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Sample records for fiji french polyne

  1. Fiji Is Just ImageJ

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    be described as a "batteries-included" distribution of ImageJ (and ImageJ2), bundling Java, Java3D and a lot of plugins organized into a coherent structure. Availability Fiji's...

  2. Scott French

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the earth's interior with seismic waves, supercomputers, and PGAS Scott French 1* and Barbara Romanowicz 1,2 1 Berkeley Seismological Laboratory, UC Berkeley, Berkeley, CA, USA 2 Institut de Physique du Globe de Paris, Paris, France * Now at: Google Inc. Motivation: Why seismic imaging? ● Short answer: Because we can't just dig a big hole ● Surface and space-based observations provide our only window into the evolution and interior dynamics of Earth ○ Geophysical observations (bathymetry,

  3. French intensive truck garden

    SciTech Connect (OSTI)

    Edwards, T D

    1983-01-01

    The French Intensive approach to truck gardening has the potential to provide substantially higher yields and lower per acre costs than do conventional farming techniques. It was the intent of this grant to show that there is the potential to accomplish the gains that the French Intensive method has to offer. It is obvious that locally grown food can greatly reduce transportation energy costs but when there is the consideration of higher efficiencies there will also be energy cost reductions due to lower fertilizer and pesticide useage. As with any farming technique, there is a substantial time interval for complete soil recovery after there have been made substantial soil modifications. There were major crop improvements even though there was such a short time since the soil had been greatly disturbed. It was also the intent of this grant to accomplish two other major objectives: first, the garden was managed under organic techniques which meant that there were no chemical fertilizers or synthetic pesticides to be used. Second, the garden was constructed so that a handicapped person in a wheelchair could manage and have a higher degree of self sufficiency with the garden. As an overall result, I would say that the garden has taken the first step of success and each year should become better.

  4. Space scientist tapped for French knighthood

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Space scientist tapped for French knighthood Space scientist tapped for French knighthood Roger Wiens was awarded the honorary title of chevalier (knight) in France's Academic ...

  5. RomanowiczFrenchRev.pptx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Calibration of Mantle Structure at Global and Regional Scales Using
 Full-Waveform Seismic Tomography" Scott French! sfrench@seismo.berkeley.edu! Romanowicz Group! Berkeley Seismological Laboratory! UC Berkeley! NERSC BES Requirements for 2017! October 8-9, 2013! Gaithersburg, MD! Present and Future Computing Requirements Seismological Laboratory Berkeley University of California Project Description! PI: Prof. Barbara Romanowicz Berkeley Seismological Laboratory, UC Berkeley;

  6. Space scientist tapped for French knighthood

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Space scientist tapped for French knighthood At the Bradbury Latest Issue:May 2016 all issues All Issues » submit Space scientist tapped for French knighthood Roger Wiens was awarded the honorary title of chevalier (knight) in France's Academic Order of Palms for his work in forging strong ties between the French and American scientific communities. May 1, 2016 Roger Wiens (right), leader of Los Alamos National Laboratory's ChemCam project, received the honorary title of knight in France's

  7. Space scientist tapped for French knighthood

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Space scientist tapped for French knighthood Space scientist tapped for French knighthood Roger Wiens was awarded the honorary title of chevalier (knight) in France's Academic Order of Palms for his work in forging strong ties between the French and American scientific communities. April 11, 2016 Roger Wiens (right), leader of Los Alamos National Laboratory's ChemCam project, received the honorary title of knight in France's Academic Order of Palms. Christophe Lemoine (left), Consul General of

  8. Richard J. French, Ph.D. | Bioenergy | NREL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Richard J. French Richard J. French, Ph.D. Senior Scientist Richard.French@nrel.gov | 303-384-6135 Research Interests Biomass thermal processing Hydrotreating Catalytic pyrolysis Steam reforming to hydrogen Gasification Bench-scale reactors Process monitoring Molecular beam mass spectrometry Molecular structure Instrumentation and controls Laboratory equipment design and construction Computer-aided design (CAD) Education Ph.D., Chemistry, Oregon State University B.S., Chemistry, Wheaton College

  9. French landmark decree authorizes ITER construction | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab French landmark decree authorizes ITER construction By John Greenwald November 20, 2012 Tweet Widget Google Plus One Share on Facebook The French government has capped more than two years of review by issuing a license for the construction of ITER, the international fusion project that the European Union, the United States and five other countries are building in Cadarache, France, to demonstrate the feasibility of fusion energy. French Prime Minister Jean-Marc Ayrault signed the

  10. French Camp, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    French Camp, California: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 37.8840922, -121.2710555 Show Map Loading map... "minzoom":false,"mapp...

  11. Cigeo, the French Geological Repository Project - 13022

    SciTech Connect (OSTI)

    Labalette, Thibaud; Harman, Alain; Dupuis, Marie-Claude; Ouzounian, Gerald

    2013-07-01

    The Cigeo industrial-scale geological disposal centre is designed for the disposal of the most highly-radioactive French waste. It will be built in an argillite formation of the Callovo-Oxfordian dating back 160 million years. The Cigeo project is located near the Bure village in the Paris Basin. The argillite formation was studied since 1974, and from the Meuse/Haute-Marne underground research laboratory since end of 1999. Most of the waste to be disposed of in the Cigeo repository comes from nuclear power plants and from reprocessing of their spent fuel. (authors)

  12. Wind and Water Materials and Structures Database Download

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & ... Eritrea Estonia Ethiopia Fiji Finland France French Polynesia Gabon Gambia Georgia ...

  13. French Broad Elec Member Corp (Tennessee) | Open Energy Information

    Open Energy Info (EERE)

    French Broad Elec Member Corp Place: Tennessee Phone Number: (828)649-2051 or (828)688-4815 or (800)222-6190 or (828)682-6121 Website: www.frenchbroademc.com Twitter:...

  14. French Broad Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    French Broad Elec Member Corp Place: North Carolina Phone Number: (828)649-2051 or (828)688-4815 or (800)222-6190 or (828)682-6121 Website: www.frenchbroademc.com Twitter:...

  15. The French Geological Repository Project Cigeo - 12023

    SciTech Connect (OSTI)

    Harman, Alain; Labalette, Thibaud; Dupuis, Marie-Claude; Ouzounian, Gerald [ANDRA, Chatenay-Malabry (France)

    2012-07-01

    The French Agency for Radioactive Waste Management, ANDRA, was launched by law in 1991 to perform and develop the research programme for managing high level and intermediate level long-lived radioactive waste generated by the French nuclear fleet. After a 15-year intensive research programme, including the study of alternative solutions, an overall review and assessment of the results was organized, including a national public debate. As a result, the Parliament passed a Planning Act on radioactive waste management in 2006. Commissioning of a geological repository by 2025 was one of the most important decisions taken at that time. To reach this goal, a license application must be submitted and reviewed by the competent authorities by 2015. A detailed review and consultation process is, as well, defined in the Planning Act. Beside the legal framework the project needs to progress on two fronts. The first one is on siting. A significant milestone was reached in 2009 with the definition of a defined area to locate the underground repository facilities. This area was approved in March 2010 by the Government, after having collected the opinions and positions of all the interested parties, at both National and local levels. A new phase of dialogue with local players began to refine the implementation scenarios of surface facilities. The final site selection will be approved after a public debate planned for 2013. The second one is the industrial organization, planning and costing. The industrial project of this geological repository was called Cigeo (Centre Industriel de Stockage Geologique). Given the amount of work to be done to comply with the given time framework, a detailed organization with well-defined milestones must be set-up. Cigeo will be a specific nuclear facility, built and operated underground for over a hundred years. The consequence of this long duration is that the development of the repository facilities will take place in successive operational phases. The characteristics of the first waste packages received will determine the work and the corresponding investments by 2025 on the repository site. One of the main challenges will be to accommodate both activities of mining and nuclear operations at the same time and at the same location. From the technical standpoint, ventilation and fire risk cannot be managed through a simple transposition from current nuclear industry practices. The reversibility demand also leads to concrete proposals with regard to repository management flexibility and waste package retrievability. These proposals contribute to the dialogue with stakeholders to prepare for the public debate and a future law which will determine the reversibility conditions. New design developments are expected to be introduced in the application from the current studies conducted until 2014. The possibility of optimization beyond 2015 will be kept open taking into account the one hundred years operating time as well as the capability to integrate feedback gained from the first construction and operation works. The industrial committed work aims to reach the application stage by 2015. The license application procedure was defined by the 2006 Act. Subject to authorization, the construction might begin in 2017. (authors)

