would be more correct to say that the installations build on the Moruroa atolls have been destroyed. From the end of nuclear tests, the Cea constructions and installations, the most susceptible to be contaminated have been ruined without exterior witness. Nobody knows if the usual procedures of decontamination have been observed. About 15% of materials from he Moruroa base have been distributed as gifts to the local communities in french Polynesia. other materials have been transferred or sold. The observatory of French nuclear weapons estimates the cost of the closing of the French Polynesia test sites to about 15 milliards of Francs, including the compensations paid to the Polynesian government during 10 yeas, so be it hundred times the cost announced by the militaries in 1998. The observatory of French nuclear weapons estimates that the real assessment of radioactive waste being on Moruroa and Fangataufa atolls has not been completely made by the experts of IAEA. This assessment is still to make. The observatory of French nuclear weapons notices that the Moruroa and Fangataufa atolls stay under military status. It recommends that these atolls be reintegrated to the Polynesian land patrimony in order to allow independent expertise. (N.C.)

Nevada Test Site Waste Acceptance Criteria, December 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

Nevada Test Site Waste Acceptance Criteria, December 2000

International Nuclear Information System (INIS)

2000-01-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

Nevada Test Site Area 25. Radiological survey and cleanup project, 1974-1983. Final report

International Nuclear Information System (INIS)

McKnight, R.K.; Rosenberry, C.E.; Orcutt, J.A.

1984-01-01

This report describes radiological survey, decontamination and decommissioning of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures

Advanced breaking technology on the Mochovce nuclear power plant building site

International Nuclear Information System (INIS)

Mraz, M.; Podel, R.; Vojta, A.

1982-01-01

Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m 3 of rock, the required output was derived for the 7th five year plan to the value of 200,000 m 3 per month, i.e., 10,000 m 3 per day and 700 m 3 per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m 2 which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m 3 the combination was used of 6 excavators with a shovel volume of 2.5 m 3 ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m 3 and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m 3 of excavated and removed rock. (B.S.)

Advanced breaking technology on the Mochovce nuclear power plant building site

Energy Technology Data Exchange (ETDEWEB)

Mraz, M; Podel, R; Vojta, A [Vyskumny Ustav Inzinierskych Stavieb, Bratislava (Czechoslovakia)

1982-10-01

Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m/sup 3/ of rock, the required output was derived for the 7th five year plan to the value of 200,000 m/sup 3/ per month, i.e., 10,000 m/sup 3/ per day and 700 m/sup 3/ per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m/sup 2/ which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m/sup 3/ the combination was used of 6 excavators with a shovel volume of 2.5 m/sup 3/ ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m/sup 3/ and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m/sup 3/ of excavated and removed rock.

Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-01-01

The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

Geologic surface effects of underground nuclear testing, Yucca Flat, Nevada Test Site, Nevada; TOPICAL

International Nuclear Information System (INIS)

Grasso, D.N.

2000-01-01

This report presents a new Geographic Information System composite map of the geologic surface effects caused by underground nuclear testing in the Yucca Flat Physiographic Area of the Nevada Test Site, Nye County, Nevada. The Nevada Test Site (NTS) was established in 1951 as a continental location for testing nuclear devices (Allen and others, 1997, p.3). Originally known as the ''Nevada Proving Ground'', the NTS hosted a total of 928 nuclear detonations, of which 828 were conducted underground (U.S. Department of Energy, 1994). Three principal testing areas of the NTS were used: (1) Yucca Flat, (2) Pahute Mesa, and (3) Rainier Mesa including Aqueduct Mesa. Underground detonations at Yucca Flat and Pahute Mesa were typically emplaced in vertical drill holes, while others were tunnel emplacements. Of the three testing areas, Yucca Flat was the most extensively used, hosting 658 underground tests (747 detonations) located at 719 individual sites (Allen and others, 1997, p.3-4). Figure 1 shows the location of Yucca Flat and other testing areas of the NTS. Figure 2 shows the locations of underground nuclear detonation sites at Yucca Flat. Table 1 lists the number of underground nuclear detonations conducted, the number of borehole sites utilized, and the number of detonations mapped for surface effects at Yucca Flat by NTS Operational Area

Engineering evaluation/cost analysis for the proposed management of 15 nonprocess buildings (15 series) at the Weldon Spring Site Chemical Plant, Weldon Spring, Missouri

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.

1991-11-01

The US Department of Energy, under its Surplus Facilities Management Program (SFMP), is responsible for cleanup activities at the Weldon Spring site, located near Weldon Spring, Missouri. The site consists of two noncontiguous areas: (1) a raffinate pits and chemical plant area and (2) a quarry. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support a proposed removal action to manage 15 nonprocess buildings, identified as the 15 Series buildings, at the chemical plant on the Weldon Spring site. These buildings have been nonoperational for more than 20 years, and the deterioration that has occurred during this time has resulted in a potential threat to site workers, the general public, and the environment. The EE/CA documentation of this proposed action is consistent with guidance from the US Environmental Protection Agency (EPA) that addresses removal actions at sites subject to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Actions at the Weldon Spring site are subject to CERCLA requirements because the site is on the EPA's National Priorities List. The objectives of this report are to (1) identify alternatives for management of the nonprocess buildings; (2) document the selection of response activities that will mitigate the potential threat to workers, the public, and the environment associated with these buildings; and (3) address environmental impact associated with the proposed action

Wave Resource Characterization at US Wave Energy Converter (WEC) Test Sites

Science.gov (United States)

Dallman, A.; Neary, V. S.

2016-02-01

The US Department of Energy's (DOE) Marine and Hydrokinetic energy (MHK) Program is supporting a diverse research and development portfolio intended to accelerate commercialization of the marine renewable industry by improving technology performance, reducing market barriers, and lowering the cost of energy. Wave resource characterization at potential and existing wave energy converter (WEC) test sites and deployment locations contributes to this DOE goal by providing a catalogue of wave energy resource characteristics, met-ocean data, and site infrastructure information, developed utilizing a consistent methodology. The purpose of the catalogue is to enable the comparison of resource characteristics among sites to facilitate the selection of test sites that are most suitable for a developer's device and that best meet their testing needs and objectives. It also provides inputs for the design of WEC test devices and planning WEC tests, including the planning of deployment and operations and maintenance. The first edition included three sites: the Pacific Marine Energy Center (PMEC) North Energy Test Site (NETS) offshore of Newport, Oregon, the Kaneohe Bay Naval Wave Energy Test Site (WETS) offshore of Oahu, HI, and a potential site offshore of Humboldt Bay, CA (Eureka, CA). The second edition was recently finished, which includes five additional sites: the Jennette's Pier Wave Energy Converter Test Site in North Carolina, the US Army Corps of Engineers (USACE) Field Research Facility (FRF), the PMEC Lake Washington site, the proposed PMEC South Energy Test Site (SETS), and the proposed CalWave Central Coast WEC Test Site. The operational sea states are included according to the IEC Technical Specification on wave energy resource assessment and characterization, with additional information on extreme sea states, weather windows, and representative spectra. The methodology and a summary of results will be discussed.

Model tests and numerical analysis on restoring force characteristics of reactor buildings

International Nuclear Information System (INIS)

Uchiyama, Y.; Suzuki, S.; Akino, K.

1987-01-01

Seismic shear walls of nuclear reactor buildings are composed of cylindrical, truncated cone-shape, box-shape, irregular polygonal walls or its combination and they are generally heavily reinforced concrete (RC) walls. So the elasto-plastic behaviors of those RC structures in ultimate regions have many unsolved and may be considered as especially important factors for explaining nonlinear response of nuclear reactor buildings. Following these research demands, the authors have prepared a nonlinear F.E.M. code called ''SANREF'' and made an extensive study for the restoring force characteristics of the inner concrete structures (I/C) of a PWR-type containment vessel and the principal seismic shear walls of a BWR-type reactor building by some series of reduced model tests and simulation analysis for the tests results. The detailed objectives of this study can be summarized as follows: (1) Examine the effectiveness of the configurations of shear walls, reinforcement ratios, shear span ratios (M/Qd) and vertical axial stress by ''partial model test'' which simulates some independent shear walls of the PWR-type and BWR-type reactor buildings. (2) Obtain fundamental data of restoring force characteristics of the complex shaped RC structures by ''composite model test'' which models are composed of the partial model test specimens. (3) Verify the applicability of analytical methods and constitutive modelings in SANREF code for complex shaped RC structures through nonlinear simulation analysis for the composite model test

Political aspects of nuclear test effects at Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Sydykov, E.B.; Panin, M.S.

2003-01-01

The paper describes tense struggle of Kazakhstan people for closure of the Semipalatinsk Nuclear Test Site. It reveals major foreign policy aspects and nuclear test effects for both Kazakhstan and the world community. (author)

Embedment Effect test on soil-structure interaction

International Nuclear Information System (INIS)

Nasuda, Toshiaki; Akino, Kinji; Izumi, Masanori.

1991-01-01

A project consisting of laboratory test and field test has been conducted to clarify the embedment effect on soil-structure interaction. The objective of this project is to obtain the data for improving and preparing seismic analysis codes regarding the behavior of embedded reactor buildings during earthquakes. This project was planned to study the effect of soil-structure interaction using small size soil-structure models as well as the large scale models. The project was started in April, 1986, and is scheduled to end in March, 1994. The laboratory test models and field test models, and the measurement with accelerometers and others are described. As the interim results, the natural frequency and damping factor increased, and the amplitude decreased by the embedment of the test models. Some earthquakes were recorded in a soft rock site. The epicenters of the earthquakes occurred in 1989 are shown. The field tests were carried out in three sites. Two sites were used for the dynamic test with four test models having 8 m x 8 m plane size and 10 m height. One site was used for the static test with one concrete block as a specimen. Two models represent BWR type reactor buildings, and two models represent PWR type buildings. (K.I.)

Sandia National Laboratories, Tonopah Test Range Assembly Building 9B (Building 09-54): Photographs and Written Historical and Descriptive Data

Energy Technology Data Exchange (ETDEWEB)

Ullrich, Rebecca A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Corporate Archives and History Program

2017-08-01

Assembly Building 9B (Building 09-54) is a contributing element to the Sandia National Laboratories (SNL) Tonopah Test Range (TTR) Historic District. The SNL TTR Historic District played a significant role in U.S. Cold War history in the areas of stockpile surveillance and non-nuclear field testing of nuclear weapons designs. The district covers approximately 179,200 acres and illustrates Cold War development testing of nuclear weapons components and systems. This report includes historical information, architectural information, sources of information, project information, maps, blueprints, and photographs.

Radiation doses to local populations near nuclear weapons test sites worldwide.

Science.gov (United States)

Simon, Steven L; Bouville, André

2002-05-01

Nuclear weapons testing was conducted in the atmosphere at numerous sites worldwide between 1946 and 1980, which resulted in exposures to local populations as a consequence of fallout of radioactive debris. The nuclear tests were conducted by five nations (United States, Soviet Union, United Kingdom, France, and China) primarily at 16 sites. The 16 testing sites, located in nine different countries on five continents (plus Oceania) contributed nearly all of the radioactive materials released to the environment by atmospheric testing; only small amounts were released at a fewother minor testing sites. The 16 sites discussed here are Nevada Test Site, USA (North American continent), Bikini and Enewetak, Marshall Islands (Oceania); Johnston Island, USA (Oceania), Christmas and Malden Island, Kiribati (Oceania); Emu Field, Maralinga, and Monte Bello Islands, Australia (Australian continent); Mururoa and Fangataufa, French Polynesia (Oceania), Reggane, Algeria (Africa), Novaya Zemlya and Kapustin Yar, Russia (Europe), Semipalatinsk, Kazakhstan (Asia), and Lop Nor, China (Asia). There were large differences in the numbers of tests conducted at each location and in the total explosive yields. Those factors, as well as differences in population density, lifestyle, environment, and climate at each site, led to large differences in the doses received by local populations. In general, the tests conducted earliest led to the highest individual and population exposures, although the amount of information available for a few of these sites is insufficient to provide any detailed evaluation of radiation exposures. The most comprehensive information for any site is for the Nevada Test Site. The disparities in available information add difficulty to determining the radiation exposures of local populations at each site. It is the goal of this paper to summarize the available information on external and internal doses received by the public living in the regions near each of the

Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 1

International Nuclear Information System (INIS)

1997-12-01

The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This closure report documents the strategy and analytical results that support the clean closure or closure in place of each of the components within CAU 93. In addition, the report documents all deviations from the approved closure plan and provides rationale for all deviations

Controlled Archaeological Test Site (CATS) Facility

Data.gov (United States)

Federal Laboratory Consortium — CATS facility is at the Construction Engineering Research Laboratory (CERL), Champaign, IL. This 1-acre test site includes a variety of subsurface features carefully...

Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

International Nuclear Information System (INIS)

1980-02-01

This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm 2 of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm 2 . The other three spots are 100 cm 2 or less. The beta-gamma readings at these spots are 8.4 x 10 2 dis/min-100 cm 2 , 2.2 x 10 5 dis/min-100 cm 2 , 2.2 x 10 5 dis/min-100 cm 2 and 8.5 x 10 4 dis/min-100 cm 2 . No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer

Performance evaluation of the Solar Building Test Facility

Science.gov (United States)

Jensen, R. N.

1981-01-01

The general performance of the NASA Solar Building Test Facility (SBTF) and its subsystems and components over a four year operational period is discussed, and data are provided for a typical one year period. The facility consists of a 4645 sq office building modified to accept solar heated water for operation of an absorption air conditioner and a baseboard heating system. An adjoining 1176 sq solar flat plate collector field with a 114 cu tank provides the solar heated water. The solar system provided 57 percent of the energy required for heating and cooling on an annual basis. The average efficiency of the solar collectors was 26 percent over a one year period.

HIV/AIDS testing sites and locator services

Data.gov (United States)

U.S. Department of Health & Human Services — The HIV Testing Sites & Care Services Locator is a first-of-its-kind, location-based search tool that allows you to search for testing services, housing...

Trust-Building in Electronic Markets: Relative Importance and Interaction Effects of Trust-Building Mechanisms

Science.gov (United States)

Tams, Stefan

We examine the relative and complementary effectiveness of trust-building strategies in online environments. While prior research has examined various antecedents to trust, we investigated two trust-building mechanisms more in depth: Web site trust and vendor reputation. We tried to understand the relative effectiveness of these two important mechanisms to provide online businesses with a clear recommendation of how to establish trust in an effective and efficient manner. Drawing from the literature on trust, we proposed vendor reputation to be more effective than Web site trust. Moreover, we examined a potential complementary effect of these mechanisms so as to provide online businesses with a deeper understanding of how to derive superior trust. We hypothesize a small such effect. The study proposes a laboratory experiment to test the model.

Measures of transparency for decommissioning of test site

International Nuclear Information System (INIS)

Andrusenko, B. A.; Smirnov, V. G.; Sherbina, A. N.

1997-01-01

This paper presents non-traditional directions of activity of the Institute specialists to solve complicated scientific and technical tasks within the framework of observance of international obligations on non-proliferation. In the latest time much attention is paid to the reaching of mutual confidence between sides during a control over the observance of agreements regarding disarmament. How can we demonstrate implementation of agreements to each of both sides, not having leakage of confidential or, so called, 'sensitive' information? That means to ensure 'transparency' of activity, not doing a damage to both sides. It is needed to note that the meaning of the above term can be substantially varied, depending on what field of activity it is used in. For instance, the meaning of the transparency measures adopted in joint program of RFNC and SNL for future control of disassembling of nuclear weapon is represented as ''...measures which can be taken for building of the confidence of both sides, assuring that these sides reach mutual understanding, and one side can inspect activity of another side as well as its outcomes which are a part of lifetime cycle of nuclear weapon. We consider this meaning to be acceptable for objectives and principles indicated in joint Russian-Kazakhstani activity on decommisioning of the test site. Hereafter in this paper we will use terminology on the transparency measures which is adopted for future control of the nuclear weapon disassembling. The transparency measures application distates a necessity of development of documentation drawing system of individual procedures and operations, which has 'sensitive' information and to which some transporancy measures, and be in accord with the existent legislation of Russia and Kazakhstan. There is an example of nuclear device (ND) destruction in a tunnel 108 located on the former Semipalatinsk test site, that represents experience gained by specialists of RFNC-RITP in the field of the

Nevada Test Site Environmental Report 2007 Summary

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2007 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Nuclear test at Semipalatinsk test site and their environmental impacts

International Nuclear Information System (INIS)

Logachev, V.A.

2000-01-01

This paper present classification of nuclear tests conducted at the Semipalatinsk test site by tier radiation hazards. The Institute of Biophysics of the Russian Ministry of Health established a data base the archival data on radiation situation parameters and compiled an album of radioactive plum footprints. The paper states that external and internal exposure doses received by population lived in the test vicinity can sufficiently reliably assesses using archival data. (author)

Site 300 SPCC Plan

Energy Technology Data Exchange (ETDEWEB)

Griffin, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-11-23

This Spill Prevention, Control, and Countermeasure (SPCC) Plan describes the measures that are taken at Lawrence Livermore National Laboratory’s (LLNL) Experimental Test Site (Site 300) near Tracy, California, to prevent, control, and handle potential spills from aboveground containers that can contain 55 gallons or more of oil. This SPCC Plan complies with the Oil Pollution Prevention regulation in Title 40 of the Code of Federal Regulations, Part 112 (40 CFR 112) and with 40 CFR 761.65(b) and (c), which regulates the temporary storage of polychlorinated biphenyls (PCBs). This Plan has also been prepared in accordance with Division 20, Chapter 6.67 of the California Health and Safety Code (HSC 6.67) requirements for oil pollution prevention (referred to as the Aboveground Petroleum Storage Act [APSA]), and the United States Department of Energy (DOE) Order No. 436.1. This SPCC Plan establishes procedures, methods, equipment, and other requirements to prevent the discharge of oil into or upon the navigable waters of the United States or adjoining shorelines for aboveground oil storage and use at Site 300. This SPCC Plan has been prepared for the entire Site 300 facility and replaces the three previous plans prepared for Site 300: LLNL SPCC for Electrical Substations Near Buildings 846 and 865 (LLNL 2015), LLNL SPCC for Building 883 (LLNL 2015), and LLNL SPCC for Building 801 (LLNL 2014).

Closure Report for Corrective Action Unit 261: Area 25 Test Cell A Leachfield System, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

T. M. Fitzmaurice

2001-04-01

The purpose of this Closure Report (CR) is to provide documentation of the completed corrective action at the Test Cell A Leachfield System and to provide data confirming the corrective action. The Test Cell A Leachfield System is identified in the Federal Facility Agreement and Consent Order (FFACO) of 1996 as Corrective Action Unit (CAU) 261. Remediation of CAU 261 is required under the FFACO (1996). CAU 261 is located in Area 25 of the Nevada Test Site (NTS) which is approximately 140 kilometers (87 miles) northwest of Las Vegas, Nevada (Figure 1). CAU 261 consists of two Corrective Action Sites (CASS): CAS 25-05-01, Leachfield; and CAS 25-05-07, Acid Waste Leach Pit (AWLP) (Figures 2 and 3). Test Cell A was operated during the 1960s and 1970s to support the Nuclear Rocket Development Station. Various operations within Building 3124 at Test Cell A resulted in liquid waste releases to the Leachfield and the AWLP. The following existing site conditions were reported in the Corrective Action Decision Document (CADD) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1999): Soil in the leachfield was found to exceed the Nevada Division of Environmental Protection (NDEP) Action Level for petroleum hydrocarbons, the U.S. Environmental Protection Agency (EPA) preliminary remediation goals for semi volatile organic compounds, and background concentrations for strontium-90; Soil below the sewer pipe and approximately 4.5 meters (m) (15 feet [ft]) downstream of the initial outfall was found to exceed background concentrations for cesium-137 and strontium-90; Sludge in the leachfield septic tank was found to exceed the NDEP Action Level for petroleum hydrocarbons and to contain americium-241, cesium-137, uranium-234, uranium-238, potassium-40, and strontium-90; No constituents of concern (COC) were identified at the AWLP. The NDEP-approved CADD (DOWNV, 1999) recommended Corrective Action Alternative 2, ''Closure of the Septic Tank and Distribution Box

Hess Tower field study: sonic measurements at a former building-integrated wind farm site

Science.gov (United States)

Araya, Daniel

2017-11-01

Built in 2010, Hess Tower is a 29-story office building located in the heart of downtown Houston, TX. Unique to the building is a roof structure that was specifically engineered to house ten vertical-axis wind turbines (VAWTs) to partially offset the energy demands of the building. Despite extensive atmospheric boundary layer (ABL) wind tunnel tests to predict the flow conditions on the roof before the building was constructed, the Hess VAWTs were eventually removed after allegedly one of the turbines failed and fell to the ground. This talk presents in-situ sonic anemometry measurements taken on the roof of Hess Tower at the former turbine locations. We compare this wind field characterization to the ABL wind tunnel data to draw conclusions about building-integrated wind farm performance and prediction capability.

Penetration Testing Model for Web sites Hosted in Nuclear Malaysia

International Nuclear Information System (INIS)

Mohd Dzul Aiman Aslan; Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Saaidi Ismail; Mohd Fauzi Haris; Norzalina Nasiruddin; Raja Murzaferi Mokhtar

2012-01-01

Nuclear Malaysia web sites has been very crucial in providing important and useful information and services to the clients as well as the users worldwide. Furthermore, a web site is important as it reflects the organisation image. To ensure the integrity of the content of web site, a study has been made and a penetration testing model has been implemented to test the security of several web sites hosted at Nuclear Malaysia for malicious attempts. This study will explain how the security was tested in the detailed condition and measured. The result determined the security level and the vulnerability of several web sites. This result is important for improving and hardening the security of web sites in Nuclear Malaysia. (author)

Build green and conventional materials off-gassing tests: A final report

Energy Technology Data Exchange (ETDEWEB)

Piersol, P.

1995-12-31

Build Green is a certification program that will identify and label building products with a known recycled content. The introduction of these recycled materials has raised the concern that they may emit more indoor pollutants than conventional materials. This study addresses that concern by analyzing Build Green and conventional materials to assess their potential for off-gassing. The study involved emission tests of 37 materials including carpets, carpet undercushions, structural lumber, foundation material, insulation, drywall, fiberboard, counter tops, and cabinetry. The results presented in this report include comparisons of Build Green and conventional materials in terms of emissions of volatile organic compounds and formaldehyde, the material loading ratio, and discussion of the specific sources of the emissions.

Sustainability assessment, rating systems and historical buildings Case study: Rehabilitated construction in a university site

Directory of Open Access Journals (Sweden)

Sadrykia Somayeh

2016-01-01

Full Text Available This paper explores the relationship between the indicators and different factors that “rating systems for green projects” concentrates on, and principles and factors considered in the rehabilitation of historical buildings. In recent years, different methods and systems concerned and improved for assessing environmental sustainability. LEED (Leadership in Energy and Environmental Design and BREEAM (Building Research Establishment (BRE Environmental Assessment Method are two most commonly used rating systems, established in U.S and UK. These systems comprise some categories and different factors to achieve environmentally responsible design. Firstly, this study focuses on the list of rating systems indicators and criteria. Secondly this paper investigates a historical rehabilitated building in the site of Tabriz Art University, as a case study and has tried to compile its green design elements. Finally, this work intends to compare mentioned elements with indicators and factors of building rating systems. Findings of the study revealed that “Materials and Resources”, “indoor environmental quality” and also “Sustainable Sites” ,the most significant indicator of rating systems, had major and important role in the rehabilitation of the building. Beyond this materials’ life cycle was considerable in construction.

Storage for the Fast Flux Test Facility unirradiated fuel in the Plutonium Finishing Plant Complex, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-01-01

This Environmental Assessment evaluates the proposed action to relocate and store unirradiated Fast Flux Test Facility fuel in the Plutonium Finishing Plant Complex on the Hanford Site, Richland, Washington. The US Department of Energy has decided to cease fuel fabrication activities in the 308 Building in the 300 Area. This decision was based on a safety concern over the ability of the fuel fabrication portion of the 308 Building to withstand a seismic event. The proposed action to relocate and store the fuel is based on the savings that could be realized by consolidating security costs associated with storage of the fuel. While the 308 Building belowgrade fuel storage areas are not at jeopardy by a seismic event, the US Department of Energy is proposing to cease storage operations along with the related fabrication operations. The US Department of Energy proposes to remove the unirradiated fuel pins and fuel assemblies from the 308 Building and store them in Room 192A, within the 234-5Z Building, a part of the Plutonium Finishing Plant Complex, located in the 200 West Area. Minor modifications to Room 192A would be required to accommodate placement of the fuel. The US Department of Energy estimates that removing all of the fuel from the 308 Building would save $6.5 million annually in security expenditures for the Fast Flux Test Facility. Environmental impacts of construction, relocation, and operation of the proposed action and alternatives were evaluated. This evaluation concluded that the proposed action would have no significant impacts on the human environment

HIV testing sites' communication about adolescent confidentiality: potential barriers and facilitators to testing.

Science.gov (United States)

Hyden, Christel; Allegrante, John P; Cohall, Alwyn T

2014-03-01

This study sought to evaluate HIV testing locations in New York City in terms of staff communication of confidentiality policies for adolescent clients. Using the New York State Directory of HIV Counseling and Testing Resources as a sampling frame, this study made telephone contact with 164 public HIV testing locations in New York City and used a semistructured interview to ask questions about confidentiality, parental permission, and parent access to test results. At 48% of locations, either HIV testing was not offered or we were unable to reach a staff member to ask questions about testing options and confidentiality. At the remaining sites, information provided regarding confidentiality, parental consent, and privacy of test results was correct only 69% to 85% of the time. Additionally, 23% of sites successfully contacted offered testing exclusively between 9:00 a.m. and 3:00 p.m. weekdays, when most adolescents are in school. Our findings point to a need for increased training and quality control at the clinical level to ensure that consumers in need of HIV testing are provided with accurate information and accessible services. Furthermore, these results highlight the need for more "patient-centric" sites with enhanced accessibility for potential clients, particularly youth.

The role of clearance in Germany - release of materials, buildings and sites

International Nuclear Information System (INIS)

Thierfeldt, S.

2005-01-01

Clearance in Germany is far advanced. A complex regulatory framework exists in the Radiation Protection Ordinance (RPO/Strahlenschutzverordnung, StrlSchV) since 2001 which has replaced previous recommendations on clearance issued by the German Radiation Protection Commission (Strahlenschutzkommission, SSK). A number of options exist both for unconditional clearance (e.g. of all kinds of materials with no restrictions on the destination or future use) and for clearance for a specific purpose (e.g. recycling of metal scrap). For each clearance option there is a set of nuclide specific clearance levels which have been derived on the basis of the 10 Sv/a individual dose criterion using complex radiological models which are tailored to the respective material cycles (metal scrap, buildings, building rubble, waste for disposal, sites). The clearance levels have been thoroughly reviewed by the SSK. An extensive comparison to sets of clearance levels used in other countries or issued as guidance by international bodies revealed that the correspondence between values is between good and acceptable taking into account country-specific approaches and special assumptions which would not necessarily pertain to German situations. Clearance is a major factor in the material management, especially of nuclear installations undergoing decommissioning. The variety of clearance options leaves the operator of a nuclear installation sufficient flexibility for optimisation of the material management. Clearance is of particular importance in a country like Germany where the estimated costs for a future repository are very high and the interim storage facilities for radioactive material are limited and costly. While the licensee is responsible for his material management, the issuance of a clearance permit is done by the regulatory body upon application. The regulators may choose to use the clearance levels and regulations as stipulated by the RPO, or to impose site-specific regulations on

Nevada Test Site Environmental Report 2008 Summary

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2009-09-01

The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

Radiological Situation at the Bomb Test Sites

International Nuclear Information System (INIS)

Valkovic, V.

1998-01-01

An overview of radiological situation at the selected bomb test sites is presented. The report is based on the reports and measurements performed by IAEA while the author was a head of its Physics-Chemistry-Instrumentation Laboratory. Radiological conditions at Bikini Atoll (USA testing ground), Mururoa and Fangataufa Atolls (French testing ground) and Semipalatinsk (SSSR testing ground) have been discussed in some details. (author)

Removal site evaluation report on Building 3019B at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-09-01

This removal site evaluation report on Building 3019B at Oak Ridge National Laboratory was prepared to provide the environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the facility pose a substantial risk to human health or the environment and whether remedial site evaluations or removal actions are, therefore, required. The scope of the project included (1) a search for, and review of, readily available historical records regarding operations and use of the facility (including hazardous substance usage and existing contamination); (2) interviews with facility personnel concerning current and past practices; and (3) a brief walk-through to visually inspect the facility nd identify existing hazard areas requiring maintenance actions or remedial evaluation. The results of the removal site evaluation indicate that areas inside Building 3019B pose no imminent hazard because adequate engineering and administrative controls are in place and enforced within the facility to ensure worker and environmental protection. A maintenance action, however, is being undertaken or proposed. Deteriorated and peeling exterior paint in areas on the west and south walls on the exterior of the building has an uninhibited pathway to the storm water drainage system and can potentially impact the local surface water during periods of storm water runoff. The paint is assumed to be lead based, thus posing a potential problem. In addition, the subsurface of all of the exterior walls may be radiologically contaminated. A maintenance action will be necessary to prevent further deterioration and dislodging of the paint

About rehabilitation of vegetation of disturbed ecosystems of the Semipalatinsk test sites

International Nuclear Information System (INIS)

Plisak, R.P.; Plisak, S.V.

2005-01-01

Full text: Semipalatinsk Test Sites are the place where 470 nuclear tests were conducted in 1949-1989: 26 surface, 87 air, 357 underground. Total area of polluted territories within the test sites reaches 400 square kilometers and 32 squire kilometers at adjoining territory. Radioactive precipitation spread at the territory of 304 thousand square kilometers by traces of radioactive clouds. The precipitation promoted negative processes in environment and damaged public health. One of the most negative factors is products of nuclear decay after underground nuclear tests. They accumulate in soil. Vertical and horizontal migration of radionuclides occurs. The radionuclides accumulate in plants and reach human organism through food chain. Vegetation cover of former Semipalatinsk Test Sites was partly destroyed or damaged on the test sites mentioned above. Nuclear explosions, military and technical construction, building of roads and communication network were conducted out here. Present vegetation cover of breached areas is represented by plant aggregations and communities. They are attributed to different stages of the process of restoration of initial (steppe) vegetation. Rates of rehabilitation of breached ecosystems are conditioned by degree of moisture and properties of formed technogene substratum (soil texture, presence of detritus, and quantity of fine earth). The higher rates of rehabilitation of breached vegetation are typical for ecosystems of flood lands, depressions between hills and slopes of hills of northern exposition. Rehabilitation of zonal ecosystems (sagebrush-eather-grass communities on light chestnut soils) in conditions of arid climate and insignificant water content in substratum of technogene objects proceeds slowly. Rates of restoration of haloxerophyte communities are conditioned by additional moistening of surface washing down of moist ure into micro depressions occupied by sanotiazol. The process of vegetation rehabilitation of damaged

Strategies for Demand Response in Commercial Buildings

Energy Technology Data Exchange (ETDEWEB)

Watson, David S.; Kiliccote, Sila; Motegi, Naoya; Piette, Mary Ann

2006-06-20

This paper describes strategies that can be used in commercial buildings to temporarily reduce electric load in response to electric grid emergencies in which supplies are limited or in response to high prices that would be incurred if these strategies were not employed. The demand response strategies discussed herein are based on the results of three years of automated demand response field tests in which 28 commercial facilities with an occupied area totaling over 11 million ft{sup 2} were tested. Although the demand response events in the field tests were initiated remotely and performed automatically, the strategies used could also be initiated by on-site building operators and performed manually, if desired. While energy efficiency measures can be used during normal building operations, demand response measures are transient; they are employed to produce a temporary reduction in demand. Demand response strategies achieve reductions in electric demand by temporarily reducing the level of service in facilities. Heating ventilating and air conditioning (HVAC) and lighting are the systems most commonly adjusted for demand response in commercial buildings. The goal of demand response strategies is to meet the electric shed savings targets while minimizing any negative impacts on the occupants of the buildings or the processes that they perform. Occupant complaints were minimal in the field tests. In some cases, ''reductions'' in service level actually improved occupant comfort or productivity. In other cases, permanent improvements in efficiency were discovered through the planning and implementation of ''temporary'' demand response strategies. The DR strategies that are available to a given facility are based on factors such as the type of HVAC, lighting and energy management and control systems (EMCS) installed at the site.

Preliminary investigation Area 12 fleet operations steam cleaning discharge area Nevada Test Site

International Nuclear Information System (INIS)

1996-07-01

This report documents the characterization activities and findings of a former steam cleaning discharge area at the Nevada Test Site. The former steam cleaning site is located in Area 12 east of Fleet Operations Building 12-16. The characterization project was completed as a required condition of the ''Temporary Water Pollution Control Permit for the Discharge From Fleet Operations Steam Cleaning Facility'' issued by the Nevada Division of Environmental Protection. The project objective was to collect shallow soil samples in eight locations in the former surface discharge area. Based upon field observations, twelve locations were sampled on September 6, 1995 to better define the area of potential impact. Samples were collected from the surface to a depth of approximately 0.3 meters (one foot) below land surface. Discoloration of the surface soil was observed in the area of the discharge pipe and in localized areas in the natural drainage channel. The discoloration appeared to be consistent with the topographically low areas of the site. Hydrocarbon odors were noted in the areas of discoloration only. Samples collected were analyzed for bulk asbestos, Toxicity Characteristic Leaching Procedure (TCLP) metals, total petroleum hydrocarbons (TPHs), volatile organic compounds (VOCs), semi-volatile organic compounds (Semi-VOCs), and gamma scan

WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

F. Habashi

2000-06-22

The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

Habashi, F.

2000-01-01

The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

Study of site layout in the Rokkasho site

International Nuclear Information System (INIS)

Sato, Kazuyoshi; Tamura, Kousaku; Yagenji, Akira; Sekiya, Shigeki; Takahashi, Hideo; Neyatani, Yuzuru; Uehara, Masaharu; Motohashi, Keiichi; Hashimoto, Masayoshi; Ogino, Shunji; Nagamatsu, Nobuhide

2006-03-01

The Final Design Report (FDR) of the International Thermonuclear Experimental Reactor (ITER) was published on July 2001 as a summary of the Engineering Design Activity (EDA). After the EDA, site dependent design has been investigated for the invitation of ITER toward Rokkasho Site (Iyasakadai area) in Aomori prefecture. This report describes the results of site layout of major buildings and structures of ITER in the Rokkasho-Site. The data of the ground near the site and the results of site dependent design in Japan were applied to this study. Through this study, the most appropriate site layout has been constructed with satisfaction of following conditions. (1) Bedrock level at the tokamak complex building is relatively high and it can be reduced the cost of excavation and foundation work. (2) Total amount of excavation soil for site preparation is minimized and the flexibility of the layout is ensured with flat ground level. (3) Accessibility of human and equipments, reduction of noise and vibration to the environment can be obtained. Total length of ducts and piping between buildings in site is minimized. (author)

Interdisciplinary hydrogeologic site characterization at the Nevada Test Site

International Nuclear Information System (INIS)

Hawkins, W.L.; Wagoner, J.L.; Drellack, S.L.

1992-01-01

The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices. Hydrogeologic investigations began in earnest with the US Geological Survey mapping much of the area from 1960 to 1965. Since 1963, all nuclear detonations have been underground. Most tests are conducted in vertical shafts, but a small percentage are conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks, but sometimes in alluvium. Hydrogeologic investigations began in earnest with the US Geological Survey's mapping of much of the NTS region from 1960 to 1965. Following the BANEBERRY test in December 1970, which produced an accidental release of radioactivity to the atmosphere, the US Department of Energy (then the Atomic Energy Commission) established the Containment Evaluation Panel (CEP). Results of interdisciplinary hydrogeologic investigations for each test location are included in a Containment Prospectus which is thoroughly reviewed by the CEP

Radioactive contamination of former Semipalatinsk test site area

International Nuclear Information System (INIS)

Artem'ev, O.I.; Akhmetov, M.A.; Ptitskaya, L.D.

2001-01-01

The nuclear weapon infrastructure elimination activities and related surveys of radioactive contamination are virtually accomplished at the Semipalatinsk test site (STS). The radioecological surveys accompanied closure of tunnels which were used for underground nuclear testing at Degelen technical field and elimination of intercontinental ballistic missile silo launchers at Balapan technical field. At the same time a ground-based route survey was carried out at the Experimental Field where aboveground tests were conducted and a ground-based area survey was performed in the south of the test site where there are permanent and temporary inhabited settlements. People dwelling these settlements are mainly farmers. The paper presents basic results of radiological work conducted in the course of elimination activities. (author)

Lightning vulnerability of nuclear explosive test systems at the Nevada Test Site

International Nuclear Information System (INIS)

Hasbrouck, R.T.

1985-01-01

A task force chartered to evaluate the effects of lightning on nuclear explosives at the Nevada Test Site has made several recommendations intended to provide lightning-invulnerable test device systems. When these recommendations have been implemented, the systems will be tested using full-threat-level simulated lightning

[Study on Tritium Content in Soil at Sites of Nuclear Explosions on the Territory of Semipalatinsk Test Site].

Science.gov (United States)

Timonova, L V; Lyakhova, O N; Lukashenko, S N; Aidarkhanov, A O

2015-01-01

As a result of investigations carried out on the territory of Semipalatinsk Test Site, tritium was found in different environmental objects--surface and ground waters, vegetation, air environment, and snow cover. The analysis of the data obtained has shown that contamination of environmental objects at the Semipalatinsk Test Site with tritium is associated with the places where underground nuclear tests were performed. Since tritium can originate from an activation reaction and be trapped by pock particles during a test, it was decided to examine the soil in the sites where surface and excavation tests took place. It was found that the concentration of tritium in soil correlates with the concentration of europium. Probably, the concentration of tritium in the soil depends on the character and yield of the tests performed. Findings of the study have revealed that tritium can be found in soil in significant amounts not only in sites where underground nuclear tests took place but also in sites where surface and excavation nuclear tests were carried out.

Fruit and vegetable radioactivity survey, Nevada Test Site environs

International Nuclear Information System (INIS)

Andrews, V.E.; Vandervort, J.C.

1978-04-01

During the 1974 growing season, the Environmental Monitoring and Support Laboratory-Las Vegas, of the U.S. Environmental Protection Agency, collected samples of fruits and vegetables grown in the off-site area surrounding the Nevada Test Site. The objective was to estimate the potential radiological dose to off-site residents from consumption of locally grown foodstuffs. Irrigation water and soil were collected from the gardens and orchards sampled. Soil concentrations of cesium-137 and plutonium-239 reflected the effects of close-in fallout from nuclear testing at the Nevada Test Site. The only radionuclide measured in fruit and vegetable samples which might be related to such fallout was strontium-90, for which the first year estimated dose to bone marrow of an adult with an assumed rate of consumption of the food would be 0.14 millirad

Hydrologic test plans for large-scale, multiple-well tests in support of site characterization at Hanford, Washington

International Nuclear Information System (INIS)

Rogers, P.M.; Stone, R.; Lu, A.H.

1985-01-01

The Basalt Waste Isolation Project is preparing plans for tests and has begun work on some tests that will provide the data necessary for the hydrogeologic characterization of a site located on a United States government reservation at Hanford, Washington. This site is being considered for the Nation's first geologic repository of high level nuclear waste. Hydrogeologic characterization of this site requires several lines of investigation which include: surface-based small-scale tests, testing performed at depth from an exploratory shaft, geochemistry investigations, regional studies, and site-specific investigations using large-scale, multiple-well hydraulic tests. The large-scale multiple-well tests are planned for several locations in and around the site. These tests are being designed to provide estimates of hydraulic parameter values of the geologic media, chemical properties of the groundwater, and hydrogeologic boundary conditions at a scale appropriate for evaluating repository performance with respect to potential radionuclide transport

Cargo/Weapons Elevator Land Based Engineering Site

Data.gov (United States)

Federal Laboratory Consortium — The Cargo and Weapons Facility consists of a suite of full scale and component test facilities contiguously located in building 77H. The site was constructed in 1987...

Busted Butte Unsaturated Zone Transport Test: Fiscal Year 1998 Status Report Yucca Mountain Site Characterization Program Deliverable SPU85M4

International Nuclear Information System (INIS)

Bussod, G.Y.; Turin, H.J.; Lowry, W.E.

1999-01-01

This report describes the status of the Busted Butte Unsaturated Zone Transport Test (UZTT) and documents the progress of construction activities and site and laboratory characterization activities undertaken in fiscal year 1998. Also presented are predictive flow-and-transport simulations for Test Phases 1 and 2 of testing and the preliminary results and status of these test phases. Future anticipated results obtained from unsaturated-zone (UZ) transport testing in the Calico Hills Formation at Busted Butte are also discussed in view of their importance to performance assessment (PA) needs to build confidence in and reduce the uncertainty of site-scale flow-and-transport models and their abstractions for performance for license application. The principal objectives of the test are to address uncertainties associated with flow and transport in the UZ site-process models for Yucca Mountain, as identified by the PA working group in February 1997. These include but are not restricted to: (1) The effect of heterogeneities on flow and transport in unsaturated and partially saturated conditions in the Calico Hills Formation. In particular, the test aims to address issues relevant to fracture-matrix interactions and permeability contrast boundaries; (2) The migration behavior of colloids in fractured and unfractured Calico Hills rocks; (3) The validation through field testing of laboratory sorption experiments in unsaturated Calico Hills rocks; (4) The evaluation of the 3-D site-scale flow-and-transport process model (i.e., equivalent-continuum/dual-permeability/discrete-fracture-fault representations of flow and transport) used in the PA abstractions for license application; and (5) The effect of scaling from lab scale to field scale and site scale

Field testing a soil site field guide for Allegheny hardwoods

Science.gov (United States)

S.B. Jones

1991-01-01

A site quality evaluation decision model, developed for Allegheny hardwoods on the non-glaciated Allegheny Plateau of Pennsylvania and New York, was field tested by International Paper (IP) foresters and the author, on sites within the region of derivation and on glaciated sites north and west of the Wisconsin drift line. Results from the field testing are presented...