  16. Beller, Mark A From: Sent; To: SUbject:* French, Colleen Wednesday,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Beller, Mark A From: Sent; To: SUbject:* French, Colleen Wednesday, February 03,20105:07 PM Shupe, Steven D FW: 03/05 Tour Availability Is this a good enough reason to lower your age limit requirement? This could potentially bring major good tidings to B Reactor. Keep this quiet for now, but pis have the staff look into what's required for a one-day waiver of the age limit. Colleen From: Brockman, David A sent: Wednesday, February 03, 2010 4:57 PM To: French, Colleen C Subject: FW: 03/05 Tour

  17. NREL Teams with French Researchers - News Releases | NREL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NREL Teams with French Researchers NREL Director to Receive Recognition for Joint Research Efforts April 14, 2010 Two men seated at a table with others looking on. Attending the MOU signing were: Véronique Péquignat, International Manager, Rhone Alps Economic Development Agency; Hervé Fradet, Director, Rhône Alps Economic Development Agency; David E. Rodgers, Director, Strategic Energy Analysis, DOE/EERE; Ron Benioff, International Programs Manager, NREL; Daniel Harris, Minister Counselor

  18. Leak before break application in French PWR plants under operation

    SciTech Connect (OSTI)

    Faidy, C.

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  19. Fiji: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    late seventies.The DoE is responsible for the overall National Energy Policy and for off-grid rural electrification. The Ministry of Trade and Commerce is responsible for...

  20. D&D of the French High Enrichment Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    BEHAR, Christophe; GUIBERTEAU, Philippe; DUPERRET, Bernard; TAUZIN, Claude

    2003-02-27

    This paper describes the D&D program that is being implemented at France's High Enrichment Gaseous Diffusion Plant, which was designed to supply France's Military with Highly Enriched Uranium. This plant was definitively shut down in June 1996, following French President Jacques Chirac's decision to end production of Highly Enriched Uranium and dismantle the corresponding facilities.

  1. Summary of Technical Meeting To Compare US/French Approaches for Physical Protection Test Beds

    SciTech Connect (OSTI)

    Mack, Thomas Kimball; Martinez, Ruben; Thomas, Gerald; Palut, Jean-Michel

    2016-01-01

    In September 2015, representatives of the US Department of Energy/National Nuclear Security Administration, including test bed professionals from Sandia National Laboratories, and representatives of the French Alternative Energies and Atomic Energy Commission participated in a one-week workshop to share best practices in design, organization, operations, utilization, improvement, and performance testing of physical protection test beds. The intended workshop outcomes were to (1) share methods of improving respective test bed methodologies and programs and (2) prepare recommendations for standards regarding creating and operating testing facilities for nations new to nuclear operations. At the workshop, the French and American subject matter experts compared best practices as developed at their respective test bed sites; discussed access delay test bed considerations; and presented the limitations/ constraints of physical protection test beds.

  2. Linkage analysis of 19 French breast cancer families, with five chromosome 17q markers

    SciTech Connect (OSTI)

    Mazoyer, S.; Jamot, B.; Sobol, H. ); Lalle, P.; Bignon, Y.J.; Courjal, F. ); Narod, S.A. ); Dutrillaux, B.; Stoppa-Lyonnet, D. )

    1993-04-01

    Nineteen French breast and breast-ovarian cancer families were tested for linkage with five chromosome 17q markers. The five breast-ovarian cancer families as a group give positive evidence for linkage, whereas the 14 breast cancer-only families do not. Heterogeneity of linkage of breast and breast-ovarian cancers is significant in France and supports the existence of more than one susceptibility gene. 15 refs., 2 figs., 3 tabs.

  3. The Creation of a French Basic Nuclear Installation - Description of the Regulatory Process - 13293

    SciTech Connect (OSTI)

    Mahe, Carole; Leroy, Christine

    2013-07-01

    CEA is a French government-funded technological research organization. It has to build a medium-level waste interim storage facility because the geological repository will not be available until 2025. This interim storage facility, called DIADEM, has to be available in 2017. These wastes are coming from the research facilities for spent fuel reprocessing and the dismantling of the most radioactive parts of nuclear facilities. The CEA handles the waste management by inventorying the needs and updating them regularly. The conception of the facility is mainly based on this inventory. It provides quantity and characteristics of wastes and it gives the production schedule until 2035. Beyond mass and volume, main characteristics of these radioactive wastes are chemical nature, radioisotopes, radioactivity, radiation dose, the heat emitted, corrosive or explosive gas production, etc. These characteristics provide information to study the repository safety. DIADEM mainly consists of a concrete cell, isolated from the outside, wherein stainless steel welded containers are stored, stacked in a vertical position in the racks. DIADEM is scheduled to store three types of 8 mm-thick, stainless steel cylindrical containers with an outside diameter 498 mm and height from 620 to 2120 mm. DIADEM will be a basic nuclear installation (INB in French) because of overall activity of radioactive substances stored. The creation of a French basic nuclear installation is subject to authorization according to the French law No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field. The authorization takes into account the technical and financial capacities of the licensee which must allow him to conduct his project in compliance with these interests, especially to cover the costs of decommissioning the installation and conduct remediation work, and to monitor and maintain its location site or, for radioactive waste disposal installations, to cover the definitive shut-down, maintenance and surveillance expenditure. The authorization is issued by a decree adopted upon advice of the French Nuclear Safety Authority and after a public enquiry. In accordance with Decree No. 2007-1557 of November 2, 2007, the application is filed with the ministries responsible for nuclear safety and the Nuclear Safety Authority. It consists of twelve files and four records information. The favorable opinion of the Nuclear Safety Authority on the folder is required to start the public inquiry. Once the public inquiry is completed, the building permit is issued by the prefect. (authors)

  4. Microsoft PowerPoint - 4a-Revitalization Conf2014REVFINAL-Hanford-French

    Office of Legacy Management (LM)

    How DOE and the Tri Cities Community are Working to Redefine Hanford's Post-Cleanup Future Colleen French DOE Richland Operations Office Government Programs Manager 2 Hanford * Hanford was created in 1943 as part of the top secret Manhattan Project * 586 square miles * Production of plutonium increased during Cold War (peaking between 1959-1965) * Hanford produced 2/3 of the nation's plutonium between 1945-1985 * Home to the first full-scale nuclear produc on reactor - the B Reactor, now a

  5. Scott French

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in the Berkeley Seismological Laboratory, his research focused on full-waveform seismic imaging of the earth's interior at the scale of the entire globe. He has been a NERSC...

  6. An Information Building on Radioactivity and Nuclear Energy for the French CEA Cadarache Research Center - 13492

    SciTech Connect (OSTI)

    Brunel, Guy; Denis, Dominique; Boulet, Alain

    2013-07-01

    The CEA Cadarache research center is one of the 10 research centers of the French Alternative Energies and Atomic Energy Commission (CEA). Distributed throughout various research platforms, it focuses on nuclear fission, nuclear fusion, new energy technologies (hydrogen, solar, biomass) and fundamental research in the field of vegetal biology. It is the most important technological research and development centers for energy in Europe. Considering the sensitive nature of nuclear activities, the questions surrounding the issue of radioactive waste, the nuclear energy and the social, economic and environmental concerns for present and future generations, the French Government asked nuclear actors to open communication and to give all the information asked by the Local Information Commission (CLI) and the public [1]. In this context, the CEA Cadarache has decided to better show and explain its expertise and experience in the area of nuclear energy and nuclear power plant design, and to make it available to stakeholders and to the public. CEA Cadarache receives each year more than 9000 visitors. To complete technical visits of the research facilities and laboratories, a scientific cultural center has been built in 2011 to inform the public on CEA Cadarache research activities and to facilitate the acceptance of nuclear energy in a way suited to the level of knowledge of the visitors. A modern interactive exhibition of 150 m{sup 2} allows visitors to find out more about energy, CEA Cadarache research programs, radioactive waste management and radiological impact on the research center activities. It also offers an auditorium for group discussions and for school groups to discover science through enjoyment. This communication center has received several thousand visitors since its opening on October 2011; the initial results of this experience are now available. It's possible to explain the design of this exhibition, to give some statistics on the number of the visitors, their characteristics and their perception after their center visits. (authors)

  7. Fiji-Climate Finance Readiness Programme | Open Energy Information

    Open Energy Info (EERE)

    support from the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU). The Programme will prepare developing countries to effectively and...

  8. The use of LBB concept in French fast reactors: Application to SPX plant

    SciTech Connect (OSTI)

    Turbat, A.; Deschanels, H.; Sperandio, M.

    1997-04-01

    The leak before break (LBB) concept was not used at the design level for SUPERPHENIX (SPX), but different studies have been performed or are in progress concerning different components : Main Vessel (MV), pipings. These studies were undertaken to improve the defense in depth, an approach used in all French reactors. In a first study, the LBB approach has been applied to the MV of SPX plant to verify the absence of risk as regards the core supporting function and to help in the definition of in-service inspection (ISI) program. Defining a reference semi-elliptic defect located in the welds of the structure, it is verified that the crack growth is limited and that the end-of-life defect is smaller than the critical one. Then it is shown that the hoop welds (those which are the most important for safety) located between the roof and the triple point verify the leak-before-break criteria. However, generally speaking, the low level of membrane primary stresses which is favorable for the integrity of the vessel makes the application of the leak-before-break concept more difficult due to small crack opening areas. Finally, the extension of the methodology to the secondary pipings of SPX incorporating recent European works of DCRC is briefly presented.

  9. Phenomenon analysis of stress corrosion cracking in the vessel head penetrations of French PWR`s

    SciTech Connect (OSTI)

    Pichon, C.; Buisine, D.; Faidy, C.; Gelpi, A.; Vaindirlis, M.

    1995-12-31

    During a hydrotest in 1991, a leak was detected on,a reactor vessel head (RVH) penetration of a French PWR. This leak was due to a phenomenon of Primary Water Stress Corrosion Cracking (PWSCC) affecting these penetrations in Alloy 600. The destructive and non-destructive examinations undertaken during the following months highlighted the generic nature of the degradations. In order to well understand this phenomenon and implement the most suitable maintenance policy, a large scale scientific program was decided and performed jointly by Electricite de France and FRAMATOME. The paper will present all the results obtained in this program concerning the parameters governing the PWSCC. In particular the following fields will be developed: (1) the material, its microstructure in line with the manufacturing and its susceptibility to PWSCC; (2) the stresses and their evaluations by measurements, mock up corrosion tests and Finite Element Analysis (FEA); (3) the effect of surface finish on crack initiation; and (4) the crack growth rate. This phenomenon analysis will be useful for evaluating the risk of PWSCC on other Alloy 600 areas in PWR`s primary system.

  10. Stress corrosion cracking of pressurizer instrumentation nozzles in the French 1300 MWe units

    SciTech Connect (OSTI)

    Alter, D.; Robin, Y.; Pichon, M.; Teissier, A.; Thomeret, B.

    1992-12-31

    The 1300 MWE French PWR pressurizers are equipped with nozzles through which instruments penetrate the pressure vessel. The nozzles are made from forged and bored bars of Inconel 600 mechanically expanded in the pressurizer wall. They are then manually welded with Inconel 182 coated electrodes to the internal stainless steel cladding of the pressuriser. To understand the origin of leaks occurring early in life and to assess the extent of the problem we undertook an analysis of the fabrication conditions. Field investigations were carried out by dye penetrant testing on the nozzle bore. Cracks have been found on 35 percent of the 119 tested penetrations. Destructive examination performed on 3 nozzles showed that the circumferential cracks did not go through the wall thickness. Laboratory investigations of the nozzle pulled from Nogent 1 confirmed that the crack morphology corresponded to that of primary water stress corrosion cracking. No correlation has been found between microstructure of the different heats of Alloy 600 and cracking. Nozzle mock-ups investigations allowed residual stress measurements by X-ray diffraction. Stress corrosion cracking tests, showed that only longitudinal cracks can be through-wall while both longitudinal and circumferential cracks are initiated on the internal surface. As a result, Electricite De France decided to replace the Inconel 600 nozzles by stainless steel ones with austenitic st. st. weld. Furthermore, a full inventory of the Alloy 600 parts contained in the primary circuit has been performed. For each localized parts an assessment of the risk of stress corrosion cracking is under progress by studying material structures, stress level, operating conditions and safety point of view.

  11. Structural geology of the French Peak accommodation zone, Nevada Test Site, southwestern Nevada

    SciTech Connect (OSTI)

    Hudson, M.R.

    1997-12-31

    The French Peak accommodation zone (FPAZ) forms an east-trending bedrock structural high in the Nevada Test Site region of southwestern Nevada that formed during Cenozoic Basin and Range extension. The zone separates areas of opposing directions of tilt and downthrow on faults in the Yucca Flat and Frenchman Flat areas. Paleomagnetic data show that rocks within the accommodation zone adjacent to Yucca Flat were not strongly affected by vertical-axis rotation and thus that the transverse strikes of fault and strata formed near their present orientation. Both normal- and oblique strike-slip faulting in the FPAZ largely occurred under a normal-fault stress regime, with least principal stress oriented west-northwest. The normal and sinistral faults in the Puddle Peka segment transfers extension between the Plutonium Valley normal fault zone and the Cane Spring sinistral fault. Recognition of sinistral shear across the Puddle Peak segment allows the Frenchman Flat basin to be interpreted as an asymmetric pull-apart basin developed between the FPAZ and a zone of east-northeast-striking faults to the south that include the Rock Valley fault. The FPAZ has the potential to influence ground-water flow in the region in several ways. Fracture density and thus probably fracture conductivity is high within the FPAZ due to the abundant fault splays present. Moreover,, fractures oriented transversely to the general southward flow of ground water through Yucca Flat area are significant and have potential to laterally divert ground water. Finally, the FPAZ forms a faulted structural high whose northern and southern flanks may permit intermixing of ground waters from different aquifer levels, namely the lower carbonate, welded tuff, and alluvial aquifers. 42 refs.

  12. Environmental impacts of residual Municipal Solid Waste incineration: A comparison of 110 French incinerators using a life cycle approach

    SciTech Connect (OSTI)

    Beylot, Antoine Villeneuve, Jacques

    2013-12-15

    Highlights: 110 French incinerators are compared with LCA based on plant-specific data. Environmental impacts vary as a function of plants energy recovery and NO{sub x} emissions. E.g. climate change impact ranges from ?58 to 408 kg CO{sub 2}-eq/tonne of residual MSW. Implications for LCA of waste management in a decision-making process are detailed. - Abstract: Incineration is the main option for residual Municipal Solid Waste treatment in France. This study compares the environmental performances of 110 French incinerators (i.e. 85% of the total number of plants currently in activity in France) in a Life Cycle Assessment perspective, considering 5 non-toxic impact categories: climate change, photochemical oxidant formation, particulate matter formation, terrestrial acidification and marine eutrophication. Mean, median and lower/upper impact potentials are determined considering the incineration of 1 tonne of French residual Municipal Solid Waste. The results highlight the relatively large variability of the impact potentials as a function of the plant technical performances. In particular, the climate change impact potential of the incineration of 1 tonne of waste ranges from a benefit of ?58 kg CO{sub 2}-eq to a relatively large burden of 408 kg CO{sub 2}-eq, with 294 kg CO{sub 2}-eq as the average impact. Two main plant-specific parameters drive the impact potentials regarding the 5 non-toxic impact categories under study: the energy recovery and delivery rate and the NO{sub x} process-specific emissions. The variability of the impact potentials as a function of incinerator characteristics therefore calls for the use of site-specific data when required by the LCA goal and scope definition phase, in particular when the study focuses on a specific incinerator or on a local waste management plan, and when these data are available.