Interpreting Results from the Standardized UXO Test Sites

National Research Council Canada - National Science Library

May, Michael; Tuley, Michael

2007-01-01

...) and the Environmental Security Technology Certification Program (ESCTP) to complete a detailed analysis of the results of testing carried out at the Standardized Unexploded Ordnance (UXO) Test Sites...

Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

Energy Technology Data Exchange (ETDEWEB)

None

1980-02-01

This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm/sup 2/ of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm/sup 2/. The other three spots are 100 cm/sup 2/ or less. The beta-gamma readings at these spots are 8.4 x 10/sup 2/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/ and 8.5 x 10/sup 4/ dis/min-100 cm/sup 2/. No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer.

Tritium activities in selected wells on the Nevada Test Site

International Nuclear Information System (INIS)

Lyles, B.F.

1993-05-01

Literature and data were reviewed related to radionuclides in groundwater on and near the Nevada Test Site. No elevated tritium activities have been reported outside of the major testing regions of the Nevada Test Site. Three wells were identified as having water with above-background (>50 pCi/l) tritium activities: UE-15d Water Well; USGS Water Well A; and USGS Test Well B Ex. Although none of these wells have tritium activities greater than the Nevada State Drinking Water standard (20,000 pCi/l), their time-series tritium trends may be indicative to potential on-site radionuclide migration

Improving ATLAS grid site reliability with functional tests using HammerCloud

Science.gov (United States)

Elmsheuser, Johannes; Legger, Federica; Medrano Llamas, Ramon; Sciacca, Gianfranco; van der Ster, Dan

2012-12-01

With the exponential growth of LHC (Large Hadron Collider) data in 2011, and more coming in 2012, distributed computing has become the established way to analyse collider data. The ATLAS grid infrastructure includes almost 100 sites worldwide, ranging from large national computing centers to smaller university clusters. These facilities are used for data reconstruction and simulation, which are centrally managed by the ATLAS production system, and for distributed user analysis. To ensure the smooth operation of such a complex system, regular tests of all sites are necessary to validate the site capability of successfully executing user and production jobs. We report on the development, optimization and results of an automated functional testing suite using the HammerCloud framework. Functional tests are short lightweight applications covering typical user analysis and production schemes, which are periodically submitted to all ATLAS grid sites. Results from those tests are collected and used to evaluate site performances. Sites that fail or are unable to run the tests are automatically excluded from the PanDA brokerage system, therefore avoiding user or production jobs to be sent to problematic sites.

Nevada Test Site Radiological Control Manual, Revision 1

International Nuclear Information System (INIS)

2010-01-01

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. The NTS is located in Nye County, Nevada. The NTS is located approximately 105 kilometers (65 miles) northwest of Las Vegas. It is a remote facility that covers approximately 3,500 square kilometers (1,375 square miles) of land. The dimensions of the NTS vary from 46 to 56 kilometers (28 to 35 miles) in width (eastern to western border) and from 64 to 88 kilometers (40 to 55 miles) in length (northern to southern border). The NTS is surrounded to the west, north, and east by additional thousands of acres of land withdrawn from the public domain for use as a protected wildlife range and as a military gunnery range. These public exclusion areas comprise the Nellis Air Force Range complex, previously designated as the Nellis Air Force Base Bombing and Gunnery Range, and the Tonopah Test Range. These two areas provide a buffer zone between the test areas and public lands administered by the Federal Bureau of Land

Draft Underground Test Plan for site characterization and testing in an exploratory shaft facility in salt

International Nuclear Information System (INIS)

1987-05-01

An exploratory shaft facility (ESF) at the Deaf Smith County, Texas is a potential candidate repository site in salt. This program of underground testing constitutes part of the effort to determine site suitability, provide data for repository design and performance assessment, and prepare licensing documentation. This program was developed by defining the information needs, as derived from the governing regulatory requirements and associated performance issues; evaluating the efficacy of available tests in satisfying the information needs; and selecting the suite of underground tests that are most cost-effective and timely, considering the other surface-based, surface borehole, and laboratory test programs. Tests are described conceptually, categorized in terms of geology, geomechanics, thermomechanics, geohydrology, or geochemistry, and range in scope from site characterization to site/engineered system interactions. The testing involves construction testing, conducted in the shafts during construction, and in situ testing at depth, conducted in the shafts and in the at-depth test facility at the repository horizon after shaft connection. 41 refs., 67 figs., 16 tabs

Nevada Test Site Radiation Protection Program

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers' Council, Nevada Test Site

2007-08-09

Title 10 Code of Federal Regulations (CFR) 835, 'Occupational Radiation Protection', establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (onsite or offsite) DOE National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration offsite projects.

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

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

2005-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

An integrated building demolition and waste planning model for the Fernald Site

International Nuclear Information System (INIS)

Hampshire, L.H.; Clark, T.R.; Frost, M.L.; Reising, J.W.

1995-01-01

The Fernald DOE site will begin full-scale remediation of buildings under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) during the 1995 fiscal year pursuant to a signed Record of Decision. This effort is currently estimated to cost $350 million and span a minimum duration of 8 years, if funding is not a constraint. The identification of the most viable sequence and schedule for the effort involved the development of an integrated planning model and the commissioning of a sitewide planning team. The resulting work product represents the best combination of assumptions and calculations possible at this time and provides information necessary for compliance with the CERCLA Remedial Design documentation requirements for the over 230 component structures governed by the decision. Sequence and integrated schedule development for the decontamination and dismantlement (D ampersand D) of Fernald structures has involved evaluation of current and future utilization of structures, availability of waste storage and staging space, the needs and impacts of other on-going Fernald projects, Resource Conservation and Recovery Act (RCRA) waste management and remediation projects, the layout of site utilities, site hydrology, and the potential sizing, location, and construction rates for an on-property disposal cell

Solar radiation for buildings application: comparing reduced data set for mediterranean sites

International Nuclear Information System (INIS)

La Gennusa, M.; Rizzo, G.; Scaccianoce, G.; Sorrentino, G.

2006-01-01

A growing diffusion of computer programs for the thermal simulation of buildings is occurring in the last year; they allow the description of the thermal behaviour of buildings during the year, in order to verify their energy efficiencies and to suggest eventual improvements, even at the design stage. These thermal simulation programs generally need a complete input data set and among these, information particularly referring to the climatic conditions of the site where the building will be built-up. As it is well known, a climatic issue, particularly important for the thermal energy balance, is the solar radiation. In this work we have updated a short reference year of the solar radiation, more precisely the Monthly Average Day (MAD) for a town of the Southern Italy (Palermo), which shows climatic features similar to other places in the Mediterranean basin. In addition, we have compared the climatic data of the MAD (for the global and diffuse solar radiations) obtained from hourly measures for seven years, with those obtained both from geo-astronomical parameters and from the monthly average of the daily global solar radiation, which is commonly adopted on purposes. The comparison does suggest a particular caution in the choice of the method used for generating reduced data sets of the solar radiation for these mediterranean.(Author)

Ambient Vibrations Measurements and 1D Site Response Modelling as a Tool for Soil and Building Properties Investigation

Directory of Open Access Journals (Sweden)

Sebastiano Imposa

2018-03-01

Full Text Available The safety of historic buildings heritage is an important task that becomes more substantial when the buildings are directed to educational purposes. The present study aims at evaluating the dynamic features of the Benedettini complex, an historic monastery located in downtown Catania, which is at present the headquarters of the humanistic studies department of the University of Catania. Both the building’s complex response to a seismic input and the soil-to-structure interaction were investigated using ambient noise recordings. The results point out a multiple dynamic behaviour of the monastery structure that shows several oscillation modes, whereas the identification of a single natural frequency can be observed in some sites where the structure can more freely oscillate. This observation is also confirmed by the variability of computed damping values that appear linked to the different rigidity of the structure, as a function of the either the longitudinal or transversal orientation of the investigated structural elements. Moreover, the comparison between the building’s fundamental period and spectral ratios frequencies, which were obtained from free field ambient noise measurements located outside the monastery, outline the presence of potential resonance effects between the site and structure during a seismic event. Numerical modelling of the local seismic response confirms the obtained experimental site frequencies, setting into evidence that higher amplification factors are reached in the same frequency range characterizing the building.

Site selection report basalt waste isolation program near-surface test facility

International Nuclear Information System (INIS)

Sharpe, S.D.

1978-01-01

A site selection committee was established to review the information gathered on potential sites and to select a site for the Near-Surface Test Facility Phase I. A decision was made to use a site on the north face of Gable Mountain located on the Hanford Site. This site provided convenient access to the Pomona Basalt Flow. This flow was selected for use at this site because it exhibited the characteristics established in the primary criteria. These criteria were: the flows thickness; its dryness; its nearness to the surface; and, its similarities to basalt units which are candidates for the repository. After the selection of the Near-Surface Test Facility Phase I Site, the need arose for an additional facility to demonstrate safe handling, storage techniques, and the physical effects of radioactive materials on an in situ basalt formation. The committee reviewed the sites selected for Phase I and chose the same site for locating Phase II of the Near-Surface Test Facility

Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

International Nuclear Information System (INIS)

Dean, L.N.

1994-02-01

Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D ampersand D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project

Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

Energy Technology Data Exchange (ETDEWEB)

Dean, L.N. [Advanced Sciences, Inc., (United States)

1994-02-01

Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

Hanford Site physical separations CERCLA treatability test plan

International Nuclear Information System (INIS)

1992-03-01

This test plan describes specifications, responsibilities, and general procedures to be followed to conduct a physical separations soil treatability test in the North Process Pond of the 300-FF-1 Operable Unit at the Hanford Site, Washington. The objective of this test is to evaluate the use of physical separation systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions and thereby minimizing waste volumes. If successful the technology could be applied to clean up millions of cubic meters of contaminated soils in waste sites at Hanford and other sites. It is not the intent of this test to remove contaminated materials from the fine soils. Physical separation is a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils. Organic contaminants are expected to be insignificant for the 300-FF-I Operable Unit test, and further removal of metals and radioactive contaminants from the fine fraction of soils will require secondary treatment such as chemical extraction, electromagnetic separation, or other technologies. Additional investigations/testing are recommended to assess the economic and technical feasibility of applying secondary treatment technologies, but are not within the scope of this test. This plan provides guidance and specifications for the treatability test to be conducted as a service contract. More detailed instructions and procedures will be provided as part of the vendors (sellers) proposal. The procedures will be approved by Westinghouse Hanford Company (Westinghouse Hanford) and finalized by the seller prior to initiating the test

Hydrogeologic testing plan for Deep Hydronest Test Wells, Deaf Smith County site, Texas

International Nuclear Information System (INIS)

1987-12-01

This report discusses methods of hydraulic testing which are recommended for use in the Deep Hydronest Test Wells at the proposed high level nuclear waste repository site in Deaf Smith County, Texas. The deep hydronest wells are intended to provide geologic, geophysical and hydrologic information on the interval from the Upper San Andres Formation to the base of the Pennsylvanian system at the site. Following the period of drilling and testing, the wells will be converted into permanent monitoring installations through which fluid pressures and water quality can be monitored at various depths in the section. 19 refs., 17 figs., 2 tabs

Risk factors for cardiovascular diseases among male workers of building construction site in Delhi

Directory of Open Access Journals (Sweden)

Mamta Parashar

2017-01-01

Full Text Available Background: Cardiovascular disease (CVD is mainly attributable to a combination of risk factors (RFs: tobacco use, alcohol use, high blood pressure, diabetes, unhealthy diet, and obesity which are amenable to interventions. Building construction workers are poor and vulnerable. They are also the victims of adverse working environmental conditions and subjected to health hazards of occupational origin. Objective: The aim was to study the RFs and associated sociodemographics for CVD among construction site workers. Materials and Methods: This cross-sectional study was conducted among construction site workers. A total of 172 male workers over the age of 18 years were included in the study. Modified World Health Organization Step-wise approach to chronic disease RF surveillance was used to collect data. The data were analyzed in SPSS version 17 and the Chi-square test was applied to analyze the qualitative data. Results: At least one RF for CVD was present in all the subjects, with majority (93.6% of them having at least two RFs. The presence of the RFs (moderate to high, 3–11 was found to be significantly associated with lower income group, unskilled workers, migration year <1, alcoholics, personal tobacco use, family history of tobacco use, and the low knowledge score regarding tobacco use (0–2. Conclusions: Community-based comprehensive behavioral and life style communication package should be established for workers to reduce the modifiable RFs of CVD.

Preliminary site design for the SP-100 ground engineering test

International Nuclear Information System (INIS)

Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

1986-04-01

In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990

Status of the flora and fauna on the Nevada Test Site, 1992

International Nuclear Information System (INIS)

Hunter, R.B.

1994-03-01

This report documents changes in the populations of plants and animals on the Nevada Test Site (NTS) for calendar year 1992. It is part of a Department of Energy (DOE) program (Basic Environmental Compliance and Monitoring Program -- BECAMP) that also includes monitoring DOE compliance with the Endangered Species Act, the Historic Preservation Act, and the American Indian Freedom of Religion Act. Ecological studies were to comply with the National Environmental Policy Act and DOE Order 5400.1, ''General Environmental Protection Program.'' These studies focused on the following: status of ephemeral plants on the Nevada Test Site, 1992; status of reptile and amphibian populations on the Nevada Test Site, 1992; trends in small mammal populations on the Nevada Test Site, 1992; status of large mammals and birds at Nevada Test Site, 1992; and status of perennial plants on the Nevada Test Site, 1992

Buffer mass test - Site documentation

International Nuclear Information System (INIS)

Pusch, R.

1983-10-01

The purpose of this report is to compile test site data that are assumed to be of importance for the interpretation of the Buffer Mass Test. Since this test mainly concerns water uptake and migration processes in the integrated rock/backfill system and the development of temperature fields in this system, the work has been focused on the constitution and hydrology of the rock. The major constitutional rock feature of interest for the BMT is the frequency and distribution of joints and fractures. The development of models for water uptake into the highly compacted bentonite in the heater holes requires a very detailed fracture survey. The present investigation shows that two of the holes (no. 1 and 2) are located in richly fractured rock, while the others are located in fracture-poor to moderately fractured rock. The hydrological conditions of the rock in the BMT area are characterized by water pressures of as much as 100 m water head at a few meters distance from the test site. The average hydraulic conductivity of the rock that confines the BMT tunnel has been estimated at about 10 -10 m/s by Lawrence Laboratory. The actual distribution of the water that enters the tunnel has been estimated by observing the successive moistening after having switched off the ventilation, and this has offered basis of predicting the rate and uniformity of the water uptake in the tunnel backfill. As to the heater holes the detailed fracture patterns and various inflow measurements have yielded a similar basis. The report also gives major data on the rock temperature, gas conditions, mineralogy, rock mechanics, and groundwater chemistry for BMT purposes. (author)

Long-term monitoring and field testing of an innovative multistory timber building

Science.gov (United States)

Omenzetter, Piotr; Morris, Hugh; Worth, Margaret; Kohli, Varun; Uma, S. R.

2011-04-01

An innovative three-story timber building, using self-centering, post-tensioned timber shear walls as the main horizontal load resisting system and lightweight composite timber-concrete floors, has recently been completed in Nelson, New Zealand. It is expected to be the trailblazer for similar but taller structures to be more widely adopted. Performance based standards require an advanced understanding of building responses and in order to meet the need for in-situ performance data the building has been subjected to forced vibration testing and instrumented for continuous monitoring using a total of about 90 data channels to capture its dynamic and long-term responses. The first part of the paper presents a brief discussion of the existing research on the seismic performance of timber frame buildings and footfall induced floor vibrations. An outline of the building structural system, focusing on the novel design solutions, is then discussed. This is followed by the description of the monitoring system. The paper emphasizes the need for optimal placement of a limited number of sensors and demonstrates how this was achieved for monitoring floor vibrations with the help of the effective independence-driving point residue (EfI-DPR) technique. A novel approach to the EfI-DPR method proposed here uses a combinatorial search algorithm that increases the chances of obtaining the globally optimal solution. Finally, the results from the forced vibration tests conducted on the whole building at different construction stages are reviewed.

LLNL Experimental Test Site (Site 300) Potable Water System Operations Plan

Energy Technology Data Exchange (ETDEWEB)

Ocampo, R. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-09-14

The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

The verification tests of residual radioactivity measurement and assessment techniques for buildings and soils

International Nuclear Information System (INIS)

Onozawa, T.; Ishikura, T.; Yoshimura, Yukio; Nakazawa, M.; Makino, S.; Urayama, K.; Kawasaki, S.

1996-01-01

According to the standard procedure for decommissioning a commercial nuclear power plant (CNPP) in Japan, controlled areas will be released for unrestricted use before the dismantling of a reactor building. If manual survey and sampling techniques were applied to measurement for unrestricted release on and in the extensive surface of the building, much time and much specialized labor would be required to assess the appropriateness of the releasing. Therefore the authors selected the following three techniques for demonstrating reliability and applicability of the techniques for CNPPs: (1) technique of assessing radioactive concentration distribution on the surface of buildings (ADB); (2) technique of assessing radioactive permeation distribution in the concrete structure of buildings (APB); (3) technique of assessing radioactive concentration distribution in soil (ADS). These tests include the techniques of measuring and assessing very low radioactive concentration distribution on the extensive surfaces of buildings and the soil surrounding of a plant with automatic devices. Technical investigation and preliminary study of the verification tests were started in 1990. In the study, preconditions were clarified for each technique and the performance requirements were set up. Moreover, simulation models have been constructed for several feasible measurement method to assess their performance in terms of both measurement test and simulation analysis. Fundamental tests have been under way using small-scale apparatuses since 1994

A Test Method for Monitoring Modulus Changes during Durability Tests on Building Joint Sealants

Science.gov (United States)

Christopher C. White; Donald L. Hunston; Kar Tean Tan; Gregory T. Schueneman

2012-01-01

The durability of building joint sealants is generally assessed using a descriptive methodology involving visual inspection of exposed specimens for defects. It is widely known that this methodology has inherent limitations, including that the results are qualitative. A new test method is proposed that provides more fundamental and quantitative information about...

TC-13 Mod 0 and Mod 2 Steam Catapult Test Site

Data.gov (United States)

Federal Laboratory Consortium — Located on 11,000 feet of test runway, the TC-13 Mod 0 and Mod 2 Steam Catapult Test Site has in-ground catapults identical to those aboard carriers. This test site...

Shake Table Testing of an Elevator System in a Full-Scale Five-Story Building.

Science.gov (United States)

Wang, Xiang; Hutchinson, Tara C; Astroza, Rodrigo; Conte, Joel P; Restrepo, José I; Hoehler, Matthew S; Ribeiro, Waldir

2017-03-01

This paper investigates the seismic performance of a functional traction elevator as part of a full-scale five-story building shake table test program. The test building was subjected to a suite of earthquake input motions of increasing intensity, first while the building was isolated at its base, and subsequently while it was fixed to the shake table platen. In addition, low-amplitude white noise base excitation tests were conducted while the elevator system was placed in three different configurations, namely, by varying the vertical location of its cabin and counterweight, to study the acceleration amplifications of the elevator components due to dynamic excitations. During the earthquake tests, detailed observation of the physical damage and operability of the elevator as well as its measured response are reported. Although the cabin and counterweight sustained large accelerations due to impact during these tests, the use of well-restrained guide shoes demonstrated its effectiveness in preventing the cabin and counterweight from derailment during high-intensity earthquake shaking. However, differential displacements induced by the building imposed undesirable distortion of the elevator components and their surrounding support structure, which caused damage and inoperability of the elevator doors. It is recommended that these aspects be explicitly considered in elevator seismic design.

The regulatory basis for site selection for radioactive buildings

International Nuclear Information System (INIS)

Sirag, N.M.