  13. Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results

    SciTech Connect (OSTI)

    De Rosa, Felice [ENEA, Italian National Agency for New Technologies, Energy and the Environment (Italy)

    2006-07-01

    In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6. FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of 'Loss of Steam Generator (SG) Feedwater' (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when {delta}Tsat < 10 deg. C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 deg. C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its specific models (candling, corium pool behaviour, etc.) they were less good. A future work will be the preparation of an input deck for the new MELCOR 1.8.6. and to perform a code-to-code comparison with ASTEC v1.2 rev. 1. (author)

  14. A Proposal for Geologic Radioactive Waste Disposal Environmental Zero-State and Subsequent Monitoring Definition - First Lessons Learned from the French Environment Observatory - 13188

    SciTech Connect (OSTI)

    Landais, Patrick; Leclerc, Elisabeth; Mariotti, Andre

    2013-07-01

    Obtaining a reference state of the environment before the beginning of construction work for a geological repository is essential as it will be useful for further monitoring during operations and beyond, thus keeping a memory of the original environmental state. The area and the compartments of the biosphere to be observed and monitored as well as the choice of the markers (e.g. bio-markers, biodiversity, quality of the environment, etc.) to be followed must be carefully selected. In parallel, the choice and selection of the environmental monitoring systems (i.e. scientific and technical criteria, social requirements) will be of paramount importance for the evaluation of the perturbations that could be induced during the operational phase of the repository exploitation. This paper presents learning points of the French environment observatory located in the Meuse/Haute-Marne that has been selected for studying the feasibility of the underground disposal of high level wastes in France. (authors)

  15. Scott French! NERSC User Services Group! New User Training!

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    login node based on: - Number o f c onnec3ons - Memory o f p revious c onnec3ons f rom s ame I P --- 4 --- Login Node Usage * Login nodes are shared by many users, all the Dme *...

  16. Running Jobs Scott French" NERSC User Services Group" New User...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    wait for job to start mom% cd PBSOWORKDIR mom% aprun -n 48 .mycode.x 18 Serial Jobs * Carver h as a s pecial q ueue f or r unning s erial j obs - A s ingle p rocess...

  17. Promouvoir Une Energie Durable Pour Tous (French Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-06-01

    The Clean Energy Solutions Center, an initiative of the Clean Energy Ministerial and UN-Energy, helps governments design and adopt policies and programs that support the deployment of transformational low-carbon technologies. The Solutions Center serves as a first-stop clearinghouse of clean energy policy reports, data, and tools and provides expert assistance and peer-to-peer learning forums. This factsheet highlights key Solutions Center offerings, including 'ask an expert' assistance on clean energy policy matters, training and peer learning, and technical resources for policy makers worldwide.

  18. French perspective on diesel engines & emissions | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    | Department of Energy This case study describes how Freescale Semiconductor implemented projects at its Oak Hill Fab plant in Austin, Texas, that reduced annual plant-wide energy consumption by 28 million kilowatt hours (kWh) of electricity and 26,000 million British thermal units (Btu) of natural gas between 2006 and 2009, saving more than $2 million each year. PDF icon Freescale Semiconductor Successfully Implements an Energy Management System (June 2011) More Documents & Publications

  19. Total Net Imports of Crude Oil and Petroleum Products into the...

    U.S. Energy Information Administration (EIA) Indexed Site

    Rica Croatia Cyprus Czech Republic Denmark Djbouti Dominica Dominican Republic Egypt El Salvador Equatorial Guinea Ethiopia Eritrea Estonia Falkland Islands Fiji Finland France ...

  20. Total All Countries Exports of Crude Oil and Petroleum Products...

    U.S. Energy Information Administration (EIA) Indexed Site

    Curacao Cyprus Czech Republic Denmark Djbouti Dominica Dominican Republic Ecuador Egypt El Salvador Equatorial Guinea Eritrea Estonia Ethiopia Falkland Islands Fiji Finland France ...

  1. Joaquin Correa JoaquinCorrea@lbl.gov NERSC Data...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Climate, Cosmology, Kbase, Materials, BioImaging, Your science Statistics, Machine Learning R, python, MLBase Image Processing MATLAB OMERO, Fiji Graph Analytics GraphX...

  2. Non-immunogenic, hydrophilic/cationic block copolymers and uses thereof

    DOE Patents [OSTI]

    Scales, Charles W.; Huang, Faqing; McCormick, Charles L.

    2010-05-18

    The present invention provides novel non-immunogenic, hydrophilic/cationic block copolymers comprising a neutral-hydrophilic polymer and a cationic polymer, wherein both polymers have well-defined chain-end functionality. A representative example of such a block copolymer comprises poly(N-(2-hydroxypropyl)methacrylamide) (PHPMA) and poly(N-[3-(dimethylamino)propyl]methacrylamide) (PDMAPMA). Also provided is a synthesis method thereof in aqueous media via reversible addition fragmentation chain transfer (RAFT) polymerization. Further provided are uses of these block copolymers as drug delivery vehicles and protection agents.

  3. ImageJ

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ImageJ ImageJ Description and Overview ImageJ is a public domain Java image processing program inspired by NIH Image. Fiji means Fiji is Just ImageJ, and stands for a customization of ImageJ with tools to handle microscope data. ImageJ/Fiji can display, edit, analyze, process, save and print 8-bit, 16-bit and 32-bit images. It can read many image formats including TIFF, GIF, JPEG, BMP, DICOM, FITS and "raw". It supports "stacks", a series of images that share a single window.

  4. WindsForPDF1.pgm

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Kaluwin, and G. W. Lennon. In July 1998, Australian Ambassador for the Environment, Ms. Meg McDonald, officially launched the curriculum modules in Fiji. The books were well...

  5. Microsoft PowerPoint - ARM_2009_3_Fu.ppt

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Radiative heatng rates at the ARM Manus site in 2000. (a) Annual mean with O 3 from Java (solid) and Fiji (dashed); (b) difference between all sky and clear sky. IR Solar Net...

  6. User:GregZiebold/Developing Country Programs Map | Open Energy...

    Open Energy Info (EERE)

    of Congo 12 Djibouti 3 Dominica 9 Dominican Republic 12 Ecuador 7 Egypt 14 El Salvador 8 Equatorial Guinea 4 Eritrea 3 Estonia 2 Ethiopia 21 Fiji 1 Gabon 10 ... further...

  7. Prevalence and Treatment Management of Oropharyngeal Candidiasis in Cancer Patients: Results of the French Candidoscope Study

    SciTech Connect (OSTI)

    Gligorov, Joseph; Bastit, Laurent; Gervais, Honorine; Henni, Mehdi; Kahila, Widad; Lepille, Daniel; Luporsi, Elisabeth; Sasso, Giuseppe; Varette, Charles; Azria, David

    2011-06-01

    Purpose: The aim of this pharmaco-epidemiological study was to evaluate the prevalence of oropharyngeal candidiasis (OPC) in cancer patients treated with chemotherapy and/or radiotherapy. Methods and Materials: Signs and symptoms of OPC were noted for all patients. Antifungal therapeutic management was recorded in OPC patients. Patients receiving local antifungal treatments were monitored until the end of treatment. Results: Enrolled in the study were 2,042 patients with solid tumor and/or lymphoma treated with chemotherapy and/or another systemic cancer treatment and/or radiotherapy. The overall prevalence of OPC was 9.6% (95% confidence interval, 8.4%-11.0%]in this population. It was most frequent in patients treated with combined chemoradiotherapy (22.0%) or with more than two cytotoxic agents (16.9%). Local antifungal treatments were prescribed in 75.0% of OPC patients as recommended by guidelines. The compliance to treatment was higher in patients receiving once-daily miconazole mucoadhesive buccal tablet (MBT; 88.2%) than in those treated with several daily mouthwashes of amphotericin B (40%) or nystatin (18.8%). Conclusion: OPC prevalence in treated cancer patients was high. Local treatments were usually prescribed as per guidelines. Compliance to local treatments was better with once-daily drugs.

  8. World first in high level waste vitrification - A review of French vitrification industrial achievements

    SciTech Connect (OSTI)

    Brueziere, J.; Chauvin, E. [AREVA, 1 place Jean Millier, 92084 Paris La Defense (France); Piroux, J.C. [Joint Vitrification Laboratory - LCV, Marcoule, BP171, 30207 Bagnols sur Ceze (France)

    2013-07-01

    AREVA has more than 30 years experience in operating industrial HLW (High Level radioactive Waste) vitrification facilities (AVM - Marcoule Vitrification Facility, R7 and T7 facilities). This vitrification technology was based on borosilicate glasses and induction-heating. AVM was the world's first industrial HLW vitrification facility to operate in-line with a reprocessing plant. The glass formulation was adapted to commercial Light Water Reactor fission products solutions, including alkaline liquid waste concentrates as well as platinoid-rich clarification fines. The R7 and T7 facilities were designed on the basis of the industrial experience acquired in the AVM facility. The AVM vitrification process was implemented at a larger scale in order to operate the R7 and T7 facilities in-line with the UP2 and UP3 reprocessing plants. After more than 30 years of operation, outstanding record of operation has been established by the R7 and T7 facilities. The industrial startup of the CCIM (Cold Crucible Induction Melter) technology with enhanced glass formulation was possible thanks to the close cooperation between CEA and AREVA. CCIM is a water-cooled induction melter in which the glass frit and the waste are melted by direct high frequency induction. This technology allows the handling of highly corrosive solutions and high operating temperatures which permits new glass compositions and a higher glass production capacity. The CCIM technology has been implemented successfully at La Hague plant.

  9. Running Jobs Scott French" NERSC User Services Group" New User Training"

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    August 13, 2015 Jobs at NERSC * Most a re p arallel j obs ( 10s t o 1 00,000+ c ores) * Produc7on r uns e xecute i n b atch m ode * Interac7ve a nd d ebug j obs a re s upported f or u p t o 3 0 minutes * Typically r un 7 mes a re a f ew t o 1 0s o f h ours. - Each m achine h as d ifferent l imits. - Limits a re n ecessary b ecause o f M TBF a nd t he n eed t o accommodate 5 ,500 u sers' j obs * Also a n umber o f " serial" j obs - Typically " pleasantly p arallel" s imulaCon

  10. Running Jobs Scott French" NERSC User Services Group" New User Training"

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    February 23, 2015 Jobs at NERSC * Most j obs a re p arallel, u sing 1 0s t o 1 00,000+ c ores * Produc8on r uns e xecute i n b atch m ode * Interac8ve a nd d ebug j obs a re s upported f or u p t o 3 0 minutes * Typically r un 8 mes a re a f ew t o 1 0s o f h ours. - Each m achine h as d ifferent l imits. - Limits a re n ecessary b ecause o f M TBF a nd t he n eed t o accommodate 5 ,500 u sers' j obs * Also a n umber o f ' serial' j obs - Typically s ome k ind o f p leasantly p arallel s

  11. Energy Department and French Commission on Atomic Energy and Alternative Energies Sign New Research and Development Agreement

    Broader source: Energy.gov [DOE]

    Washington, D.C. – On June 19, 2012, U.S. Energy Secretary Steven Chu and Dr. Bernard Bigot, Chairman of France’s Commission on Atomic Energy and Alternative Energies (CEA), signed an agreement to...

  12. Impact of TBI on late effects in children treated by megatherapy for Stage IV neuroblastoma. A study of the French Society of Pediatric oncology

    SciTech Connect (OSTI)

    Flandin, Isabelle; Michon, Jean; Pinkerton, Ross; Coze, Carole; Stephan, Jean Louis; Fourquet, Bernard; Valteau-Couanet, Dominique; Bergeron, Christophe; Philip, Thierry; Carrie, Christian . E-mail: carrie@lyon.fnclcc.fr

    2006-04-01

    Purpose: To determine the contribution of total body irradiation (TBI) to late sequelae in children treated with high-dose chemotherapy and autologous bone marrow transplantation for Stage IV neuroblastoma. Patients and Methods: We compared two populations that were similar with regard to age, stage, pre-autologous bone marrow transplantation chemotherapy (CT) regimen, period of treatment, and follow-up (12 years). The TBI group (n = 32) received TBI as part of the megatherapy procedure (1982-1993), whereas the CT group (n 30) received conditioning without TBI (1985-1992). Analysis 12 years later focused on growth, weight and corpulence (body mass index) delay; hormonal deficiencies; liver, kidney, heart, ear, eye, and dental sequelae; school performance; and the incidence of secondary tumors. Results: Impact of TBI was most marked in relation to growth and weight delay, although the mean delay was not severe, probably because of treatment with growth hormones. Other consequences of TBI were thyroid insufficiency, cataracts, and a high incidence of secondary tumors. Hearing loss and dental agenesis were more prominent in the group treated with CT alone. No differences were observed in school performance. Conclusion: The most frequent side effects of TBI were cataracts, thyroid insufficiency, and growth delay, but more worrying is the risk of secondary tumors. Because of the young mean age of patients and the toxicity of TBI regimens without any survival advantage, regimens without TBI are preferable in the management of Stage IV neuroblastoma.

  13. Solaire Durance | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Solaire Durance Place: France Sector: Solar Product: Joint venture between French state bank la Caisse des Dpots and French solar power...

  14. Comparative Study on Exhaust Emissions from Diesel- and CNG-Powered...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Buses 2003 DEER Conference Presentations: French Agency of Environment and Energy ... Transient Heavy-Duty Chassis Dynamometer French perspective on diesel engines & emissions

  15. PROCESS FOR PREPARING RARE EARTH CHROMITE BASED CERAMIC MATERIALS...

    Office of Scientific and Technical Information (OSTI)

    MATERIALS AND THE MATERIALS OBTAINED. (in French) Authors: Elston, J. ; Roux, M. ... Country of Publication: France Language: French Subject: N30220* --Metals, Ceramics, & ...

  16. Scientific Societies, E-print Network -- Energy, science, and...

    Office of Scientific and Technical Information (OSTI)

    Chinese Dutch English French German Italian Japanese Nordic Russian SpanishPortuguese ... All Languages English Japanese Chinese Nordic Dutch Russian French Spanish-Portuguese ...

  17. EM's Richland Operations Office Completes Chromium Cleanup along...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Columbia River," said Mark French, the federal project director for the river corridor. ... the source term will greatly reduce life-cycle groundwater treatment costs," French said. ...

  18. Performance and durability of PSA Peugeot Citroen's DPF System on a Taxi Fleet in the Paris Area

    Broader source: Energy.gov [DOE]

    2003 DEER Conference Presentation: Aaqius & Aaqius, French Agency of Environment and Energy Management

  19. Development and characterization of PCDTBT:CdSe QDs hybrid solar cell

    SciTech Connect (OSTI)

    Dixit, Shiv Kumar Bhatnagar, Chhavi Kumari, Anita Madhwal, Devinder Bhatnagar, P. K. Mathur, P. C.

    2014-10-15

    Solar cell consisting of low band gap polymer poly[N-900-hepta-decanyl-2,7-carbazole-alt-5,5-(40,70-di-2-thienyl-20,10, 30-benzothiadiazole)] (PCDTBT) as donor and cadmium selenide/zinc sulphide (CdSe/ZnS) core shell quantum dots (QDs) as an acceptor has been developed. The absorption measurements show that the absorption coefficient increases in bulk heterojunction (BHJ) structure covering broad absorption spectrum (200nm–700nm). Also, the photoluminescence (PL) of the PCDTBT:QDs film is found to decrease by an order of magnitude showing a significant transfer of electrons to the QDs. With this approach and under broadband white light with an irradiance of 8.19 mW/cm{sup 2}, we have been able to achieve a power conversion efficiency (PCE) of 3.1 % with fill factor 0.42 for our typical solar cell.

  20. Wahid Bhimji

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    
 Wahid Bhimji (wbhimji@lbl.gov)
 
 https://www.nersc.gov/users/ data-analytics/data- management/
 Databases --- 1 --- Systems Services Tools Capabilities Transfer Processing Storage/ Management Analytics/ Visualisation NERSC Data and Analytics Stack Burst Buffer Parallel Filesystem Interactive Nodes Compute Nodes GridFtp NEWT Visit/ Paraview Globus HDF5/ NetCDF python/ R/ ROOT Fireworks/ Swift SciDB/MongoDB Postgres/MySQL BDAS/ SPARK OMERO/ Fiji/Matlab Access Database Servers Global FS

  1. ARM - Facility News Article

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    February 20, 2009 [Facility News] U.S. Ambassador Tours Nauru Site Bookmark and Share U.S. Ambassador Steven McGann stops for a photo during his visit to Nauru Island in February. U.S. Ambassador Steven McGann stops for a photo during his visit to Nauru Island in February. On February 7, 2009, the U.S.Ambassador to Fiji (as well as Nauru and other island nations) Steven McGann visited the ARM Climate Research Facility's Nauru site. He and Ms. Megan Kennett of the embassy arrived with Nauruan

  2. Livingston Parish, Louisiana: Energy Resources | Open Energy...

    Open Energy Info (EERE)

    Louisiana French Settlement, Louisiana Killian, Louisiana Livingston, Louisiana Port Vincent, Louisiana Springfield, Louisiana Walker, Louisiana Retrieved from "http:...

  3. COMPARATIVE STUDY ON EXHAUST EMISSIONS FROM DIESEL- AND CNG-POWERED...

    Office of Scientific and Technical Information (OSTI)

    ... Research Org: French Agency of Environment and Energy Management, Air & Transport Division ... SPAN; LUBRICANTS; MODIFICATIONS; NOISE POLLUTION; POLLUTANTS; RELIABILITY; TRANSPORT; ...