2012-01-01

The architectural bases and the design standard for radiation research buildings differ than other research building, that the nature of the used radioactive materials in the nature of the carried an work in the building will decide the planning in the design of the building, and we shall discus in this research what already had been reached of results about the architectural bases in the used standard in the used safe design of research building and establishing design standard, that archaistic rely upon when designing these project which have specific and special characters

HEAPA Filter Bank In-Place Leak Test of Advanced Fuel Science Building

Energy Technology Data Exchange (ETDEWEB)

Ji, C. G.; Bae, S. O.; Kim, C. H

2007-12-15

To maintain the optimum condition of Advanced Fuel Science Building in KAERI, this report is described leak tests for HEPA Filter of HVAC in this facility. The main topics of this report are as follows for: - Procurement Specification - Visual Inspection - Airflow Capacity Test - HEPA Filter Bank In-Place Test.

Semi-automatic building extraction in informal settlements from high-resolution satellite imagery

Science.gov (United States)

Mayunga, Selassie David

The extraction of man-made features from digital remotely sensed images is considered as an important step underpinning management of human settlements in any country. Man-made features and buildings in particular are required for varieties of applications such as urban planning, creation of geographical information systems (GIS) databases and Urban City models. The traditional man-made feature extraction methods are very expensive in terms of equipment, labour intensive, need well-trained personnel and cannot cope with changing environments, particularly in dense urban settlement areas. This research presents an approach for extracting buildings in dense informal settlement areas using high-resolution satellite imagery. The proposed system uses a novel strategy of extracting building by measuring a single point at the approximate centre of the building. The fine measurement of the building outlines is then effected using a modified snake model. The original snake model on which this framework is based, incorporates an external constraint energy term which is tailored to preserving the convergence properties of the snake model; its use to unstructured objects will negatively affect their actual shapes. The external constrained energy term was removed from the original snake model formulation, thereby, giving ability to cope with high variability of building shapes in informal settlement areas. The proposed building extraction system was tested on two areas, which have different situations. The first area was Tungi in Dar Es Salaam, Tanzania where three sites were tested. This area is characterized by informal settlements, which are illegally formulated within the city boundaries. The second area was Oromocto in New Brunswick, Canada where two sites were tested. Oromocto area is mostly flat and the buildings are constructed using similar materials. Qualitative and quantitative measures were employed to evaluate the accuracy of the results as well as the performance

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class-C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types. The paper discusses site selection; establishment of the Radioactive Waste Management Project; operations with respect to low-level radioactive wastes, transuranic waste storage, greater confinement disposal test, and mixed waste management facility; and related research activities such as tritium migration studies, revegetation studies, and in-situ monitoring of organics

Nevada Test Site Area 25, Radiological Survey and Cleanup Project, 1974-1983 (a revised final report). Revision 1

International Nuclear Information System (INIS)

Miller, M.G.

1984-12-01

This report describes the radiological survey, decontamination and decommissioning (D and D) of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for beta plus gamma and alpha radioactive contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 9 references, 23 figures

Evaluation of the radionuclide tracer test conducted at the project Gnome Underground Nuclear Test Site, New Mexico

International Nuclear Information System (INIS)

Pohll, G.; Pohlmann, K.

1996-08-01

A radionuclide tracer test was conducted in 1963 by the U.S. Geological Survey at the Project Gnome underground nuclear test site, approximately 40 km southeast of Carlsbad, New Mexico. The tracer study was carried out under the auspices of the U.S. Atomic Energy Commission (AEC) to study the transport behavior of radionuclides in fractured rock aquifers. The Culebra Dolomite was chosen for the test because it was considered to be a reasonable analogue of the fractured carbonate aquifer at the Nevada Test Site (NTS), the principal location of U.S. underground nuclear tests. Project Gnome was one of a small number of underground nuclear tests conducted by the AEC at sites distant from the NTS. The Gnome device was detonated on December 10, 1961 in an evaporate unit at a depth of 360 m below ground surface. Recently, the U.S. Department of Energy (DOE) implemented an environmental restoration program to characterize, remediate, and close these offsite nuclear test areas. An early step in this process is performance of a preliminary risk analysis of the hazard posed by each site. The Desert Research Institute has performed preliminary hydrologic risk evaluations for the groundwater transport pathway at Gnome. That evaluation included the radioactive tracer test as a possible source because the test introduced radionuclides directly into the Culebra Dolomite, which is the only aquifer at the site. This report presents a preliminary evaluation of the radionuclide tracer test as a source for radionuclide migration in the Culebra Dolomite. The results of this study will assist in planning site characterization activities and refining estimates of the radionuclide source for comprehensive models of groundwater transport st the Gnome site

Definitive design status of the SP-100 Ground Engineering System Test Site

International Nuclear Information System (INIS)

Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

1989-05-01

The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper

Definitive design status of the SP-100 Ground Engineering System Test Site

Energy Technology Data Exchange (ETDEWEB)

Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

1989-05-01

The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper.

Hanford tank initiative test facility site selection study

International Nuclear Information System (INIS)

Staehr, T.W.

1997-01-01

The Hanford Tanks Initiative (HTI) project is developing equipment for the removal of hard heel waste from the Hanford Site underground single-shell waste storage tanks. The HTI equipment will initially be installed in the 241-C-106 tank where its operation will be demonstrated. This study evaluates existing Hanford Site facilities and other sites for functional testing of the HTI equipment before it is installed into the 241-C-106 tank

Nevada Test Site, Nye County, Nevada. Final environmental impact statement

International Nuclear Information System (INIS)

1977-09-01

This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static

Nevada Test Site, Nye County, Nevada. Final environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-09-01

This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static.

Resource Conservation and Recovery Act Industrial Sites quality assurance project plan: Nevada Test Site, Nevada

International Nuclear Information System (INIS)

1994-06-01

This quality assurance project plan (QAPjP) describes the measures that shall be taken to ensure that the environmental data collected during characterization and closure activities of Resource Conservation and Recovery Act (RCRA) Industrial Sites at the Nevada Test Site (NTS) are meaningful, valid, defensible, and can be used to achieve project objectives. These activities are conducted by the US Department of Energy Nevada Operations Office (DOE/NV) under the Nevada Environmental Restoration (ER) Project. The Nevada ER Project consists of environmental restoration activities on the NTS, Tonopah Test Range, Nellis Air Force Range, and eight sites in five other states. The RCRA Industrial Sites subproject constitutes a component of the Nevada ER Project. Currently, this QAPjP is limited to the seven RCRA Industrial Sites identified within this document that are to be closed under an interim status and pertains to all field- investigation, analytical-laboratory, and data-review activities in support of these closures. The information presented here supplements the RCRA Industrial Sites Project Management Plan and is to be used in conjunction with the site-specific subproject sampling and analysis plans

Integrated leak rate testing of the fast flux test facility reactor containment building

International Nuclear Information System (INIS)

James, E.B.; Farabee, O.A.; Bliss, R.J.

1978-01-01

The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipment was operating properly and it was sensitive enough to detect leaks at low pressures. This ILRT was performed at a lower pressure than any previous ILRT on a reactor containment structure in the United States. While the initial design requirements for ice condenser containments called for a part pressure test at 6 psig, the tests were waived due to the apparent statistical problems of data analysis and the repeatability of the data itself at such low pressure. In contrast to this belief, both the 5 and 10 psig ILRT's were performed in a successful manner at FFTF

Waste generation and pollution prevention progress fact sheet: Nevada Test Site

International Nuclear Information System (INIS)

1994-01-01

The Nevada Test Site is responsible for maintaining nuclear testing capability, supporting science-based Stockpile Stewardship experiments, maintaining nuclear agency response capability, applying environmental restoration techniques to areas affected by nuclear testing, managing low-level and mixed radioactive waste, investigating demilitarization technologies, investigating counter- proliferation technologies, supporting work-for-others programs and special Department of Defense activities, operating a hazardous materials spill test center, and providing for the commercial development of the site. This fact sheet provides information on routine waste generation and projected reduction by waste type. Also, materials recycled by the Nevada Test Site in 1994 are listed

Building Social Web Applications

CERN Document Server

Bell, Gavin

2009-01-01

Building a web application that attracts and retains regular visitors is tricky enough, but creating a social application that encourages visitors to interact with one another requires careful planning. This book provides practical solutions to the tough questions you'll face when building an effective community site -- one that makes visitors feel like they've found a new home on the Web. If your company is ready to take part in the social web, this book will help you get started. Whether you're creating a new site from scratch or reworking an existing site, Building Social Web Applications

Are Biophilic-Designed Site Office Buildings Linked to Health Benefits and High Performing Occupants?

Directory of Open Access Journals (Sweden)

Tonia Gray

2014-11-01

Full Text Available This paper discusses the first phase of a longitudinal study underway in Australia to ascertain the broad health benefits of specific types of biophilic design for workers in a building site office. A bespoke site design was formulated to include open plan workspace, natural lighting, ventilation, significant plants, prospect and views, recycled materials and use of non-synthetic materials. Initial data in the first three months was gathered from a series of demographic questions and from interviews and observations of site workers. Preliminary data indicates a strong positive effect from incorporating aspects of biophilic design to boost productivity, ameliorate stress, enhance well-being, foster a collaborative work environment and promote workplace satisfaction, thus contributing towards a high performance workspace. The longitudinal study spanning over two years will track human-plant interactions in a biophilic influenced space, whilst also assessing the concomitant cognitive, social, psychological and physical health benefits for workers.

Nevada Test Site Environmental Report Summary 2009

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). NNSA/NSO prepares the Nevada Test Site Environmental Report (NTSER) to provide the public an understanding of the environmental monitoring and compliance activities that are conducted on the NTS to protect the public and the environment from radiation hazards and from nonradiological impacts. The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. This summary provides an abbreviated and more readable version of the NTSER. It does not contain detailed descriptions or presentations of monitoring designs, data collection methods, data tables, the NTS environment, or all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

Influence of turbulence, orientation, and site configuration on the response of buildings to extreme wind.

Science.gov (United States)

Aly, Aly Mousaad

2014-01-01

Atmospheric turbulence results from the vertical movement of air, together with flow disturbances around surface obstacles which make low- and moderate-level winds extremely irregular. Recent advancements in wind engineering have led to the construction of new facilities for testing residential homes at relatively high Reynolds numbers. However, the generation of a fully developed turbulence in these facilities is challenging. The author proposed techniques for the testing of residential buildings and architectural features in flows that lack fully developed turbulence. While these methods are effective for small structures, the extension of the approach for large and flexible structures is not possible yet. The purpose of this study is to investigate the role of turbulence in the response of tall buildings to extreme winds. In addition, the paper presents a detailed analysis to investigate the influence of upstream terrain conditions, wind direction angle (orientation), and the interference effect from the surrounding on the response of high-rise buildings. The methodology presented can be followed to help decision makers to choose among innovative solutions like aerodynamic mitigation, structural member size adjustment, and/or damping enhancement, with an objective to improve the resiliency and the serviceability of buildings.

Influence of Turbulence, Orientation, and Site Configuration on the Response of Buildings to Extreme Wind

Science.gov (United States)

2014-01-01

Atmospheric turbulence results from the vertical movement of air, together with flow disturbances around surface obstacles which make low- and moderate-level winds extremely irregular. Recent advancements in wind engineering have led to the construction of new facilities for testing residential homes at relatively high Reynolds numbers. However, the generation of a fully developed turbulence in these facilities is challenging. The author proposed techniques for the testing of residential buildings and architectural features in flows that lack fully developed turbulence. While these methods are effective for small structures, the extension of the approach for large and flexible structures is not possible yet. The purpose of this study is to investigate the role of turbulence in the response of tall buildings to extreme winds. In addition, the paper presents a detailed analysis to investigate the influence of upstream terrain conditions, wind direction angle (orientation), and the interference effect from the surrounding on the response of high-rise buildings. The methodology presented can be followed to help decision makers to choose among innovative solutions like aerodynamic mitigation, structural member size adjustment, and/or damping enhancement, with an objective to improve the resiliency and the serviceability of buildings. PMID:24701140

Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2011-09-29

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.

Nevada Test Site annual site environmental report for calendar year 1998

International Nuclear Information System (INIS)

Black, S.C.; Townsend, Y.E.

1999-01-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations

Traffic restrictions: Meyrin site and entrance of Prévessin site

CERN Multimedia

GS Department

2010-01-01

Between 10 April and 19 April 2010 a number of roads on the Meyrin site and at the entrance of the Prévessin site will be resurfaced. The work will be done by zones, as shown below: 12-14 April Intersection of Route Fermi and Route Gregory. Route Fermi, between Building 268 and Route Jentschke Route Fermi, Route Jentschke and Route Einstein, up to Building 593 and between Buildings 194 and 555. Plus Route Oppenheimer. 15 April Intersection of Route Bloch and Route Maxwell, and Route Maxwell itself. Route Sherrer between the overhead walkway (Building 50) and the exit from the carpark behind Building 4. 16 April and 19 April Route Fermi, Route Jentschke and Route Einstein, up to Building 593 and between Buildings 194 and 555. Prévessin site: from Route Adams to the access control Building. The construction works may result in some disruption to traffic. Users are requested to comply with the temporary traffic signs and arrangements.  Thank you for your understanding. GS/...

On-site tests on the nuclear power plants

International Nuclear Information System (INIS)

Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

1996-01-01

On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

Plutonium Particle Migration in the Shallow Vadose Zone: The Nevada Test Site as an Analog Site

Science.gov (United States)

Hunt, J. R.; Smith, D. K.

2004-12-01

The upper meter of the vadose zone in desert environments is the horizon where wastes have been released and human exposure is determined through dermal, inhalation, and food uptake pathways. This region is also characterized by numerous coupled processes that determine contaminant transport, including precipitation infiltration, evapotranspiration, daily and annual temperature cycling, dust resuspension, animal burrowing, and geochemical weathering reactions. While there is considerable interest in colloidal transport of minerals, pathogenic organisms, and contaminants in the vadose zone, there are limited field sites where the actual occurrence of contaminant migration can be quantified over the appropriate spatial and temporal scales of interest. At the US Department of Energy Nevada Test Site, there have been numerous releases of radionuclides since the 1950's that have become field-scale tracer tests. One series of tests was the four safety shots conducted in an alluvial valley of Area 11 in the 1950's. These experiments tested the ability of nuclear materials to survive chemical explosions without initiating fission reactions. Four above-ground tests were conducted and they released plutonium and uranium on the desert valley floor with only one of the tests undergoing some fission. Shortly after the tests, the sites were surveyed for radionuclide distribution on the land surface using aerial surveys and with depth. Additional studies were conducted in the 1970's to better understand the fate of plutonium in the desert that included studies of depth distribution and dust resuspension. More recently, plutonium particle distribution in the soil profile was detected using autoradiography. The results to date demonstrate the vertical migration of plutonium particles to depths in excess of 30 cm in this arid vadose zone. While plutonium migration at the Nevada Test Site has been and continues to be a concern, these field experiments have become analog sites for the

Intra-site Secure Transport Vehicle test and evaluation

International Nuclear Information System (INIS)

Scott, S.

1995-01-01

In the past many DOE and DoD facilities involved in handling nuclear material realized a need to enhance the safely and security for movement of sensitive materials within their facility, or ''intra-site''. There have been prior efforts to improve on-site transportation; however, there remains a requirement for enhanced on-site transportation at a number of facilities. The requirements for on-site transportation are driven by security, safety, and operational concerns. The Intra-site Secure Transport Vehicle (ISTV) was designed to address these concerns specifically for DOE site applications with a standardized vehicle design. This paper briefly reviews the ISTV design features providing significant enhancement of onsite transportation safety and security, and also describes the test and evaluation activities either complete of underway to validate the vehicle design and operation

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

Nuclear Materials Management for the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Jesse C. Schreiber

2007-01-01

The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

AP1000 shield building: a constructability challenge

International Nuclear Information System (INIS)

Di Giuseppe, Giovanni; Bonanno, Domenico

2010-01-01

The AP1000 Shield Building, an enhanced structure which surrounds the containment vessel, consists of standard Reinforced Concrete (RC) and composite Steel and Concrete (SC) construction. In the SC module the surface steel plates, (with attached shear studs and angles) filled with concrete, act as the steel reinforcement in concrete. This is a relatively new design technology that required the appropriate use of structural codes, supplemented with information from applicable tests on similar composite steel and concrete construction. Being a newer design concept, existing codes do not provide explicit guidance on SC construction so a review of literature and test data on composite structures similar to AP1000 shield building was done in order to confirm the technical basis for the design. The SC walls, air inlet structure and roof of the Shield Building will be constructed using modular construction practices and then transported to site and lifted into place. These modules, working also as permanent form-work, will be filled with high strength Self- Consolidating Concrete. (SCC) This paper provides a focused and integrated presentation of the enhanced shield building design methodology, testing, constructability and inspection. (authors)

Nevada Test Site Environmental Report 2005

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts

Nevada Test Site Environmental Report 2005

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

Green Building Tools for Tribes

Science.gov (United States)

Tribal green building tools and funding information to support tribal building code adoption, healthy building, siting, energy efficiency, renewable energy, water conservation, green building materials, recycling and adaptation and resilience.

Springs on the Nevada Test Site and their use by wildlife

International Nuclear Information System (INIS)

Giles, K.R.

1976-04-01

During August 1972, natural springs located on the Nevada Test Site were surveyed to determine the use by wildlife and the effort required for improving flow. Each spring is described and its use by wildlife noted. Methods of improving spring flow are suggested. It is believed that minimal effort at most of the springs would result in a significant improvement of waterflow with resulting benefits to wildlife. The intention of the recommendations in this report is to encourage development of the Nevada Test Site springs and to maintain the wildlife now at the Site. There is no recommendation to bring in or support wildlife outside the Nevada Test Site area

Pixel Detector Trial Assembly Test in the SR1 building

CERN Multimedia

D. Giugni

2004-01-01

During the last two months the Pixel group [LBL, Milan and Wuppertal] made a successful integration test on the mechanics of the barrel. The scope of the test was to qualify the integration procedures and the various assembling tools. The test took place in the clean room of the SR1 building at CERN, where the detector has been assembled around a dummy beam pipe made of Stainless Steel. The process is rather complex: the shells come in two parts and they have to be clamped together to get the full shell. This operation is carried out by a dedicated tool which is shown to the right in the picture below. The layer 1 shell is clamped around a "service" pipe that will be used for moving the full layer to the integration tool [ITT] which is visible on the left. View of the tools devoted to the Pixel barrel integration in the SR1 building Also visible in the picture is the global frame that is actually held by the tool. It will engage the layers sliding onto the rails. The first two layers are sequentially...

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types

Improving ATLAS grid site reliability with functional tests using HammerCloud

CERN Document Server

Legger, F; The ATLAS collaboration

2012-01-01

With the exponential growth of LHC (Large Hadron Collider) data in 2011, and more coming in 2012, distributed computing has become the established way to analyse collider data. The ATLAS grid infrastructure includes almost 100 sites worldwide, ranging from large national computing centers to smaller university clusters. These facilities are used for data reconstruction and simulation, which are centrally managed by the ATLAS production system, and for distributed user analysis. To ensure the smooth operation of such a complex system, regular tests of all sites are necessary to validate the site capability of successfully executing user and production jobs. We report on the development, optimization and results of an automated functional testing suite using the HammerCloud framework. Functional tests are short light-weight applications covering typical user analysis and production schemes, which are periodically submitted to all ATLAS grid sites. Results from those tests are collected and used to evaluate site...

The Road Side Unit for the A270 Test Site

NARCIS (Netherlands)

Passchier, I.; Driessen, B.J.F.; Heijligers, B.M.R.; Netten, B.D.; Schackmann, P.P.M.

2011-01-01

The design and implementation of the Road Side Unit for the A270 Test Site is presented. It consists of a sensor platform and V2I communication platform with full coverage of the test site. A service platform enables applications to make use of these facilities. The RSU will be used both for the

Sexually selected nest-building--Pomatoschistus minutus males build smaller nest-openings in the presence of sneaker males.

Science.gov (United States)

Svensson, O; Kvarnemo, C

2003-09-01

Both natural selection and sexual selection may act on nest-building. We tested experimentally how different regimes of egg-predation and male-male competition influence nest-building before mating, using the marine fish sand goby, Pomatoschistus minutus. Males with sneaker males present built the smallest nest-openings, smaller than males held alone or with Pomatoschistus microps males (which may predate eggs and compete over nest-sites but not compete over fertilizations). Males with visual access to other nest-building males tended also to build smaller openings than males held alone or with P. microps. Males with egg-predators present built nests with openings not differing significantly from any other treatment. Our results indicate that the small nest-openings found in the sneaker male treatment are sexually selected through protection against sneaking or by female choice. Across treatments, time span before a male started to build his nest also explained variation in nest-opening width; males starting late built larger nest-openings.