  4. U.S. Department Of Energy Commends Industry Consortia for Making...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... French electric utility; Entergy Nuclear, Jackson, Mississippi; Exelon Generation, Philadelphia, Pennsylvania; Florida Power & Light Company, Juno Beach, Florida; Progress Energy, ...

  5. Comparison of JSFR design with EDF requirements for future SFR

    SciTech Connect (OSTI)

    Uematsu, M. M.; Prele, G.; Mariteau, P.; Sauvage, J. F.; Hayafune, H.; Chikazawa, Y.

    2012-07-01

    A comparison of Japan sodium-cooled fast reactor (JSFR) design with future French SFR concept has been done based on the requirement of EDF, the investor-operator of future French SFR, and the French safety baseline, under the framework of EDF-JAEA bilateral agreement of research and development cooperation on future SFR. (authors)

  6. Monitoring and Assessment of Greenhouse Gas Emissions and Mitigation...

    Open Energy Info (EERE)

    Technical report Website http:www.fao.orgclimatechan References MICCA Website (English)1 MICCA Website (French)2 MICCA Website (Spanish)3 The main goal of this...

  7. UNECE-Annual Bulletin of Transport Statistics for Europe and...

    Open Energy Info (EERE)

    Data covers Europe, Canada and the United States. This is a trilingual publication in English, French and Russian." "This annual publication presents statistics and brief studies...

  8. file://L:\\DOE-hanford.gov\\public\\boards\\hab\\advice\\advice110...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fitzsimmons, Washington Department of Ecology Dick French, Office of River Protection Wade Ballard, Deputy Designated Federal Official The Oregon and Washington Congressional...

  9. Intel Bug Reports

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    4 C++11 header files appear missing on Edison December 3, 2014 by Scott French, NERSC USG Status: Reported to Cray (801693), Workaround available

  10. TRUTeamWorks 06-24-04

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Visitors included CEA Chairman Alain Bugat, French Embassy Nuclear Counselor Regis ... been selected on six contracts in the Intelligence, Defense, and Homeland Security arenas. ...

  11. Microsoft Word - CFN ref. IO-14-CFT-9560-ACS CP3 CFN Technical...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    - French Order 2005 December 12 th for nuclear pressurised equipment (ESPN) 5 Directive 200642EC of the European Parliament and of the Council of 17 May 2006 on...

  12. Velcan Energy India Ltd | Open Energy Information

    Open Energy Info (EERE)

    Energy India Ltd Jump to: navigation, search Name: Velcan Energy India Ltd. Place: Bangalore, Karnataka, India Zip: 560 024 Sector: Biomass Product: Indian subsidiary of French...

  13. PGI Bug Reports

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    June 2015 Internal compiler error for function pointer with identically named arguments June 9, 2015 by Scott French, NERSC USG Status: Bug 21435 reported to PGI

  14. CT Scan of Earth Links Mantle Plumes with Volcanic Hotspots

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NERSC PI: Barbara Romanowicz Lead Institution: University of California, Berkeley Project ... Image: Scott French, Lawrence Berkeley National Laboratory University of California, ...

  15. Performance of an LPD prototype detector at MHz frame rates under...

    Office of Scientific and Technical Information (OSTI)

    at MHz frame rates under Synchrotron and FEL radiation Authors: Koch, Andreas ; Hart, Matthew ; Nicholls, Tim ; Angelsen, Christian ; Coughlan, John ; French, Marcus ;...

  16. Participants

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Richard Gerber. Back row, from left: Scott French, Jeff Neaton, Sudip Dosanjh, Harvey Wasserman, Jim Davenport, David ... NERSC Program Manager James W. Davenport DOE BES Program ...

  17. CRiSTAL Project Management Tool | Open Energy Information

    Open Energy Info (EERE)

    modeling tools User Interface: Spreadsheet Website: www.iisd.orgcristaltool Cost: Free Language: "English, French, Portuguese, Spanish; Castilian" is not in the list of...

  18. FUSION OF HOMOATOMIC SOLIDS. (Journal Article) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: Country unknownCode not available Language: French Subject: N20230* --Chemistry--Inorganic, Organic, & Physical Chemistry--Physical Chemistry; EQUATIONS; ...

  19. Study, design and realization of a Fabry-Perot cavity for the Compton polarimeter of TJNAF; Etude, conception et realisation d'une cavite Fabry-Perot pour le polarimetre Compton de TJNAF

    SciTech Connect (OSTI)

    Falletto, M. Nicolas

    2001-01-01

    This is a doctoral dissertation, in French, on the subject of study, design and realization of a Fabry-Perot cavity for the Compton polarimeter of TJNAF.

  20. Intel C++ compiler error: stl_iterator_base_types.h

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    C++ compiler error: stliteratorbasetypes.h Intel C++ compiler error: stliteratorbasetypes.h December 7, 2015 by Scott French Because the system-supplied version of GCC is...

  1. PGI Bug Reports

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    PGI PGI Bug Reports PGI Bug Reports Internal compiler error for function pointer with identically named arguments June 9, 2015 by Scott French, NERSC USG Status: Bug 21435...

  2. Solactiva | Open Energy Information

    Open Energy Info (EERE)

    Solactiva Jump to: navigation, search Name: Solactiva Place: Rosny-sous-Bois, France Zip: 93110 Sector: Solar Product: A French company offering turnkey installation of solar...

  3. Pierre Michel | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postdoctoral Appointee Pierre Michel received his Ph.D. from the University of Orleans, France in 2015, in collaboration with the French carmaker PSA. His doctoral work focused...

  4. Solems SA | Open Energy Information

    Open Energy Info (EERE)

    Solems SA Jump to: navigation, search Name: Solems SA Place: Palaiseau, France Zip: 91124 Product: French manufacturer of amorphous thin-film modules on glass substrate....

  5. Voltec Solar | Open Energy Information

    Open Energy Info (EERE)

    Solar Jump to: navigation, search Name: Voltec-Solar Place: Dinsheim Sur Bruche, France Zip: 67190 Product: French manufacturer of crystalline silicon modules. References:...

  6. Sinatis Europe | Open Energy Information

    Open Energy Info (EERE)

    Sinatis Europe Jump to: navigation, search Name: Sinatis Europe Place: France Product: French project developer and distributor with customers across France and North Africa....

  7. Voltalia | Open Energy Information

    Open Energy Info (EERE)

    Voltalia Jump to: navigation, search Name: Voltalia Place: Neuilly-sur-Seine, France Zip: 92200 Sector: Renewable Energy Product: French developer and operator of renewable power...

  8. Conexia Energy | Open Energy Information

    Open Energy Info (EERE)

    Conexia Energy Jump to: navigation, search Name: Conexia Energy Place: Aix-en-Provence, France Zip: 13857 Sector: Renewable Energy Product: French renewable energy consulting and...

  9. La Francaise dEoliennes | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: La Francaise dEoliennes Place: Maisons Laffitte, France Zip: 78600 Sector: Wind energy Product: French wind farm developer focused on...

  10. AuantumSolar | Open Energy Information

    Open Energy Info (EERE)

    AuantumSolar Jump to: navigation, search Name: AuantumSolar Place: Montpellier, France Zip: 34695 Product: French developer of inorganic dye-based PV cells References:...

  11. Strategeco Solar aka Eneovia | Open Energy Information

    Open Energy Info (EERE)

    to: navigation, search Name: Strategeco Solar (aka Eneovia) Place: Joinville-le-Pont, France Zip: 94340 Product: French PV project developer of medium to large scale projects....

  12. Photon Power Technologies PPT | Open Energy Information

    Open Energy Info (EERE)

    PPT Jump to: navigation, search Name: Photon Power Technologies (PPT) Place: Ecully, France Product: French PV system installer for residential and commercial systems. Coordinates:...

  13. Hiolle Energies | Open Energy Information

    Open Energy Info (EERE)

    Hiolle Energies Jump to: navigation, search Name: Hiolle Energies Place: France Product: French PV system integrator. References: Hiolle Energies1 This article is a stub. You can...

  14. Photowatt Technologies aka Photowatt International SA | Open...

    Open Energy Info (EERE)

    Name: Photowatt Technologies (aka Photowatt International SA) Place: Bourgoin-Jallieu, France Zip: 38300 Product: French manufacturer of integrated PV products from ingots to...

  15. Frey Nouvelles Energies | Open Energy Information

    Open Energy Info (EERE)

    Energies Jump to: navigation, search Name: Frey Nouvelles Energies Place: Cormontreuil, France Zip: 51350 Sector: Renewable Energy Product: French project developer for all...

  16. Emix | Open Energy Information

    Open Energy Info (EERE)

    Emix Jump to: navigation, search Name: Emix Place: St Maurice La Souterraine, France Zip: 23300 Product: French manufacturer of multicrystalline ingots and wafers. References:...

  17. REFRACTORY MATERIALS IN ATOMIC PILES. (Journal Article) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Research Org: Originating Research Org. not identified Country of Publication: Country unknownCode not available Language: French Subject: N30250* --Metals, Ceramics, & Other ...

  18. Total Crude Oil and Products Imports from All Countries

    U.S. Energy Information Administration (EIA) Indexed Site

    Costa Rica Croatia Curacao Cyprus Czech Republic Denmark Dominican Republic Egypt El Salvador Equatorial Guinea Estonia Finland France French Guiana Gabon Georgia, Republic ...

  19. U.S. Imports from All Countries

    U.S. Energy Information Administration (EIA) Indexed Site

    Costa Rica Croatia Curacao Cyprus Czech Republic Denmark Dominican Republic Egypt El Salvador Equatorial Guinea Estonia Finland France French Guiana Gabon Georgia, Republic ...

  20. NERSC Hosts Application Readiness and Portability Meeting with...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Antypas, NERSC; Ashley Barker, OLCF; Matt Cordery, NERSC; Jack Deslippe, NERSC; Carter Edwards, SNL; Hal Finkel, ALCF; Fernanda Foertter, OLCF; Scott French, NERSC; Scott Futral,...

  1. Orange County, Indiana: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Climate Zone Number 4 Climate Zone Subtype A. Places in Orange County, Indiana French Lick, Indiana Orleans, Indiana Paoli, Indiana West Baden Springs, Indiana Retrieved...

  2. EDF Energies Nouvelles Portugal formerly SIIF Energies Portugal...

    Open Energy Info (EERE)

    Sector: Renewable Energy Product: Renewable energy project developer, subsidiary of French EDF Energies Nouvelles (formerly SIIF Energies). Coordinates: 38.725735, -9.15021...

  3. 157 nm Pellicles (Thin Films) for Photolithography: Mechanistic...

    Office of Scientific and Technical Information (OSTI)

    of model compounds. Authors: Lee, Kwangjoo ; Jockusch, Steffen ; Turro, Nicholas J. ; French, Roger H. ; Wheland, Robert C. ; Lemon, M F. ; Braun, Andre M. ; Widerschpan, Tatjana...

  4. La Crosse County, Wisconsin: Energy Resources | Open Energy Informatio...

    Open Energy Info (EERE)

    INOV8 International Inc Energy Generation Facilities in La Crosse County, Wisconsin French Island Biomass Facility Places in La Crosse County, Wisconsin Bangor, Wisconsin Barre,...

  5. Chautauqua County, New York: Energy Resources | Open Energy Informatio...

    Open Energy Info (EERE)

    York Ellington, New York Falconer, New York Forestville, New York Fredonia, New York French Creek, New York Frewsburg, New York Gerry, New York Hanover, New York Harmony, New...

  6. Energeo sro | Open Energy Information

    Open Energy Info (EERE)

    Energeo sro Place: Prague 3, Czech Republic Zip: 130 00 Sector: Solar Product: Czech - French company developing solar PV projects in the Czech Republic. References: Energeo sro1...

  7. Choctaw County, Mississippi: Energy Resources | Open Energy Informatio...

    Open Energy Info (EERE)

    3 Climate Zone Subtype A. Places in Choctaw County, Mississippi Ackerman, Mississippi French Camp, Mississippi Mathiston, Mississippi Weir, Mississippi Retrieved from "http:...

  8. Extrapolating Accelerated UV Weathering Data: Perspective from...

    Office of Scientific and Technical Information (OSTI)

    Amal ; Bokria, Jayesh G. ; Bruckman, Laura S. ; Burns, David M. ; Elliott, Lamont ; French, Roger H. ; Fowler, Sean ; Gu, Xiaohong ; Honeker, Christian C. ; Kempe, Michael D. ;...

  9. Degradation in PV Encapsulation Transmittance: An Interlaboratory...

    Office of Scientific and Technical Information (OSTI)

    Fanny ; Ballion, Amal ; Kohl, Michael ; Bokria, Jayesh G. ; Bruckman, Laura S. ; French, Roger H. ; Burns, David ; Phillips, Nancy H. ; Feng ; Jiangtao ; Elliott, Lamont ;...

  10. Voltalia Brasil | Open Energy Information

    Open Energy Info (EERE)

    20011-030 Sector: Carbon, Renewable Energy Product: Brazilian-based subsidiary of the French company Voltalia. Project developer company in renewable energy projects and carbon...

  11. REFRACTORY MATERIALS IN THE NUCLEAR INDUSTRY (Journal Article...

    Office of Scientific and Technical Information (OSTI)

    REFRACTORY MATERIALS IN THE NUCLEAR INDUSTRY Citation Details In-Document Search Title: REFRACTORY MATERIALS IN THE NUCLEAR INDUSTRY (in French) In reactors operating at high ...

  12. Aerowatt Energies | Open Energy Information

    Open Energy Info (EERE)

    Name: Aerowatt Energies Place: France Sector: Solar, Wind energy Product: France-based joint venture established to develop wind and solar projects in French territories....

  13. Plexus Sol | Open Energy Information

    Open Energy Info (EERE)

    Plexus Sol Jump to: navigation, search Name: Plexus Sol Place: Reunion Island, France Product: PV project developer in Reunion Island, 95% acquired by French Sechilienne-Sidec in...

  14. Events leading to the Manhattan Project

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to understand the nature of atoms. French physicist Pierre Curie and his Polish wife Marie in 1898 demonstrated that the uranium ore pitchblende emitted radioactivity that they...

  15. EnergyFiles | OSTI, US Dept of Energy, Office of Scientific and...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    such as energy, medicine, agriculture, environment, and basic sciences. Multilingual translation capabilities are available for ten languages: Arabic, Chinese, English, French,...

  16. OSTI, US Dept of Energy, Office of Scientific and Technical Informatio...

    Office of Scientific and Technical Information (OSTI)

    with millions of books, recordings, photographs, maps and manuscriptsin its collections. ... of seven languages: English, Chinese, French, Russian, Spanish, Portuguese, and Arabic. ...

  17. NEAR FIELD MODELING OF SPE1 EXPERIMENT AND PREDICTION OF THE...

    Office of Scientific and Technical Information (OSTI)

    AND PREDICTION OF THE SECOND SOURCE PHYSICS EXPERIMENTS ... as Russian and French nuclear test data in granitic rocks. ... Country of Publication: United States Language: English ...

  18. Performance and durability of PSA Peugeot Citroen's DPF System...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Performance and durability of PSA Peugeot Citroen's DPF System on a Taxi Fleet in the Paris Area 2003 DEER Conference Presentation: Aaqius & Aaqius, French Agency of Environment ...

  19. Review of SCR Technologies for Diesel Emission Control: Euruopean...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    More Documents & Publications A New Active DPF System for "Stop and Go" Duty-Cycle Vehicles French perspective on diesel engines & emissions Potential Effect of Pollutantn ...

  20. Hydrogen Liquefaction

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    4-7 European Installations 4-6 Japanese Installations India Program ESA French Guiana (South America) 4 Satisfies ASME J-2719 (hydrogen fuel quality) ...

  1. Microsoft PowerPoint - NEAC Rpt of Fuel Cycle comm slides

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Swedes and Finns know about granite, the the Swedes and Finns know about granite, the French know about clay * Recommendation - do a comprehensive Recommendation do a ...

  2. Voltalia Guyane | Open Energy Information

    Open Energy Info (EERE)

    Guyana Sector: Renewable Energy Product: French developer and operator of renewable plants References: Voltalia Guyane1 This article is a stub. You can help OpenEI by...