Assessment of three cuban sites for testing resistance to sugarcane mosaic virus

Directory of Open Access Journals (Sweden)

Yaquelin Puchades

2015-03-01

Full Text Available Sugarcane mosaic disease is amongst the world’s most important diseases affecting sugarcane worldwide. The objective was to assess the environmental conditions of the sites where the test for SCMV resistance is done. Multi-environment trial Data were analyzed using a Principal Components Analysis Eighteen sugarcane genotypes s were evaluated from the main testing sites in Cuba (Jovellanos, Florida, Mayarí . The information of the climatic conditions was recorded at local weather stations. The assessment of the sites was done by analyzing the main components. Results showed that the testing sites were different from one another, and proved that the environment strongly influences on the mosaic symptom manifestation. PCA was an excellent procedure to assess the testing sites .for SCMV resistance.

Plant integration of MITICA and SPIDER experiments with auxiliary plants and buildings on PRIMA site

Energy Technology Data Exchange (ETDEWEB)

Fellin, Francesco, E-mail: francesco.fellin@igi.cnr.it; Boldrin, Marco; Zaccaria, Pierluigi; Agostinetti, Piero; Battistella, Manuela; Bigi, Marco; Palma, Samuele Dal Bello Mauro Dalla; Fiorentin, Aldo; Luchetta, Adriano; Maistrello, Alberto; Marcuzzi, Diego; Ocello, Edoardo; Pasqualotto, Roberto; Pavei, Mauro; Pomaro, Nicola; Rizzolo, Andrea; Toigo, Vanni; Valente, Matteo; Zanotto, Loris; Calore, Luca; and others

2015-10-15

Highlights: • Focus on plant integration work supporting the realization of SPIDER and MITICA fusion experiments hosted in PRIMA buildings complex in Padova, Italy. • Huge effort of coordination and integration among many stakeholders, taking into account several constrains coming from experiments requirements (on-going) and precise time schedule and budget on buildings construction. • The paper also deals of interfaces management, coordination and integration of many competences, problems solving to find best solution also considering other aspects like safety and maintenance. - Abstract: This paper presents a description of the PRIMA (Padova Research on ITER Megavolt Accelerator) Plant Integration work, aimed at the construction of PRIMA Buildings, which will host two nuclear fusion test facilities named SPIDER and MITICA, finalized to test and optimize the neutral beam injectors for ITER experiment. These activities are very complex: inputs coming from the experiments design are changing time to time, while the buildings construction shall fulfill precise time schedule and budget. Moreover the decision process is often very long due to the high number of stakeholders (RFX, IO, third parties, suppliers, domestic agencies from different countries). The huge effort includes: forecasting what will be necessary for the integration of many experimental plants; collecting requirements and translating into inputs; interfaces management; coordination meetings with hundreds of people with various and different competences in construction and operation of fusion facilities, thermomechanics, electrical and control, buildings design and construction (civil plants plus architectural and structural aspects), safety, maintenance and management. The paper describes these activities and also the tools created to check and to validate the building design, to manage the interfaces and the organization put in place to achieve the required targets.

Plant integration of MITICA and SPIDER experiments with auxiliary plants and buildings on PRIMA site

International Nuclear Information System (INIS)

Fellin, Francesco; Boldrin, Marco; Zaccaria, Pierluigi; Agostinetti, Piero; Battistella, Manuela; Bigi, Marco; Palma, Samuele Dal Bello Mauro Dalla; Fiorentin, Aldo; Luchetta, Adriano; Maistrello, Alberto; Marcuzzi, Diego; Ocello, Edoardo; Pasqualotto, Roberto; Pavei, Mauro; Pomaro, Nicola; Rizzolo, Andrea; Toigo, Vanni; Valente, Matteo; Zanotto, Loris; Calore, Luca

2015-01-01

Highlights: • Focus on plant integration work supporting the realization of SPIDER and MITICA fusion experiments hosted in PRIMA buildings complex in Padova, Italy. • Huge effort of coordination and integration among many stakeholders, taking into account several constrains coming from experiments requirements (on-going) and precise time schedule and budget on buildings construction. • The paper also deals of interfaces management, coordination and integration of many competences, problems solving to find best solution also considering other aspects like safety and maintenance. - Abstract: This paper presents a description of the PRIMA (Padova Research on ITER Megavolt Accelerator) Plant Integration work, aimed at the construction of PRIMA Buildings, which will host two nuclear fusion test facilities named SPIDER and MITICA, finalized to test and optimize the neutral beam injectors for ITER experiment. These activities are very complex: inputs coming from the experiments design are changing time to time, while the buildings construction shall fulfill precise time schedule and budget. Moreover the decision process is often very long due to the high number of stakeholders (RFX, IO, third parties, suppliers, domestic agencies from different countries). The huge effort includes: forecasting what will be necessary for the integration of many experimental plants; collecting requirements and translating into inputs; interfaces management; coordination meetings with hundreds of people with various and different competences in construction and operation of fusion facilities, thermomechanics, electrical and control, buildings design and construction (civil plants plus architectural and structural aspects), safety, maintenance and management. The paper describes these activities and also the tools created to check and to validate the building design, to manage the interfaces and the organization put in place to achieve the required targets.

Overview of Low-Level Waste Disposal Operations at the Nevada Test Site

International Nuclear Information System (INIS)

2007-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future

Slope stability and bearing capacity of landfills and simple on-site test methods.

Science.gov (United States)

Yamawaki, Atsushi; Doi, Yoichi; Omine, Kiyoshi

2017-07-01

This study discusses strength characteristics (slope stability, bearing capacity, etc.) of waste landfills through on-site tests that were carried out at 29 locations in 19 sites in Japan and three other countries, and proposes simple methods to test and assess the mechanical strength of landfills on site. Also, the possibility of using a landfill site was investigated by a full-scale eccentric loading test. As a result of this, landfills containing more than about 10 cm long plastics or other fibrous materials were found to be resilient and hard to yield. An on-site full scale test proved that no differential settlement occurs. The repose angle test proposed as a simple on-site test method has been confirmed to be a good indicator for slope stability assessment. The repose angle test suggested that landfills which have high, near-saturation water content have considerably poorer slope stability. The results of our repose angle test and the impact acceleration test were related to the internal friction angle and the cohesion, respectively. In addition to this, it was found that the air pore volume ratio measured by an on-site air pore volume ratio test is likely to be related to various strength parameters.

Semipalatinsk test site: 10 years after shutting down

International Nuclear Information System (INIS)

Tukhvatulin, Sh.T.

2001-01-01

The paper consists the historical materials and chronology of events on the Semipalatinsk test site before and after it shutdown. The main part of the paper is focused on the activity on the former nuclear site after it shutdown. The first of all activity is related with coming into being and development of the National Nuclear Center of the Republic of Kazakhstan

Nevada Test Site craters used for astronaut training

Science.gov (United States)

Moore, H. J.

1977-01-01

Craters produced by chemical and nuclear explosives at the Nevada Test Site were used to train astronauts before their lunar missions. The craters have characteristics suitable for reconnaissance-type field investigations. The Schooner test produced a crater about 300 m across and excavated more than 72 m of stratigraphic section deposited in a fairly regular fashion so that systematic observations yield systematic results. Other features common on the moon, such as secondary craters and glass-coated rocks, are present at Schooner crater. Smaller explosive tests on Buckboard Mesa excavated rocks from three horizontal alteration zones within basalt flows so that the original sequence of the zones could be determined. One crater illustrated the characteristics of craters formed across vertical boundaries between rock units. Although the exercises at the Nevada Test Site were only a small part of the training of the astronauts, voice transcripts of Apollo missions 14, 16, and 17 show that the exercises contributed to astronaut performance on the moon.

On the population dose around the Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Hill, P.; Dederichs, H.; Ostapczuk, P.; Hille, R.; Artemev, O.; Ptitskaya, L.; Akhmetov, M.; Pivovarov, S.

2002-01-01

Since 1949 the Semipalatinsk Nuclear Test Site (NTS) was extensively used by the former Soviet government as a testing range for atomic weapons. Atmospheric and underground tests were finally stopped in 1962 and 1989, respectively. The Ministry of the Russian Federation of Atomic Energy officially counts a total of 456 tests, including 116 atmospheric tests. The total yield of the nuclear explosions carried out was 6.3 Megatons equivalent with 6.7 PetaBq of 1 37C s and 3.7 PetaBq of 9 0S r being released into the athmosphere. Some of the athmospheric radioactive tests shielded plumes, which extended far beyond the outer borders of the NTS. Already the first Soviet atomic bomb test on August 29, 1949 due to unfavourable meteorological conditions affected the villages of Dolon and Moistik. Since 1995 joint investigations performed by the Research Centre Julich in cooperation with the Kazakh National Nuclear Centre in the region of the former nuclear test site near Semipalatinsk besides environmental measurents also involve the assessment of the current dose of the population at and around the test site in addition to the important retrospective determination of the dose of persons affected by the atmospheric tests

Regular monitoring, analysis and forecast of radioecological environment of Azgir test site

International Nuclear Information System (INIS)

Akhmetov, E.; Agymov, I.; Gilmanov, Zh.; Ermanov, A.; Zhetbaev, A.

1996-01-01

The objective of investigations: basing on the results of regular annual measurements of radiation conditions on the sites of underground nuclear cavities of the Azgir test site, specific concentrations of radionuclides and heavy metals in soil and underground aquifers on the test site and adjacent territories to obtain data on migration and transfer of radionuclides and heavy metals. This will give a real possibility to make probability predictions of ways and qualitative characteristics of spreading of radionuclides and heavy metals in the region of the northern Pricaspian lowland. The Essence of the Problem The Azgir test site is located in the arid zone of the Great Azgir salt cupola near the Azgir village of Kurmangazinskiy rayon, Atyrau region. This cupola is located in the western periphery of Pricaspian salt-bearing province situated to the north of the Caspian sea between the Volga and Emba rivers. Major Tasks: - Development of technical requirements for carrying out regular examination of radionuclide and heavy metal contamination of the Azgir test site. - Preparation of material and technical base for field works on the Azgir test site. - Radiometric measurements on the sites and around them. - Taking of soil, soil and ground waters samples both on the test site and on the adjacent territories. - Spectrometric and radiochemical investigations of soil, soil and ground water samples. - Analysis and generalization of the results creating premises for forecasting of the radioecological conditions. - Investigation of the possibility of radioactive waste disposal in underground cavities. Expected Results: - Detection and outlining of local areas of radioactive contamination on the site and adjacent territories. - Data on real structure of spreading and concentration of artificial and natural radionuclides and heavy metals in soil layer of the test site region. - Results of analytic investigations of water samples of underground sources of the site and adjacent

Forced vibration tests and simulation analyses of a nuclear reactor building. Part 2: simulation analyses

International Nuclear Information System (INIS)

Kuno, M.; Nakagawa, S.; Momma, T.; Naito, Y.; Niwa, M.; Motohashi, S.

1995-01-01

Forced vibration tests of a BWR-type reactor building. Hamaoka Unit 4, were performed. Valuable data on the dynamic characteristics of the soil-structure interaction system were obtained through the tests. Simulation analyses of the fundamental dynamic characteristics of the soil-structure system were conducted, using a basic lumped mass soil-structure model (lattice model), and strong correlation with the measured data was obtained. Furthermore, detailed simulation models were employed to investigate the effects of simultaneously induced vertical response and response of the adjacent turbine building on the lateral response of the reactor building. (author). 4 refs., 11 figs

75 FR 20364 - Public Buildings Service; Key Largo Beacon Annex Site; Key Largo, FL; Transfer of Property

Science.gov (United States)

2010-04-19

... GENERAL SERVICES ADMINISTRATION [Wildlife Order 187; 4-D-FL-1218] Public Buildings Service; Key Largo Beacon Annex Site; Key Largo, FL; Transfer of Property Pursuant to section 2 of Public Law 537, 80th Congress, approved May 19, 1948 (16 U.S.C. 667c), notice is hereby given that: 1. The General...

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2009-05-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

International Nuclear Information System (INIS)

2009-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Nevada Test Site Annual Site Environmental Report for Calendar Year - 1999

International Nuclear Information System (INIS)

Townsend, Y.E.; Grossman, R.F.

2000-01-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations

Nevada Test Site Annual Site Environmental Report for Calendar Year - 1999

Energy Technology Data Exchange (ETDEWEB)

Townsend, Y.E.; Grossman, R.F.

2000-10-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Nevada Test Site annual site environmental report for calendar year 1998

Energy Technology Data Exchange (ETDEWEB)

Black, S.C.; Townsend, Y.E.

1999-10-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Characterization of historic mortars and earthen building materials in Abu Dhabi Emirate, UAE

International Nuclear Information System (INIS)

Marcus, Benjamin L

2012-01-01

The Abu Dhabi Authority for Culture and Heritage (ADACH) is responsible for the conservation and management of historic buildings and archaeological sites in the Emirate. Laboratory analysis has been critical for understanding the composition of historic materials and establishing appropriate conservation treatments across a wide variety of building types, ranging from Iron Age earthen archaeological sites to late-Islamic stone buildings. Analysis was carried out on historic sites in Al Ain, Delma Island and Liwa Oasis using techniques such as micro-x-ray fluorescence (MXRF), scanning electron microscopy/energy dispersive x-ray spectroscopy (SEM-EDX), polarized light microscopy (PLM), and x-ray diffraction (XRD). Testing was conducted through consultant laboratories and in collaboration with local universities. The initial aim of the analysis was to understand historic earthen materials and to confirm the suitability of locally sourced clays for the production of mud bricks and plasters. Another important goal was to characterize materials used in historic stone buildings in order to develop repair mortars, renders and grouts.

Modified TCLP test for evaluating the leachability of site-specific wastes

International Nuclear Information System (INIS)

Pier, J.

1996-01-01

The Weldon Spring Site Remedial Action Project (WSSRAP) has developed a site-specific test to assess the leachability of wastes that will be placed in its on-site disposal cell. This test is modelled after the TCLP, but examines an expanded list of parameters and uses an extraction solution that is representative of conditions that are expected to exist in the disposal facility. Following the same logic that guided development of TCLP protocols, the WSSRAP developed concentration guidelines for non-TCLP parameters that were contaminants of concern in its wastes. Response actions, specific to the WSSRAP cell and wastes, were also developed to address constituents that failed to meet these guides. From 1955 to 1966, the US Atomic Energy Commission operated a uranium feed materials plant on this site. Nitroaromatic, and later, radiological wastes were disposed of in the quarry from 1945 until 1970. This paper describes testing to determine whether contaminant concentrations in leachates derived from the major waste-types that will be placed in its on-site disposal cell conform with the Department of Energy's (DOE) as low as reasonably achievable (ALARA) policy. Although the WSSRAP will continue to use the TCLP test to determine if any waste is classified RCRA-hazardous, the site-specific test described in this paper will be used to further assess whether leachate from any waste-type has the potential to adversely impact groundwater

Corrective Action Decision Document for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2000-01-01

This Corrective Action Decision Document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 254, R-MAD Decontamination Facility, under the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 254 is comprised of Corrective Action Site (CAS) 25-23-06, Decontamination Facility. A corrective action investigation for this CAS as conducted in January 2000 as set forth in the related Corrective Action Investigation Plan. Samples were collected from various media throughout the CAS and sent to an off-site laboratory for analysis. The laboratory results indicated the following: radiation dose rates inside the Decontamination Facility, Building 3126, and in the storage yard exceeded the average general dose rate; scanning and static total surface contamination surveys indicated that portions of the locker and shower room floor, decontamination bay floor, loft floor, east and west decon pads, north and south decontamination bay interior walls, exterior west and south walls, and loft walls were above preliminary action levels (PALs). The investigation-derived contaminants of concern (COCs) included: polychlorinated biphenyls, radionuclides (strontium-90, niobium-94, cesium-137, uranium-234 and -235), total volatile and semivolatile organic compounds, total petroleum hydrocarbons, and total Resource Conservation and Recovery Act (Metals). During the investigation, two corrective action objectives (CAOs) were identified to prevent or mitigate human exposure to COCs. Based on these CAOs, a review of existing data, future use, and current operations at the Nevada Test Site, three CAAs were developed for consideration: Alternative 1 - No Further Action; Alternative 2 - Unrestricted Release Decontamination and Verification Survey; and Alternative 3 - Unrestricted

Comparison of test methods for mould growth in buildings

DEFF Research Database (Denmark)

Bonderup, Sirid; Gunnarsen, Lars Bo; Knudsen, Sofie Marie

2016-01-01

renovation needs. This is of importance when hidden surface testing would require destructive measures and subsequent renovation. After identifying available methods on the Danish market for assessing mould growth in dwellings, a case study was conducted to test the usefulness of the methods in four......The purpose of this work is to compare a range of test methods and kits for assessing whether a building structure is infested by mould fungi. A further purpose of this work is to evaluate whether air-based methods for sampling fungal emissions provide information qualifying decisions concerning...... methods measure different aspects relating to mould growth and vary in selectivity and precision. The two types of air samples indicated low levels of mould growth, even where the results of the other methods indicated high to moderate growth. With methods based on culture and DNA testing some differences...

Surplus Facilities Management Program. Post-remedial-action survey report for SNAP-8 Experimental Reactor Facility, Building 010 site, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Mayes, C.B.; Justus, A.L.; Flynn, K.F.

1984-04-01

Based on the results of the radiological assessment, the Argonne National Laboratory Radiological Survey Group arrived at the following conclusions: (1) soil contaminated with the radionuclides 60 Co and 152 Eu of undetermined origin was detected in the southwest quadrant of the Building 010 site. 60 Co was also detected in one environmental sample taken from an area northwest of the site and in a borehole sample taken from the area that previously held the radioactive gas hold-up tanks. Uranium was detected in soil from a hole in the center of the building site and in a second hole southwest of the building site. In all cases, the radionuclide levels encountered in the soil were well below the criteria set by DOE for this site; and (2) the direct instrument readings at the surface of the site were probably the result of natural radiation (terrestrial and celestial), as well as shine from the material being stored at the nearby RMDF facility. There was no evidence that the contaminated soil under the asphalt pad contributed detectable levels to the total background readings

Evaluation of the OnSite malaria rapid test performance in Miandrivazo, Madagascar.

Science.gov (United States)

Ravaoarisoa, E; Andriamiandranoro, T; Raherinjafy, R; Jahevitra, M; Razanatsiorimalala, S; Andrianaranjaka, V; Randrianarivelojosia, M

2017-10-01

The performance of the malaria rapid diagnostic test OnSite-for detecting pan specific pLDH and Plasmodium falciparum specific HRP2 - was assessed during the malaria transmission peak period in Miandrivazo, in the southwestern part of Madagascar from April 20 to May 6, 2010. At the laboratory, the quality control OnSite Malaria Rapid Test according to the WHO/TDR/FIND method demonstrated that the test had good sensitivity. Of the 218 OnSite tests performed at the Miandrivazo Primary Health Center on patients with fever or a recent history of fever, four (1.8%, 95% CI: 0.6-4.9%) were invalid. Ninety four (43,1%) cases of malaria were confirmed by microscopy, of which 90 were P. falciparum malaria and 4 Plasmodium vivax malaria. With a Cohen's kappa coefficient of 0.94, the agreement between microscopy and OnSite is excellent. Compared with the rapid test CareStart™ commonly used within the public health structures in Madagascar, the sensitivity and specificity of the OnSite test were 97.9% and 96.8%.

Evaluation of Flygt Mixers for Application in Savannah River Site Tank 19. Test Results from Phase B: Mid-Scale Testing at PNNL

International Nuclear Information System (INIS)

Powell, M.R.; Combs, W.H.; Farmer, J.R.; Gladki, H.; Hatchell, B.K.; Johnson, M.A.; Poirier, M.R.; Rodwell, P.O.

1999-01-01

Pacific Northwest National Laboratory (PNNL) performed mixer tests using 3-kW (4-hp) Flygt mixers in 1.8- and 5.7-m-diameter tanks at the 336 building facility in Richland, Washington to evaluate candidate scaling relationships for Flygt mixers used for sludge mobilization and particle suspension. These tests constituted the second phase of a three-phase test program involving representatives from ITT Flygt Corporation, the Savannah River Site (SRS), the Oak Ridge National Laboratory (ORNL), and PNNL. The results of the first phase of tests, which were conducted at ITT Flygt's facility in a 0.45-m-diameter tank, are documented in Powell et al. (1999). Although some of the Phase B tests were geometrically similar to selected Phase A tests (0.45-m tank), none of the Phase B tests were geometrically, cinematically, and/or dynamically similar to the planned Tank 19 mixing system. Therefore, the mixing observed during the Phase B tests is not directly indicative of the mixing expected in Tank 19 and some extrapolation of the data is required to make predictions for Tank 19 mixing. Of particular concern is the size of the mixer propellers used for the 5.7-m tank tests. These propellers were more than three times larger than required by geometric scaling of the Tank 19 mixers. The implications of the lack of geometric similarity, as well as other factors that complicate interpretation of the test results, are discussed in Section 5.4

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2008-01-01

This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (FFACO, 1996 (as amended February 2008)). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (1) CAS 01-23-02, Atmospheric Test Site - High Alt; (2) CAS 02-23-02, Contaminated Areas (2); (3) CAS 02-23-03, Contaminated Berm; (4) CAS 02-23-10, Gourd-Amber Contamination Area; (5) CAS 02-23-11, Sappho Contamination Area; (6) CAS 02-23-12, Scuttle Contamination Area; (7) CAS 03-23-24, Seaweed B Contamination Area; (8) CAS 03-23-27, Adze Contamination Area; (9) CAS 03-23-28, Manzanas Contamination Area; (10) CAS 03-23-29, Truchas-Chamisal Contamination Area; (11) CAS 04-23-02, Atmospheric Test Site T4-a; (12) CAS 05-23-06, Atmospheric Test Site; (13) CAS 09-23-06, Mound of Contaminated Soil; (14) CAS 10-23-04, Atmospheric Test Site M-10; and (15) CAS 18-23-02, U-18d Crater (Sulky). Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107. CAU 107 closure activities will consist of verifying that the current postings required under Title 10 Code of Federal Regulations (CFR) Part 835 are in place and implementing use restrictions (URs) at two sites, CAS 03-23-29 and CAS 18-23-02. The current radiological postings combined with the URs are adequate administrative controls to limit site access and worker dose

Retail Building Guide for Entrance Energy Efficiency Measures

Energy Technology Data Exchange (ETDEWEB)

Stein, J.; Kung, F.

2012-03-01

This booklet is based on the findings of an infiltration analysis for supermarkets and large retail buildings without refrigerated cases. It enables retail building managers and engineers to calculate the energy savings potential for vestibule additions for supermarkets; and bay door operation changes in large retail stores without refrigerated cases. Retail managers can use initial estimates to decide whether to engage vendors or contractors of vestibules for pricing or site-specific analyses, or to decide whether to test bay door operation changes in pilot stores, respectively.

Solar envelope concepts: moderate density building applications. Final report

Energy Technology Data Exchange (ETDEWEB)

Knowles, R.L.; Berry, R.D.

1980-04-01

Solar energy utilization in urban areas requires public guarantees that all property owners have direct access to the sun. The study examines the implications of this premise in relation to the need for cities to also encourage or accommodate rebuilding and future development. The public policy mechanism for guaranteeing solar access is conceptualized as a solar zoning envelope that allows the largest possible building bulk on a land parcel without shadowing neighboring properties during specified times. Step-by-step methods for generating solar envelopes are described with extensive drawings, showing a variety of urban platting and lot configurations. Development and design possibilities are examined on a selected set of Los Angeles sites with typically diverse urban characteristics. Envelope attributes suitable for encouraging moderate-density commercial and residential building are examined in the context of two hypothetical but realistic development programs: one for speculative office buildings and one for condominium housing. Numerous illustrations of envelope forms and prototypical building designs are provided. The results of development simulation studies on all test sites are tabulated to show building bulk, density, land-coverage and open space characteristics obtainable under the hypothesized envelopes.

Health and safety consequences of medical isotope processing at the Hanford Site 325 building

Energy Technology Data Exchange (ETDEWEB)

Nielsen, D. L.

1997-11-19

Potential activities associated with medical isotope processing at the Hanford Site 325 Building laboratory and hot cell facilities are evaluated to assess the health and safety consequences if these activities are to be implemented as part of a combined tritium and medical isotope production mission for the Fast Flux Text Facility (FFTF). The types of activities included in this analysis are unloading irradiated isotope production assemblies at the 325 Building, recovery and dissolution of the target materials, separation of the product isotopes as required, and preparation of the isotopes for shipment to commercial distributors who supply isotopes to the medical conunuriity. Possible consequences to members of the public and to workers from both radiological and non-radiological hazards are considered in this evaluation. Section 2 of this docinnent describes the assumptions and methods used for the health and safety consequences analysis, section 3 presents the results of the analysis, and section 4 summarizes the results and conclusions from the analysis.

Microbiological analyses of samples from the H-Area injection well test site

International Nuclear Information System (INIS)

Wilde, E.W.; Franck, M.M.

1997-01-01

Microbial populations in well water from monitoring wells at the test site were one to three orders of magnitude higher than well water from the Cretaceous aquifer (used as dilution water for the tests) or from a control well adjacent to the test site facility. Coupons samples placed in monitoring and control wells demonstrated progressive adhesion by microbes to materials used in well construction. Samples of material scraped from test well components during abandonment of the test site project revealed the presence of a variety of attached microbes including iron bacteria. Although the injection wells at the actual remediation facility for the F- and H-Area seepage basins remediation project are expected to be subjected to somewhat different conditions (e.g. considerably lower iron concentrations) than was the case at the test site, the potential for microbiologically mediated clogging and fouling within the process should be considered. A sampling program that includes microbiological testing is highly recommended

BUILDING FACADE DOCUMENTATION USING LASER SCANNING AND PHOTOGRAMMETRY AND DATA IMPLEMENTATION INTO BIM

Directory of Open Access Journals (Sweden)

M. Faltýnová

2016-06-01

Full Text Available A project started last year called MORE-CONNECT, which focuses on the renovation of buildings (especially building facades using prefabricated elements. The aim of this project is to create a competitive solution consisting of a technology and processes which enable fast, cost-effective renovation with minimal difficulties to inhabitants. Significant cost savings in renovation costs lies in the usage of prefabricated elements and the reduction of construction works on site. The precision of the prefabricated element depends on the precision of the construction, project and building documentation. This article offers an overview of the possible methods for building documentation and spatial data transfer into BIM (Building Information Modelling software. The description of methods focuses on laser scanning and photogrammetry (including RPAS based, its advantages, disadvantages and limitations according to the documented building, level of renovation, situation on site etc. The next part involves spatial data transfer into BIM software. A proposed solution is tested in a case study.

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2009-01-01

This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (1996 (as amended February 2008)). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (sm b ullet) CAS 01-23-02, Atmospheric Test Site - High Alt(sm b ullet) CAS 02-23-02, Contaminated Areas (2)(sm b ullet) CAS 02-23-03, Contaminated Berm(sm b ullet) CAS 02-23-10, Gourd-Amber Contamination Area(sm b ullet) CAS 02-23-11, Sappho Contamination Area(sm b ullet) CAS 02-23-12, Scuttle Contamination Area(sm b ullet) CAS 03-23-24, Seaweed B Contamination Area(sm b ullet) CAS 03-23-27, Adze Contamination Area(sm b ullet) CAS 03-23-28, Manzanas Contamination Area(sm b ullet) CAS 03-23-29, Truchas-Chamisal Contamination Area(sm b ullet) CAS 04-23-02, Atmospheric Test Site T4-a(sm b ullet) CAS 05-23-06, Atmospheric Test Site(sm b ullet) CAS 09-23-06, Mound of Contaminated Soil(sm b ullet) CAS 10-23-04, Atmospheric Test Site M-10(sm b ullet) CAS 18-23-02, U-18d Crater (Sulky) Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107.

National Ignition Facility Site Management Plan

International Nuclear Information System (INIS)

Roberts, V.

1997-01-01

The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1 degree C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

National Ignition Facility Site Management Plan

Energy Technology Data Exchange (ETDEWEB)

Roberts, V.

1997-09-01

The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1{degree}C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

Wind Tunnel Tests for Wind Pressure Distribution on Gable Roof Buildings

Science.gov (United States)

2013-01-01

Gable roof buildings are widely used in industrial buildings. Based on wind tunnel tests with rigid models, wind pressure distributions on gable roof buildings with different aspect ratios were measured simultaneously. Some characteristics of the measured wind pressure field on the surfaces of the models were analyzed, including mean wind pressure, fluctuating wind pressure, peak negative wind pressure, and characteristics of proper orthogonal decomposition results of the measured wind pressure field. The results show that extremely high local suctions often occur in the leading edges of longitudinal wall and windward roof, roof corner, and roof ridge which are the severe damaged locations under strong wind. The aspect ratio of building has a certain effect on the mean wind pressure coefficients, and the effect relates to wind attack angle. Compared with experimental results, the region division of roof corner and roof ridge from AIJ2004 is more reasonable than those from CECS102:2002 and MBMA2006.The contributions of the first several eigenvectors to the overall wind pressure distributions become much bigger. The investigation can offer some basic understanding for estimating wind load distribution on gable roof buildings and facilitate wind-resistant design of cladding components and their connections considering wind load path. PMID:24082851

An accelerated exposure and testing apparatus for building joint sealants.

Science.gov (United States)

White, C C; Hunston, D L; Tan, K T; Hettenhouser, J; Garver, J D

2013-09-01

The design, fabrication, and implementation of a computer-controlled exposure and testing apparatus for building joint sealants are described in this paper. This apparatus is unique in its ability to independently control and monitor temperature, relative humidity, ultraviolet (UV) radiation, and mechanical deformation. Each of these environmental factors can be controlled precisely over a wide range of conditions during periods of a month or more. Moreover, as controlled mechanical deformations can be generated, in situ mechanical characterization tests can be performed without removing specimens from the chamber. Temperature and humidity were controlled during our experiments via a precision temperature regulator and proportional mixing of dry and moisture-saturated air; while highly uniform UV radiation was attained by attaching the chamber to an integrating sphere-based radiation source. A computer-controlled stepper motor and a transmission system were used to provide precise movement control. The reliability and effectiveness of the apparatus were demonstrated on a model sealant material. The results clearly show that this apparatus provides an excellent platform to study the long-term durability of building joint sealants.

Environmental site assessments should include radon gas testing

International Nuclear Information System (INIS)

Nardi, M.A.

1991-01-01

There are two emerging influences that will require radon gas testing as part of many property transfers and most site assessments. These requirements come from lending regulators and state legislatures. Fannie Mae and others have developed environmental investigation guidelines for the purchase of environmentally contaminated real estate. These guidelines include radon gas testing for many properties. Several states have enacted laws that require environmental disclosure forms be prepared to ensure that the parties involved in certain real estate transactions are aware of the environmental liabilities that may come with the transfer of property. Indiana has recently enacted legislation that would require the disclosure of the presence of radon gas on many commercial real estate transactions. With more lenders and state governments likely to follow this trend, radon gas testing should be performed during all property transfers and site assessment to protect the parties involved from any legal liabilities

Drupal The Guide to Planning and Building Websites

CERN Document Server

McCourt, Cynthia

2011-01-01

A complete lifecycle guide to planning and building a site with Drupal Drupal allows you to quickly and easily build a wide variety of web sites, from very simple blog sites to extremely complex sites that integrate with other systems. In order to maximize what Drupal can do for you, you need to plan. Whether you are building with Drupal 6 or 7, this book details the steps necessary to plan your site so you can make informed decisions before you start to build.Explains how to define the scope of your projectShows you how to create a design plan taking into consideration how Drupal worksHelps y

Fiscal 1997 research report on the PV power generation field test project for public facilities. Evaluation and analysis of collected data for every site (2/3); 1997 nendo kokyo shisetsu nadoyo taiyoko hatsuden field test jigyo ni okeru shushu data hyoka kaiseki. Kaku site betsu (2/3)

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

As a part of the PV power generation field test project, this report summarizes the monthly collected data for every site in fiscal 1996. Collected data items are as follows: horizontal/total/effective solar irradiation (kWh/m{sup 2}), average air temperature, array power, system power, load power, power system supply load, reverse power flow (kWh for every item), power system protective operation frequency, system disinterconnection time (min), system operation time (min), self-operation load, self-supply load, equivalent array/system operation time, array/system performance ratio, system use factor, system generation efficiency, effective inverter efficiency, and inverter load factor. The test sites include various public facilities such as doctor's office, newspaper office, general building for public corporations, primary school, hot water pool, health center, public hall, town/ward office, water purification plant, consumers' cooperative (CO-OP), university, high school, technical center, training center, nursery school, kindergarten, and nursing home for the aged. (NEDO)

Full scale vibration test on nuclear power plant auxiliary building: Part I

International Nuclear Information System (INIS)

Langer, V.; Tinic, S.; Berger, E.; Zwicky, P.; Prater, E.G.

1987-01-01

In connection with the construction of the reinforced concrete auxiliary building housing the two boric water tanks (so-called BOTA building) of the Beznau Nuclear Power Plant in Switzerland the opportunity was given to carry out full scale vibration tests in November 1985. The overall aim of the tests was to validate computational models and parameters widely used in the seismic analysis of the structures and critical components of nuclear power plants. The scope of the experimental investigation was the determination of the eigenfrequencies and damping values for the fundamental soil-structure interaction (SSI) modes. The excitation level was aimed to be as high as feasibly possible. A working group was formed of representatives of the owner, NOK, the consulting firm Basler and Hofmann and the ETH to supervise the project. The project's main phases were the planning and execution of the tests, the evaluation of recorded data, numerical simulation of the tests using different computer models and finally the comparison and interpretation of measured and computed results

Damage Assessment of a Full-Scale Six-Story wood-frame Building Following Triaxial shake Table Tests

Science.gov (United States)

John W. van de Lindt; Rakesh Gupta; Shiling Pei; Kazuki Tachibana; Yasuhiro Araki; Douglas Rammer; Hiroshi Isoda

2012-01-01

In the summer of 2009, a full-scale midrise wood-frame building was tested under a series of simulated earthquakes on the world's largest shake table in Miki City, Japan. The objective of this series of tests was to validate a performance-based seismic design approach by qualitatively and quantitatively examining the building's seismic performance in terms of...

Improving ATLAS grid site reliability with functional tests using HammerCloud

CERN Document Server

Legger, F; The ATLAS collaboration; Medrano Llamas, R; Sciacca, G; Van der Ster, D C

2012-01-01

With the exponential growth of LHC (Large Hadron Collider) data in 2011, and more coming in 2012, distributed computing has become the established way to analyse collider data. The ATLAS grid infrastructure includes more than 80 sites worldwide, ranging from large national computing centers to smaller university clusters. These facilities are used for data reconstruction and simulation, which are centrally managed by the ATLAS production system, and for distributed user analysis. To ensure the smooth operation of such a complex system, regular tests of all sites are necessary to validate the site capability of successfully executing user and production jobs. We report on the development, optimization and results of an automated functional testing suite using the HammerCloud framework. Functional tests are short light-weight applications covering typical user analysis and production schemes, which are periodically submitted to all ATLAS grid sites. Results from those tests are collected and used to evaluate si...

Preoperational test report, cross-site transfer system integrated test (POTR-007)

Energy Technology Data Exchange (ETDEWEB)

Pacquet, E.A.

1998-04-02

This report documents the results obtained during the performance of Preoperational Test POTP-007, from December 12, 1997 to March 27, 1998. The main objectives were to demonstrate the operation of the following Cross-Site Transfer System components: Booster pumps P-3125A and P-3125B interlocks and controls, both local and remote; Booster pump P-3125A and P-3125B and associated variable speed drives VSD-1 and VSD-2 performance in both manual and automatic modes; and Water filling, circulation, venting and draining of the transfer headers (supernate and slurry line). As described in reference 1, the following components of the Cross-Site Transfer System that would normally be used during an actual waste transfer, are not used in this specific test: Water Flush System; Valving and instrumentation associated with the 241-SY-A valve pit jumpers; and Valving and instrumentation associated with the 244-A lift station.

Preoperational test report, cross-site transfer system integrated test (POTR-007)

International Nuclear Information System (INIS)

Pacquet, E.A.

1998-01-01

This report documents the results obtained during the performance of Preoperational Test POTP-007, from December 12, 1997 to March 27, 1998. The main objectives were to demonstrate the operation of the following Cross-Site Transfer System components: Booster pumps P-3125A and P-3125B interlocks and controls, both local and remote; Booster pump P-3125A and P-3125B and associated variable speed drives VSD-1 and VSD-2 performance in both manual and automatic modes; and Water filling, circulation, venting and draining of the transfer headers (supernate and slurry line). As described in reference 1, the following components of the Cross-Site Transfer System that would normally be used during an actual waste transfer, are not used in this specific test: Water Flush System; Valving and instrumentation associated with the 241-SY-A valve pit jumpers; and Valving and instrumentation associated with the 244-A lift station

Probabilistic Description of a Clay Site using CPTU tests

DEFF Research Database (Denmark)

Andersen, Sarah; Lauridsen, Kristoffer; Nielsen, Benjaminn Nordahl

2012-01-01

A clay site at the harbour of Aarhus, where numerous cone penetration tests have been conducted, is assessed. The upper part of the soil deposit is disregarded, and only the clay sections are investigated. The thickness of the clay deposit varies from 5 to 6 meters, and is sliced into sections of...... a geotechnical assessment of a site, using both the method for classifying soil behaviour types and applying statistics, yield a new level of information, and certainty about the estimates of the strength parameters which are the important outcome of such a site description.......A clay site at the harbour of Aarhus, where numerous cone penetration tests have been conducted, is assessed. The upper part of the soil deposit is disregarded, and only the clay sections are investigated. The thickness of the clay deposit varies from 5 to 6 meters, and is sliced into sections of 1...... meter in thickness. For each slice, a map of the variation of the undrained shear strength is created through Kriging and the probability of finding weak zones in the deposit is calculated. This results in a description of the spatial variation of the undrained shear strength at the site. Making...

The 'Guetsch' Alpine wind power test site; Alpine Test Site Guetsch. Handbuch und Fachtagung

Energy Technology Data Exchange (ETDEWEB)

Cattin, R.

2008-12-15

This final report for the Swiss Federal Office of Energy (SFOE) takes a look at the influence of icing-up on the operation of wind turbines in mountainous areas. Within the Swiss research project 'Alpine Test Site Guetsch', extensive icing studies were carried out at the Guetsch site near Andermatt, Switzerland. This document deals with the following subjects: Information about ice formation on structures, in particular with respect to wind turbines, standards and international research activities, wind measurements under icing-up conditions, estimation of the frequency of icing-up conditions, effects of icing-up on wind turbines, ice detection, measures available for de-icing and anti-icing as well as ice throw. A list of factors to be taken into account by the planners and operators of wind turbines in alpine environments is presented.

Perspectives of investigation and development of Semipalatinsk Test Site

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Lukashenko, S.N.

2008-01-01

Full text: Since the Semipalatinsk Test Site has been stopped and up until now, National Nuclear Center of the Republic of Kazakhstan (NNC RK) in cooperation with other specialist from Kazakhstan and international scientific community have accumulated large scope of information about current radiological situation at Semipalatinsk Nuclear Test Site (SNTS) and adjacent territories. There were revealed all important spots of radioactive contamination, identified main pathways and mechanisms for present and potential proliferation of radioactive substances. Obtained data assure us that present-day SNTS provides no negative impact on population on adjacent to the Site territories excluding people in the water basin of the river Shagan. Compliance with regulatory requirements and special rules for SNTS territory assures radiation safety at commercial activities on the Site. At the same time, the radiological situation does not remain stable; there were revealed the processes of radionuclide migration what requires regular monitoring of radiological situation at SNTS. Taking into account the scale of the Site and the variety of tests performed there, the information available about SNTS can not be completely exhaustive but enables us to propose a scientifically grounded plan for further research and practical measures aimed at remediation and reclamation of lands. implementation of such measures should return up to 80% of the lands to commercial use. SNTS is one of the world largest nuclear test sites with decisive contribution to creation and development of nuclear weapon. To considerable extent, these were works at SNTS which established nuclear parity between the superpowers one of the crucial factors in the history of human civilization in the 20 century. Also taking into account the interest to SNTS paid by international organizations, it is reasonable to initiate a procedure and recognize SNTS as a landmark including it in the UNESCO List of Cultural and Nature

Comparison of constant-rate pumping test and slug interference test results at the Hanford Site B pond multilevel test facility

International Nuclear Information System (INIS)

Spane, F.A. Jr.; Thorne, P.D.

1995-10-01

Pacific Northwest Laboratory (PNL), as part of the Hanford Site Ground-Water Surveillance Project, is responsible for monitoring the movement and fate of contamination within the unconfined aquifer to ensure that public health and the environment are protected. To support the monitoring and assessment of contamination migration on the Hanford Site, a sitewide 3-dimensional groundwater flow model is being developed. Providing quantitative hydrologic property data is instrumental in development of the 3-dimensional model. Multilevel monitoring facilities have been installed to provide detailed, vertically distributed hydrologic characterization information for the Hanford Site unconfined aquifer. In previous reports, vertically distributed water-level and hydrochemical data obtained over time from these multi-level monitoring facilities have been evaluated and reported. This report describes the B pond facility in Section 2.0. It also provides analysis results for a constant-rate pumping test (Section 3.0) and slug interference test (Section 4.0) that were conducted at a multilevel test facility located near B Pond (see Figure 1. 1) in the central part of the Hanford Site. A hydraulic test summary (Section 5.0) that focuses on the comparison of hydraulic property estimates obtained using the two test methods is also presented. Reference materials are listed in Section 6.0

77 FR 43084 - Office of Federal High-Performance Green Buildings; Federal Buildings Personnel Training Act...

Science.gov (United States)

2012-07-23

... Federal High-Performance Green Buildings; Federal Buildings Personnel Training Act; Notification of... High- Performance Green Buildings, Office of Governmentwide Policy, General Services Administration... download from the Office of Federal High-Performance Green Building Web site Library at-- http://www.gsa...

Usability Testing of an Academic Library Web Site: A Case Study.

Science.gov (United States)

Battleson, Brenda; Booth, Austin; Weintrop, Jane

2001-01-01

Discusses usability testing as a tool for evaluating the effectiveness and ease of use of academic library Web sites; considers human-computer interaction; reviews major usability principles; and explores the application of formal usability testing to an existing site at the University at Buffalo (NY) libraries. (Author/LRW)

A case study on the structural assessment of fire damaged building

Science.gov (United States)

Osman, M. H.; Sarbini, N. N.; Ibrahim, I. S.; Ma, C. K.; Ismail, M.; Mohd, M. F.

2017-11-01

This paper presents a case study on the structural assessment of building damaged by fire and discussed on the site investigations and test results prior to determine the existing condition of the building. The building was on fire for about one hour before it was extinguished. In order to ascertain the integrity of the building, a visual inspection was conducted for all elements (truss, beam, column and wall), followed by non-destructive, load and material tests. The load test was conducted to determine the ability of truss to resist service load, while the material test to determine the residual strength of the material. At the end of the investigation, a structural analysis was carried out to determine the new factor of safety by considering the residual strength. The highlighted was on the truss element due to steel behaviour that is hardly been predicted. Meanwhile, reinforced concrete elements (beam, column and wall) were found externally affected and caused its strength to be considered as sufficient for further used of building. The new factor of safety is equal to 2, considered as the minimum calculated value for the truss member. Therefore, this fire damaged building was found safe and can be used for further application.

Applicability of slug interference testing of hydraulic characterization of contaminated aquifer sites

International Nuclear Information System (INIS)

Spane, F.A.; Swanson, L.C.

1993-10-01

Aquifer test methods available for characterizing hazardous waste sites are sometimes restricted because of problems with disposal of contaminated groundwater. These problems, in part, have made slug tests a more desirable method of determining hydraulic properties at such sites. However, in higher permeability formations (i.e., transmissivities ≥ 1 x 10 -3 m 2 /s), slug test results often cannot be analyzed and give, at best, only a lower limit for transmissivity. A need clearly exists to develop test methods that can be used to characterize higher permeability aquifers without removing large amounts of contaminated groundwater. One hydrologic test method that appears to hold promise for characterizing such sites is the slug interference test. To assess the applicability of this test method for use in shallow alluvial aquifer systems, slug interference tests have been conducted, along with more traditional aquifer testing methods, at several Hanford multiple-well sites. Transmissivity values estimated from the slug interference tests were comparable (within a factor of 2 to 3) to values calculated using traditional testing methods, and made it possible to calculate the storativity or specific yield for the intervening test formation. The corroboration of test results indicates that slug interference testing is a viable hydraulic characterization method in transmissive alluvial aquifers, and may represent one of the few test methods that can be used in sensitive areas where groundwater is contaminated

Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2011-08-01

CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison

Usability Testing in a Library Web Site Redesign Project.

Science.gov (United States)

McMullen, Susan

2001-01-01

Discusses the need for an intuitive library information gateway to meet users' information needs and describes the process involved in redesigning a library Web site based on experiences at Roger Williams University. Explains usability testing methods that were used to discover how users were interacting with the Web site interface. (Author/LRW)

Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2012-10-01

CAU 104 comprises the following corrective action sites (CASs): • 07-23-03, Atmospheric Test Site T-7C • 07-23-04, Atmospheric Test Site T7-1 • 07-23-05, Atmospheric Test Site • 07-23-06, Atmospheric Test Site T7-5a • 07-23-07, Atmospheric Test Site - Dog (T-S) • 07-23-08, Atmospheric Test Site - Baker (T-S) • 07-23-09, Atmospheric Test Site - Charlie (T-S) • 07-23-10, Atmospheric Test Site - Dixie • 07-23-11, Atmospheric Test Site - Dixie • 07-23-12, Atmospheric Test Site - Charlie (Bus) • 07-23-13, Atmospheric Test Site - Baker (Buster) • 07-23-14, Atmospheric Test Site - Ruth • 07-23-15, Atmospheric Test Site T7-4 • 07-23-16, Atmospheric Test Site B7-b • 07-23-17, Atmospheric Test Site - Climax These 15 CASs include releases from 30 atmospheric tests conducted in the approximately 1 square mile of CAU 104. Because releases associated with the CASs included in this CAU overlap and are not separate and distinguishable, these CASs are addressed jointly at the CAU level. The purpose of this CADD/CAP is to evaluate potential corrective action alternatives (CAAs), provide the rationale for the selection of recommended CAAs, and provide the plan for implementation of the recommended CAA for CAU 104. Corrective action investigation (CAI) activities were performed from October 4, 2011, through May 3, 2012, as set forth in the CAU 104 Corrective Action Investigation Plan.

Interim report on flash floods, Area 5 - Nevada Test Site

International Nuclear Information System (INIS)

French, R.H.

1980-09-01

Examination of the presently available data indicates that consideration must be given to the possibility of flash floods when siting waste management facilities in Area 5 of the Nevada Test Site. 6 figures, 7 tables

Supporting documents for LLL area 27 (410 area) safety analysis reports, Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Odell, B. N. [comp.

1977-02-01

The following appendices are common to the LLL Safety Analysis Reports Nevada Test Site and are included here as supporting documents to those reports: Environmental Monitoring Report for the Nevada Test Site and Other Test Areas Used for Underground Nuclear Detonations, U. S. Environmental Protection Agency, Las Vegas, Rept. EMSL-LV-539-4 (1976); Selected Census Information Around the Nevada Test Site, U. S. Environmental Protection Agency, Las Vegas, Rept. NERC-LV-539-8 (1973); W. J. Hannon and H. L. McKague, An Examination of the Geology and Seismology Associated with Area 410 at the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-51830 (1975); K. R. Peterson, Diffusion Climatology for Hypothetical Accidents in Area 410 of the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-52074 (1976); J. R. McDonald, J. E. Minor, and K. C. Mehta, Development of a Design Basis Tornado and Structural Design Criteria for the Nevada Test Site, Nevada, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-13668 (1975); A. E. Stevenson, Impact Tests of Wind-Borne Wooden Missiles, Sandia Laboratories, Tonopah, Rept. SAND 76-0407 (1976); and Hydrology of the 410 Area (Area 27) at the Nevada Test Site.

BUILDING CONCEPTUAL AND MATHEMATICAL MODEL FOR WATER FLOW AND SOLUTE TRANSPORT IN THE UNSATURATED ZONE AT KOSNICA SITE

Directory of Open Access Journals (Sweden)

Stanko Ružičić

2012-12-01

Full Text Available Conceptual model of flow and solute transport in unsaturated zone at Kosnica site, which is the basis for modeling pollution migration through the unsaturated zone to groundwater, is set up. The main characteristics of the unsaturated zone of the Kosnica site are described. Detailed description of investigated profile of unsaturated zone, with all necessary analytical results performed and used in building of conceptual models, is presented. Experiments that are in progress and processes which are modeled are stated. Monitoring of parameters necessary for calibration of models is presented. The ultimate goal of research is risk assessment of groundwater contamination at Kosnica site that has its source in or on unsaturated zone.

Co-Simulation of Building Energy and Control Systems with the Building Controls Virtual Test Bed

Energy Technology Data Exchange (ETDEWEB)

Wetter, Michael

2010-08-22

This article describes the implementation of the Building Controls Virtual Test Bed (BCVTB). The BCVTB is a software environment that allows connecting different simulation programs to exchange data during the time integration, and that allows conducting hardware in the loop simulation. The software architecture is a modular design based on Ptolemy II, a software environment for design and analysis of heterogeneous systems. Ptolemy II provides a graphical model building environment, synchronizes the exchanged data and visualizes the system evolution during run-time. The BCVTB provides additions to Ptolemy II that allow the run-time coupling of different simulation programs for data exchange, including EnergyPlus, MATLAB, Simulink and the Modelica modelling and simulation environment Dymola. The additions also allow executing system commands, such as a script that executes a Radiance simulation. In this article, the software architecture is presented and the mathematical model used to implement the co-simulation is discussed. The simulation program interface that the BCVTB provides is explained. The article concludes by presenting applications in which different state of the art simulation programs are linked for run-time data exchange. This link allows the use of the simulation program that is best suited for the particular problem to model building heat transfer, HVAC system dynamics and control algorithms, and to compute a solution to the coupled problem using co-simulation.

CTBTO tests its on-site inspection regime in Kazakhstan

International Nuclear Information System (INIS)

2003-07-01

The former Soviet Union's nuclear test site at Semipalatinsk in the east of today's Kazakhstan was closed down after Kazakhstan became an independent State in 1991. This region in the Kazakh steppe is deserted and pockmarked by countless craters, remnants of over 450 nuclear explosions that were detonated there. In September 2008, the area will start brimming with activity. Scientists, diplomats and journalists will arrive from all over the world to witness an endeavour in the Kazakh steppe that is of great significance for the safety of our planet. The organization that monitors the comprehensive ban on nuclear testing will conduct a large scale exercise to test one of the key elements of its global alarm system - on-site inspections.

Preliminary investigation on determination of radionuclide distribution in field tracing test site

International Nuclear Information System (INIS)

Tanaka, Tadao; Mukai, Masayuki; Takebe, Shinichi; Guo Zede; Li Shushen; Kamiyama, Hideo.

1993-12-01

Field tracing tests for radionuclide migration have been conducted by using 3 H, 60 Co, 85 Sr and 134 Cs, in the natural unsaturated loess zone at field test site of China Institute for Radiation Protection. It is necessary to obtain confidable distribution data of the radionuclides in the test site, in order to evaluate exactly the migration behavior of the radionuclides in situ. An available method to determine the distribution was proposed on the basis of preliminary discussing results on sampling method of soils from the test site and analytical method of radioactivity in the soils. (author)

Demosite - Demonstration of the integration of photovoltaic elements in buildings; DEMOSITE. Site de demonstration d'elements de construction photovoltaiques integres au batiment

Energy Technology Data Exchange (ETDEWEB)

Roecker, C.; Affolter, P.; Muller, A.N.; Ould-Yenia, A.

2003-07-01

This final report for the Swiss Federal Office of Energy summarises Phase 4 of the DEMOSITE project and concludes 10 years of DEMOSITE activities. The DEMOSITE project, started in 1992, demonstrates various ways of integrating photovoltaic elements in buildings by providing stands, pavilions and monitoring facilities at its site in Lausanne, Switzerland. Here, at the Swiss Federal Institute of Technology, roof-mounted installations can be found as well as mock-ups of buildings and roofing systems that also serve as covered parking facilities. The DEMOSITE web site and graphical presentations are also reviewed. Furthermore, the six newest pavilions are presented in detail. The report also presents several sets of data from measurements made on the installations and discusses the dissemination of information and results obtained from the project. A comprehensive annex provides illustrations of examples of building-integrated photovoltaics from around the world.

Closure report for CAU No. 450: Historical UST release sites, Nevada Test Site. Volume 1

International Nuclear Information System (INIS)

1997-09-01

This report addresses the closure of 11 historical underground storage tank (UST) release sites within various areas of the Nevada Test Site (NTS). The closure of each hydrocarbon release has not been documented, therefore, this report addresses the remedial activities completed for each release site. The hydrocarbon release associated with each tank site within CAU 450 was remediated by excavating the impacted soil. Clean closure of the release was verified through soil sample analysis by an off-site laboratory. All release closure activities were completed following standard environmental and regulatory guidelines. Based upon site observations during the remedial activities and the soil sample analytical results, which indicated that soil concentrations were below the Nevada Administrative code (NAC) Action Level of 100 mg/kg, it is anticipated that each of the release CASs be closed without further action

Digitally-Assisted Stone Carving of a Relief Sculpture for the Parliament Buildings National Historic Site of Canada

Science.gov (United States)

Hayes, J.; Fai, S.; Kretz, S.; Ouimet, C.; White, P.

2015-08-01

The emerging field of digital fabrication is a process where three-dimensional datasets can be directly transferred to fabrication equipment to create models or even 1:1 building elements. In this paper, we will discuss the results of a collaboration between the Carleton Immersive Media Studio (CIMS), the Dominion Sculptor of Canada, and the Heritage Conservation Directorate (HCD) of Public Works and Government Services Canada (PWGSC), that utilizes digital fabrication technologies in the development of a digitally-assisted stone carving process. The collaboration couples the distinguished skill of the Dominion Sculptor with the latest digital acquisition and digital fabrication technologies for the reconstruction of a deteriorated stone bas-relief on the façade of the East Block building of the Parliament Buildings National Historic Site of Canada. The intention of the research is to establish a workflow of hybrid digital/analogue methodologies from acquisition through rehabilitation and ultimately to the fabrication of stone elements.

Rehabilitation of former nuclear test sites in Australia

International Nuclear Information System (INIS)

1990-01-01

A range of options with indicative cost estimates and timescale has been defined for clean-up of the former British nuclear test sites at Maralinga and Emu in South Australia. The situation at the former test sites on the Monte Bello Islands has been reported separately. The predominant contributor to potential radiation dose at the test sites is residual plutonium contamination of soil which may be incorporated into the body through inhalation of resuspended dust. Acceptable levels of radioactive soil contamination based upon organ doses from incorporated plutonium and the associated health detriment are proposed by the Technical Assessment Group for a series of land-use options ranging from fully unrestricted habitation by Aboriginals including the case of high dependence on local plants and animals for food: to casual access by Aboriginals assuming retained or, if necessary, extended fences. The area of land affected and the quantity of soil and other material with more than the proposed limit of contamination as well as a range of remedial measures for reduction of the contamination to a level acceptable for each of the land-use options has been assessed and methods proposed for safe disposal of the contaminated materials. The associated costs of these remedial measures and disposal methods have also been estimated. 28 refs., 71 tabs., 45 figs

DOUBLE TRACKS Test Site interim corrective action plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

Energy savings potential from improved building controls for the US commercial building sector

Energy Technology Data Exchange (ETDEWEB)

Fernandez, Nick; Katipamula, Srinivas; Wang, Weimin; Xie, Yulong; Zhao, Mingjie

2017-09-27

The U.S. Department of Energy’s (DOE’s) Building Technologies Office (BTO) sponsored a study to determine the potential national savings achievable in the commercial building sector through widespread deployment of best practice controls, elimination of system and component faults, and use of better sensing. Detailed characterization of potential savings was one source of input to set research, development, and deployment (RD&D) goals in the field of building sensors and controls. DOE’s building energy simulation software, EnergyPlus, was employed to estimate the potential savings from 34 measures in 9 building types and across 16 climates representing almost 57% of commercial building sector energy consumption. In addition to estimating savings from individual measures, three packages of measures were created to estimate savings from the packages. These packages represented an 1) efficient building, 2) typical building, and 3) inefficient building. To scale the results from individual measures or a package to the national scale, building weights by building type and climate locations from the Energy Information Administration’s 2012 Commercial Building Energy Consumption Survey (CBECS) were used. The results showed significant potential for energy savings across all building types and climates. The total site potential savings from individual measures by building type and climate location ranged between 0% and 25%. The total site potential savings by building type aggregated across all climates (using the CBECS building weights) for each measure varied between 0% and 16%. The total site potential savings aggregated across all building types and climates for each measure varied between 0% and 11%. Some individual measures had negative savings because correcting underlying operational problems (e.g., inadequate ventilation) resulted in increased energy consumption. When combined into packages, the overall national savings potential is estimated to be 29

National HIV Testing Day at CDC-funded HIV counseling, testing, and referral sites--United States, 1994-1998.

Science.gov (United States)

2000-06-23

CDC-funded human immunodeficiency virus (HIV) counseling, testing, and referral sites are an integral part of national HIV prevention efforts (1). Voluntary counseling, testing, and referral opportunities are offered to persons at risk for HIV infection at approximately 11,000 sites, including dedicated HIV counseling and testing sites, sexually transmitted disease (STD) clinics, drug-treatment centers, hospitals, and prisons. Services also are offered to women in family planning and prenatal/obstetric clinics to increase HIV prevention efforts among women and decrease the risk for perinatal HIV transmission. To increase use of HIV counseling, testing, and referral services by those at risk for HIV infection, in 1995, the National Association of People with AIDS designated June 27 each year as National HIV Testing Day. This report compares use of CDC-funded counseling, testing, and referral services the week before and the week of June 27 from 1994 through 1998 and documents the importance of a national public health campaign designed to increase knowledge of HIV serostatus.

Soil Characterization Database for the Area 3 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

Remortel, R. D. Van; Lee, Y. J.; Snyder, K. E.

2005-01-01

Soils were characterized in an investigation at the Area 3 Radioactive Waste Management Site at the U.S. Department of Energy Nevada Test Site in Nye County, Nevada. Data from the investigation are presented in four parameter groups: sample and site characteristics, U.S. Department of Agriculture (USDA) particle size fractions, chemical parameters, and American Society for Testing Materials-Unified Soil Classification System (ASTM-USCS) particle size fractions. Spread-sheet workbooks based on these parameter groups are presented to evaluate data quality, conduct database updates, and set data structures and formats for later extraction and analysis. This document does not include analysis or interpretation of presented data

Soil Characterization Database for the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

Lee, Y. J.; Remortel, R. D. Van; Snyder, K. E.

2005-01-01

Soils were characterized in an investigation at the Area 5 Radioactive Waste Management Site at the U.S. Department of Energy Nevada Test Site in Nye County, Nevada. Data from the investigation are presented in four parameter groups: sample and site characteristics, U.S. Department of Agriculture (USDA) particle size fractions, chemical parameters, and American Society for Testing Materials-Unified Soil Classification System (ASTM-USCS) particle size fractions. Spread-sheet workbooks based on these parameter groups are presented to evaluate data quality, conduct database updates,and set data structures and formats for later extraction and analysis. This document does not include analysis or interpretation of presented data

On-Site or Off-Site Renewable Energy Supply Options?

DEFF Research Database (Denmark)

Marszal, Anna Joanna; Heiselberg, Per; Jensen, Rasmus Lund

2012-01-01

The concept of a Net Zero Energy Building (Net ZEB) encompasses two options of supplying renewable energy, which can offset energy use of a building, in particular on-site or off-site renewable energy supply. Currently, the on-site options are much more popular than the off-site; however, taking...... into consideration the limited area of roof and/or façade, primarily in the dense city areas, the Danish weather conditions, the growing interest and number of wind turbine co-ops, the off-site renewable energy supply options could become a meaningful solution for reaching ‘zero’ energy goal in the Danish context...... five technologies, i.e., two on-site options: (1) photovoltaic, (2) micro combined heat and power, and three off-site options: (1) off-site windmill, (2) share of a windmill farm and (3) purchase of green energy from the 100% renewable utility grid. The results indicate that in case of the on...

Tonopah Test Range Environmental Restoration Corrective Action Sites

International Nuclear Information System (INIS)

Ronald B. Jackson

2007-01-01

Corrective Action Sites (CASs) and Corrective Action Units (CAUs) at the Tonopah Test Range (TTR) may be placed into three categories: Clean Closure/No Further Action, Closure in Place, or Closure in Progress

An assessment and evaluation for recycle/reuse of contaminated process and metallurgical equipment at the DOE Rocky Flats Plant Site -- Building 865

International Nuclear Information System (INIS)

1993-08-01

An economic analysis of the potential advantages of alternatives for recycling and reusing equipment now stored in Building 865 at the Rocky Flats Plant (RFP) in Colorado has been conducted. The inventory considered in this analysis consists primarily of metallurgical and process equipment used before January 1992, during development and production of nuclear weapons components at the site. The economic analysis consists of a thorough building inventory and cost comparisons for four equipment dispositions alternatives. The first is a baseline option of disposal at a Low Level Waste (LLW) landfill. The three alternatives investigated are metal recycling, reuse with the government sector, and release for unrestricted use. This report provides item-by-item estimates of value, disposal cost, and decontamination cost. The economic evaluation methods documented here, the simple cost comparisons presented, and the data provided as a supplement, should provide a foundation for D ampersand D decisions for Building 865, as well as for similar D ampersand D tasks at RFP and at other sites

SEM-REV: A sea test site for Marine Energy Converter

International Nuclear Information System (INIS)

Berhault, Christian; Le Crom, Izan; Le Bihan, Gerard

2015-01-01

Thanks to a main funding of Region des Pays de la Loire, the sea test site SEM-REV has been developed by Ecole Centrale de Nantes since 2007 to test both Wave Energy Converters and Floating Wind Turbine in real sea conditions. The sea test site is equipped with a set of oceanographic sensors and with an electric cable of 8 MW, connected to the French grid. The project is located close to Le Croisic, Western coast of France. SEM-REV is one of the main test facilities operated by Ecole Centrale de Nantes to support MRE technologies development. After presenting the initial motivations of the SEM-REV development, the paper describes, in parts 1 and 2, the complete administrative and technical processes that were followed to reach SEM-REV commissioning in 2014. The third part is focused on the exploitation process, including technical and contractual specifications imposed to the MRE developers for installation, tests and decommissioning phases. Some words are given also on the R and D projects using the SEM-REV in-situ monitoring system: prediction of environmental conditions, bio-fooling, acoustic impact. Even if operational phase is not started, expected extensions of the tests site are listed. (authors)

Can interpreting sediment toxicity tests a mega sites benefit from novel approaches to normalization to address batching of tests?

Science.gov (United States)

Sediment toxicity tests are a key tool used in Ecological Risk Assessments for contaminated sediment sites. Interpreting test results and defining toxicity is often a challenge. This is particularly true at mega sites where the testing regime is large, and by necessity performed ...

Revelation and registration of geological heritage on the test sites territories

International Nuclear Information System (INIS)

Kazakova, Yu.I.

1999-01-01

Studies of geotypes in Kazakhstan are carrying out from 1993. 'Geological heritage of Kazakhstan' data base incorporating more than 400 objects is developed. The geotypes classification by a diverse features was worked out. The showing up and accounting system of geotype objects diversity was demonstrated and approved on the international symposia on geological heritage protection (ProGeo-97 and ProGeo-98). But this work does not conducted on the test sites yet. At present these territories have been more available but data about geotypes within its boundaries are fragmentary yet. Among its there are locations of interesting dinosaur remains (Baikanur space site), ancient mine working, petroglyphic drawings, agate manifestations, picturesque landscapes (Semipalatinsk test site). Within test zones there are such interesting antropogenic noticeably object as places of nuclear explosions including the famous Atomic Lake. There are a lot interest object on the territories adjoint to test sites (stratigraphical open-casts of the universal importance, paleontological remains and others) gives basis for to suggest that on the closed earlier territories there are a lot of interesting geotypes. At present these sites are entering to rehabilitation stage. At that one of the important measure must be study of geotypes situated within its limits

Before and after retrofit - response of a building during ambient and strong motions

Science.gov (United States)

Celebi, M.; Liu, Huaibao P.; ,

1998-01-01

This paper presents results obtained from ambient vibration and strong-motion responses of a thirteen-story, moment-resisting steel framed Santa Clara County Office Building (SCCOB) before being retrofitted by visco-elastic dampers and from ambient vibration response following the retrofit. Understanding the cumulative structural and site characteristics that affect the response of SCCOB before and after the retrofit is important in assessing earthquake hazards to other similar buildings and decision making in retrofitting them. The results emphasize the need to better evaluate structural and site characteristics in developing earthquake resisting designs that avoid resonating effects. Various studies of the strong-motion response records from the SCCOB during the 24 April 1984 (MHE) Morgan Hill (MS = 6.1), the 31 March 1986 (MLE) Mt. Lewis (MS = 6.1) and the 17 October 1989 (LPE) Loma Prieta (MS = 7.1) earthquakes show that the dynamic characteristics of the building are such that it (a) resonated (b) responded with a beating effect due to close-coupling of its translational and torsional frequencies, and (c) had a long-duration response due to low-damping. During each of these earthquakes, there was considerable contents damage and the occupants felt the rigorous vibration of the building. Ambient tests of SCCOB performed following LPE showed that both translational and torsional periods of the building are smaller than those derived from strong motions. Ambient tests performed following the retrofit of the building with visco-elastic dampers show that the structural fundamental mode frequency of the building has increased. The increased frequency implies a stiffer structure. Strong-motion response of the building during future earthquakes will ultimately validate the effectiveness of the retrofit method.This paper presents results obtained from ambient vibration and strong-motion responses of a thirteen-story, moment-resisting steel framed Santa Clara County

Nevada test site water-supply wells

International Nuclear Information System (INIS)

Gillespie, D.; Donithan, D.; Seaber, P.

1996-05-01

A total of 15 water-supply wells are currently being used at the Nevada Test Site (NTS). The purpose of this report is to bring together the information gleaned from investigations of these water-supply wells. This report should serve as a reference on well construction and completion, static water levels, lithologic and hydrologic characteristics of aquifers penetrated, and general water quality of water-supply wells at the NTS. Possible sources for contamination of the water-supply wells are also evaluated. Existing wells and underground nuclear tests conducted near (within 25 meters (m)) or below the water table within 2 kilometers (km) of a water-supply were located and their hydrogeologic relationship to the water-supply well determined

Population dose near the Semipalatinsk test site.

Science.gov (United States)

Hille, R; Hill, P; Bouisset, P; Calmet, D; Kluson, J; Seisebaev, A; Smagulov, S

1998-10-01

To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 microSv/year for 90Sr. For other radionuclides the internal doses are also negligible.

Population dose near the Semipalatinsk test site

International Nuclear Information System (INIS)

Hille, R.; Hill, P.; Kluson, J.; Seisebaev, A.; Smagulov, S.

1998-01-01

To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/ year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 μSv/year for 90 Sr. For other radionuclides the internal doses are also negligible. (orig.)

Off-site monitoring for the Mighty Oak nuclear test

International Nuclear Information System (INIS)

Black, S.C.; Smith, A.E.; Costa, C.F.

1986-07-01

After a nuclear explosives test, code name Mighty Oak, the tunnel leading to the test point became contaminated with radioactive debris. To re-enter and recover valuable equipment and data, the DOE purged the tunnel air using particulate and charcoal filters to minimize discharge of radioactivity to the atmosphere. During this purging, the EPA established special air samples supplementing their routine air monitoring networks. Analysis of the collected samples for radioactive noble gases and for gamma-emitting radionuclides indicated that only low levels of xenon-133 were released in amounts detectable in populated areas near the Nevada Test Site. The maximum dose to an individual was calculated to be 0.36 microrem, assuming that person remained in the open field at the measurement site during the whole period of the purging

Aquifer recharge with reclaimed water in the Llobregat Delta. Laboratory batch experiments and field test site.

Science.gov (United States)

Tobella, J.

2010-05-01

Summary Spain, as most other Mediterranean countries, faces near future water shortages, generalized pollution and loss of water dependent ecosystems. Aquifer recharge represents a promising option to become a source for indirect potable reuse purposes but presence of pathogens as well as organic and inorganic pollutants should be avoided. To this end, understanding the processes of biogeochemical degradation occurring within the aquifer during infiltration is capital. A set of laboratory batch experiments has been assembled in order to assess the behaviour of selected pesticides, drugs, estrogens, surfactant degradation products, biocides and phthalates under different redox conditions. Data collected during laboratory experiments and monitoring activities at the Sant Vicenç dels Horts test site will be used to build and calibrate a numerical model (i) of the physical-chemical-biochemical processes occurring in the batches and (ii) of multicomponent reactive transport in the unsaturated/saturated zone at the test site. Keywords Aquifer recharge, batch experiments, emerging micropollutants, infiltration, numerical model, reclaimed water, redox conditions, Soil Aquifer Treatment (SAT). 1. Introduction In Spain, the Llobregat River and aquifers, which supply water to Barcelona, have been overexploited for years and therefore, suffer from serious damages: the river dries up on summer, riparian vegetation has disappeared and seawater has intruded the aquifer. In a global context, solutions to water stress problems are urgently needed yet must be sustainable, economical and safe. Recent developments of analytical techniques detect the presence of the so-called "emerging" organic micropollutants in water and soils. Such compounds may affect living organisms when occurring in the environment at very low concentrations (microg/l or ng/l). In wastewater and drinking water treatment plants, a remarkable removal of these chemicals from water can be obtained only using

Test site experiments with a reconfigurable stepped frequency GPR

Science.gov (United States)

Persico, Raffaele; Matera, Loredana; Piro, Salvatore; Rizzo, Enzo; Capozzoli, Luigi

2016-04-01

In this contribution, some new possibilities offered by a reconfigurable stepped frequency GPR system are exposed. In particular, results achieved from a prototypal system achieved in two scientific test sites will be shown together with the results achieved in the same test sites with traditional systems. Moreover a novel technique for the rejection of undesired interferences is shown, with the use of interferences caused on purpose. Key words GPR, reconfigurable stepped frequency. Introduction A reconfigurable GPR system is meant as a GPR where some parameter can be changed vs. the frequency (if the system is stepped frequency) or vs. the time (if the system is pulsed) in a programmable way. The programming should then account for the conditions met in the scenario at hand [1]. Within the research project AITECH (http://www.aitechnet.com/ibam.html), the Institute for Archaeological and Monumental Heritage, together with the University of Florence and the IDS corporation have implemented a prototype, that has been used in sites of cultural interest in Italy [2], but also abroad in Norway and Malta. The system is a stepped frequency GPR working in the frequency range 50-1000 MHz, and its reconfigurability consists in three properties. The first one is the fact that the length of the antennas can be modulated by the aperture and closure of two electronic switches present along the arms of the antennas, so that the antennas can become electrically (and electronically) longer or shorter, so becoming more suitable to radiate some frequencies rather than some other. In particular, the system can radiate three different bands in the comprehensive range between 50-1000 MHz, so being suitable for different depth range of the buried targets, and the three bands are gathered in a unique "going through" because for each measurement point the system can sweep the entire frequency range trhee times, one for each configuration of the switchres on the arms. The second property is

77 FR 29986 - Savannah River Site Building 235-F Safety

Science.gov (United States)

2012-05-21

..., the Building 235-F fire detection system is not credited, does not provide complete coverage, nor is..., Building 235-F does not have a fire suppression system to prevent an incipient stage fire from growing into... standpipes or hose connections inhibits the ability of the fire department to fight a fire inside Building...

Calculation methods of Structure-Soil-Structure Interaction (3SI) for embedded buildings: Application to NUPEC tests

International Nuclear Information System (INIS)

Clouteau, D.; Broc, D.; Devesa, G.; Guyonvarh, V.; Massin, P.

2012-01-01

This work aims at improving and validating methods coupling Finite Element (FE) and Boundary Element (BE) Methods in the context of Soil-Structure Interaction (SSI) and Structure-Soil-Structure Interaction (3SI) tests performed by NUPEC on mock-up structures built on an unmade ground. Several cases have been tested: single and juxtaposed buildings, shallow and embedded foundations, with various loading conditions: forced and natural seismic loadings. The numerical simulations of forced vibration tests are in good agreement with the results of the NUPEC experiments in the case of two embedded buildings either in terms of amplitude and resonance. The numerical simulation of seismic response tests by FEM and BEM allows for a proper choice of the 'reference point' where the computed and the experimental displacements coincide. A parametric analysis of Structure-Soil-Structure Interaction carried out by the FEM has allowed to determine the influence of some parameters on SSI. Most of them like the position of the building in the excavation, the direction of the load, the quality of the contact between the sidewalls of the buildings and the soil for embedded foundations, do not show to have a strong influence on the dynamic system behaviour, which is mainly governed by the stiffness of the first soil layer. As far as 3SI is concerned, this paper shows that when the cross interaction has a small effect on the building response in the case of surface foundations, it has a strong influence in the case of embedded foundations with an important decrease of the response at the top of the buildings. (authors)

On-line reactor building integrity testing at Gentilly-2 (summary of results 1987-1994)

International Nuclear Information System (INIS)

Collins, N.; Lafreniere, P.

1994-01-01

In 1987, Hydro-0uebec embarked on an ambitious development program to provide the Gentilly-2 Nuclear Power Station with an effective and practical Reactor Building Containment integrity Test (CIT). In October 1992, the inaugural low pressure (3 kPa(g) nominal) CIT at 100% F.P was performed. The test was conclusive and the CIT was declared In-Service for containment integrity verification on-line. Five subsequent CITs performed in 1993 and 1994 have demonstrated the expected leak rate results and good reliability. The outstanding feature of the CITs is the demonstrated accurary of better than 5% of the measured leak rate. The CIT was developed with the primary goal of demonstrating 'overall' containment availability. Specifically it was designed to detect a 25 mm. diameter leak or hole in the Reactor Building. However, the remarkable CIT accuracy allows reliable detection of a 2 mm. hole. The Gentilly-2 CIT is an innovative approach based on the Temperature Compensation Method (TCM) which uses a reference volume composed of an extensive tubular network of several different diameters. This eliminates the need to track numerous temperature points. A second independent tubular network includes numerous humidity sampling points, thereby enabling the mearurernent of minute pressure variations inside the Reactor Building, independant of the spatial and temporal humidity behaviour. This Gentilly-2 TOM System has been demonstrated to work at both high and low test pressures. The GentiIly-2 design allows the CIT to be performed at a nominal 3 kPa(g) test pressure during a 12-hour period (28 hours total with alignment time) with the reactor at full power. The traditional Reactor Building Pressure Test (RBPT) is typically performed at high pressure (124 kPa(g) in a 5-day critical path window (7 days total with alignment time) during an annual shutdown

Experimental study of a model and parameters calculating annual mean atmospheric dispersion factor for a nuclear power plant to be build in coastal site

International Nuclear Information System (INIS)

Hu Erbang; Chen Jiayi; Zhang Maoshuan; Gao Zhanrong; Yao Rentai; Jia Peirong; Qiao Qingdang

1999-01-01

The author tries to develop a new model calculating annual mean atmospheric dispersion factor for a nuclear power plant to be build in coastal site based on field experiments. This model considers not only the difference between shore ward and off-shore but also the comprehensive effect of following factors: mixed layer and thermal internal boundary layer, mixing release and variation of diffusion parameters due to the distance from coast and so on. The various parameters needed in the model are obtained from the field atmospheric experiments done on the NPP site during 1995∼1996. There dimension joint frequency is got from wind and temperature measurements at 4 heights of a tower of 100 m; diffusion parameters shore ward and off-shore from turbulent measurement and wind tunnel simulation test; the parameters relative to sea and land breeze and thermal internal boundary layer are obtained from tests with low altitude radiosonde and lost balloon at 3 sites during two periods of Summer and Winter. Finally a comparison of the results given by this model and commonly used model provided by relative guides is done. The comparison shows that about 1 times under estimation is found for the maximum of annual mean atmospheric dispersion factor in common model because the effect from thermal internal boundary layer and other factors are neglected

Shaking Table Tests Validating Two Strengthening Interventions on Masonry Buildings

International Nuclear Information System (INIS)

De Canio, Gerardo; Poggi, Massimo; Clemente, Paolo; Muscolino, Giuseppe; Palmeri, Alessandro

2008-01-01

numerical and experimental research has been carried out, aimed at validating two different strengthening interventions on masonry buildings: (i) the substitution of the existing roof with timber-concrete composite slabs, which are able to improve the dynamic behaviour of the structure without excessively increase the mass, and (ii) the reinforcement of masonry walls with FRP materials, which allow increasing both stiffness and strength of the construction. The experimental tests have been performed on a 1:2 scale model of a masonry building resembling a special type, the so-called 'tipo misto messinese', which is proper to the reconstruction of the city of Messina after the 1783 Calabria earthquake. The model, incorporating a novel timber-concrete composite slab, has been tested on the main shaking table available at the ENEA Research Centre 'Casaccia', both before and after the reinforcement with FRP materials. Some aspects related to the definition of the model and to the selection of an appropriate seismic input will be discussed, and numerical results confirming the effectiveness of the interventions mentioned above will be presented

Monitoring production using surface deformation: the Hijiori test site and the Okuaizu geothermal field

International Nuclear Information System (INIS)

Vasco, D.W.; Karasaki, Kenzi

2002-01-01

Production in geothermal reservoirs often leads to observable surface displacement. As shown in this paper, there is a direct relationship between such displacement and reservoir dynamics. This relationship is exploited in order to image fluid flow at two geothermal field sites. At the first locality, the Hijiori Hot Dry Rock (HDR) test site, 17 tilt meters record deformation associated with a 2.2 km deep injection experiment. Images of fluid migration along a ring fracture system of the collapsed Hijiori caldera are obtained. At the Okuaizu geothermal field, leveling and tilt meter data provide constraints on long- and short-term fluid movement within the reservoir. A set of 119 leveling data suggest that the north-to-northeast trending Takiyagawa fault acts as a barrier to flow. The northwesterly oriented Chinoikezawa and Sarukurazawa faults appear to channel fluid from the southeast. The tilt data from Okuaizu indicate that a fault paralleling the Takiyagawa fault zone acts as a conduit to transient flow, on a time scale of several weeks. The volume strain in a region adjacent to the injection wells reaches a maximum and then decreases with time. The transient propagation of fluid along the fault may be due to pressure build-up, resulting from the re-initiation of injection. (author)

Excessive leakage measurement using pressure decay method in containment building local leakage rate test at nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Lee, Won Kyu; Kim, Chang Soo; Kim, Wang Bae [KHNP, Central Research Institute, Daejeon (Korea, Republic of)

2016-06-15

There are two methods for conducting the containment local leakage rate test (LLRT) in nuclear power plants: the make-up flow rate method and the pressure decay method. The make-up flow rate method is applied first in most power plants. In this method, the leakage rate is measured by checking the flow rate of the make-up flow. However, when it is difficult to maintain the test pressure because of excessive leakage, the pressure decay method can be used as a complementary method, as the leakage rates at pressures lower than normal can be measured using this method. We studied the method of measuring over leakage using the pressure decay method for conducting the LLRT for the containment building at a nuclear power plant. We performed experiments under conditions similar to those during an LLRT conducted on-site. We measured the characteristics of the leakage rate under varies pressure decay conditions, and calculated the compensation ratio based on these data.

Site characterization and monitoring data from Area 5 Pilot Wells, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

1994-02-01

The Special Projects Section (SPS) of Reynolds Electrical ampersand Engineering Co., Inc. (REECO) is responsible for characterizing the subsurface geology and hydrology of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division, Waste Operations Branch. The three Pilot Wells that comprise the Pilot Well Project are an important part of the Area 5 Site Characterization Program designed to determine the suitability of the Area 5 RWMS for disposal of low-level waste (LLW), mixed waste (MW), and transuranic waste (TRU). The primary purpose of the Pilot Well Project is two-fold: first, to characterize important water quality and hydrologic properties of the uppermost aquifer; and second, to characterize the lithologic, stratigraphic, and hydrologic conditions which influence infiltration, redistribution, and percolation, and chemical transport through the thick vadose zone in the vicinity of the Area 5 RWMS. This report describes Pilot Well drilling and coring, geophysical logging, instrumentation and stemming, laboratory testing, and in situ testing and monitoring activities

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.

ISC origin times for announced and presumed underground nuclear explosions at several test sites

International Nuclear Information System (INIS)

Rodean, H.C.

1979-01-01

Announced data for US and French underground nuclear explosions indicate that nearly all detonations have occurred within one or two tenths of a second after the minute. This report contains ISC origin-time data for announced explosions at two US test sites and one French test site, and includes similar data for presumed underground nuclear explosions at five Soviet sites. Origin-time distributions for these sites are analyzed for those events that appeared to be detonated very close to the minute. Particular attention is given to the origin times for the principal US and Soviet test sites in Nevada and Eastern Kazakhstan. The mean origin times for events at the several test sites range from 0.4 s to 2.8 s before the minute, with the earlier mean times associated with the Soviet sites and the later times with the US and French sites. These times indicate lower seismic velocities beneath the US and French sites, and higher velocities beneath the sites in the USSR 9 figures, 8 tables

Corrective Action Decision Document, Area 15 Environmental Protection Agency Farm Laboratory Building, Corrective Action Unit No. 95, Revision 0

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-18

This report is the Corrective Action Decision Document (CADD) for the Nevada Test Site (NTS) Area 15 U.S. Environmental Protection Agency (EPA) Farm, Laboratory Building (Corrective Action Unit [CAU] No. 95), at the Nevada Test Site, Nye County, Nevada. The scope of this CADD is to identify and evaluate potential corrective action alternatives for the decommissioning and decontamination (D and D) of the Laboratory Building, which were selected based on the results of investigative activities. Based on this evaluation, a preferred corrective action alternative is recommended. Studies were conducted at the EPA Farm from 1963 to 1981 to determine the animal intake and retention of radionuclides. The main building, the Laboratory Building, has approximately 370 square meters (4,000 square feet) of operational space. Other CAUS at the EPA Farm facility that will be investigated and/or remediated through other environmental restoration subprojects are not included in this CADD, with the exception of housekeeping sites. Associated structures that do not require classification as CAUS are considered in the evaluation of corrective action alternatives for CAU 95.

Corrective Action Decision Document, Area 15 Environmental Protection Agency Farm Laboratory Building, Corrective Action Unit No. 95, Revision 0