  3. Kent Hibben | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Kent graduated from the University of Maryland, Baltimore County with Bachelor of Arts degrees in Economics, French, German, and Linguistics, and a minor in Political Science

  4. C:\\Forms\\DOE F 3305.13.cdr

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EXAMPLE PERSONAL HISTORY PROF. ACTIVITIES AND SPECIAL QUALIFICATIONS PRIVATE INDUSTRY JOB ... Foreign Languages: French and German (Fluent in reading, writing and conversing) 1987 ...

  5. Nature Energie | Open Energy Information

    Open Energy Info (EERE)

    Nature Energie Jump to: navigation, search Name: Nature Energie Place: France Sector: Solar, Wind energy Product: French developer of wind and solar energy projects. References:...

  6. R2D Ingenierie SAS | Open Energy Information

    Open Energy Info (EERE)

    search Name: R2D Ingenierie SAS Place: Montpellier, France Product: French automation equipment manufacturer for PV cells and semiconductor chips. Coordinates:...

  7. Browse Societies by Language -- E-print Network Societies by...

    Office of Scientific and Technical Information (OSTI)

    If you wish to view societies in another language, please select from the following options. Chinese Dutch English French German Italian Japanese Nordic Spanish and Portuguese ...

  8. United States and France Sign Joint Statement on Civil Liability...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    the Joint Statement by U.S. Secretary of Energy, Ernest Moniz, and French Minister of Ecology, Sustainable Development, and Energy, Philippe Martin. "The signing of this joint ...

  9. Kent Hibben | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    A native German speaker, he attended preparatory school in Germany. He graduated in 1987 with Bachelor Degrees in Economics, French, German, and Linguistics, and a minor in ...

  10. Carbon Dioxide, Hydrographic, and Chemical Data Obtained During the R/V Thomas G. Thompson Cruise in the Pacific Ocean

    SciTech Connect (OSTI)

    Sabine, C.L.; Key, R.M.; Hall, M.; Kozyr, A.

    1999-08-01

    This data documentation discusses the procedures and methods used to measure total carbon dioxide (TCO2), total alkalinity (TALK), and radiocarbon (delta 14C), at hydrographic stations, as well as the underway partial pressure of CO2 (pCO2) during the R/V Thomas G. Thompson oceanographic cruise in the Pacific Ocean (Section P10). Conducted as part of the World Ocean Circulation Experiment (WOCE), the cruise began in Suva, Fiji, on October 5, 1993, and ended in Yokohama, Japan, on November 10, 1993. Measurements made along WOCE Section P10 included pressure, temperature, salinity [measured by conductivity temperature, and depth sensor (CTD)], bottle salinity, bottle oxygen, phosphate, nitrate, silicate, chlorofluorocarbons (CFC-11, CFC-12), TCO2, TALK, delta 14C, and underway pCO2.

  11. CX-006866: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    American Recovery and Reinvestment Act Energy Efficiency Conservation Block Grant - State of Louisiana - Livingston Parish (French Settlement)CX(s) Applied: B5.1Date: 09/23/2011Location(s): French Settlement, LouisianaOffice(s): Energy Efficiency and Renewable Energy, Golden Field Office

  12. Museum Hours

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    provide a listening-assistance system and translations of the script in French and Spanish. Sorry, a local shop has closed The Otowi Bookstore and Museum Shop, which had been...

  13. CRYSTAL STRUCTURE OF OXIDES AND THEIR NEUTRON IRRADIATION BEHAVIOR...

    Office of Scientific and Technical Information (OSTI)

    NEUTRON IRRADIATION BEHAVIOR AT 80 DEG C Citation Details In-Document Search Title: CRYSTAL STRUCTURE OF OXIDES AND THEIR NEUTRON IRRADIATION BEHAVIOR AT 80 DEG C (in French) ...

  14. 2011??????????

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    U.S. ESCO industry is comparable and probably larger than French and German industry; Chinese ESCO industry is growing rapidly and may soon surpass U.S. ESCO industry size *...

  15. Department of Energy to Take Steps to Remove ENERGY STAR Label...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    As a result, effective January 2, 2010, certain LG French-door refrigerators are no longer eligible to carry the ENERGY STAR label. ENERGY STAR is a voluntary program sponsored ...

  16. Support for ENERGY STAR Enforcement | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    (LG) that modifies a prior agreement under which LG had been making annual payments to consumers who had purchased certain models of LG and Kenmore-brand French Door refrigerators. ...

  17. Glenn Seaborg Trail | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Trees in this small forest, therefore, span the years from the French and Indian War, ... Some areas of the forest were farm land just 45 years ago, when the AEC purchased the land ...

  18. NNMCAB Board Minutes: May 2010 Ohkay Owingeh

    Broader source: Energy.gov [DOE]

    Minutes of the May 13, 2010 Board meeting at Ohkay Conference Center Presentation DOE/LANS, Disposal Authority Statement and Performance Assessment and Composite Analyses, George Henkel, Sean French

  19. Slide15 | OSTI, US Dept of Energy, Office of Scientific and Technical

    Office of Scientific and Technical Information (OSTI)

    Information Multilingual Translations Translating ten languages, with potential for more Arabic Chinese German Deutsch English Spanish Español French Français Japanese Korean Portuguese Português Russian

  20. Solareo | Open Energy Information

    Open Energy Info (EERE)

    Solareo Jump to: navigation, search Name: Solareo Place: Le Chesnay, France Zip: 78150 Product: French project developer who is developing a 400kW roof mounted project in the heart...

  1. ProLogis France IX EURL | Open Energy Information

    Open Energy Info (EERE)

    ProLogis France IX EURL Jump to: navigation, search Name: ProLogis France IX EURL Place: Aulnay-Sous-Bois Cedex, France Zip: 93614 Product: French subsidiary of ProLogis, a...

  2. SolSia | Open Energy Information

    Open Energy Info (EERE)

    SolSia Jump to: navigation, search Name: SolSia Place: France Product: A start-up manufacturer of thin-film silicon modules for the French market. References: SolSia1 This...

  3. Property:Address | Open Energy Information

    Open Energy Info (EERE)

    Inc + 2130 Van Horn Rd. + AC Solar Inc + P.O. Box 128 + ACME solar works + 20738 Brown Lane + ACORE + PO Box 33518 + ADI Wind, llc. + 4686 French Creek Road + AEE Solar +...

  4. Distributed Bio-Oil Reforming

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Distributed Bio-Oil Reforming R. Evans, S. Czernik, R. French, M. Ratcliff National ... GAS 7 BIOMASS BIO-OIL CHAR For reactor or export Gas recycle For fluidization or export ...

  5. 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    old) that are distinctly light in color, which were analyzed by the ChemCam instrument.French and U.S. scientists observed images and chemical - 2 - results of 22 of these rock...

  6. MHK Projects/CETO La Reunion | Open Energy Information

    Open Energy Info (EERE)

    of the single, stand-alone unit due in Q2 2012. Stage 1 has been awarded 5M of French Government funding. Project Installed Capacity (MW) 0 Number of Devices Deployed 1...

  7. Graded Interface Models for more accurate Determination of van...

    Office of Scientific and Technical Information (OSTI)

    length scale property variations. Authors: van Benthem, Klaus 1 ; Tan, Guolong 2 ; French, Roger H 3 ; DeNoyer, Linda K 4 ; Podgornik, Rudolf 5 ; Parsegian, V Adrian 5...

  8. ARM - Niamey News

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sheets RADAGAST (PDF) Annual Climate Cycle in Niger, Africa (PDF) Posters AMF Poster, French Version We're Going to Sample the Sky in Africa News Campaign Images AMMA...

  9. Applicability of 10 CFR 851 to Parsons ATC and Barnwell Activities

    Broader source: Energy.gov [DOE]

    Letter from Bruce Diamond, Assistant General Counsel for Environment, Department of Energy, dated June 27, 2007 to Bob French, Program Manager, Parsons SB-1 Office regarding Parsons' Request for Interpretive Ruling Under 10 CFR Section 851.7

  10. Applicability of 10 CFR 851 to Parsons non-DOE Office Areas at SRS

    Broader source: Energy.gov [DOE]

    Letter from Bruce Diamond, Assistant General Counsel for Environment, DOE, dated June 27, 2007, to Bob French, Program Manager, Parsons SB-1 Office regarding Parsons' Request for Interpretative Ruling Under 10 CFR Section 851.7

  11. 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Space scientist tapped for French knighthood April 11, 2016 ChemCam leader honored for touching the lives of "ambitious earthlings" LOS ALAMOS, N.M., April 11, 2016-Space scientist ...

  12. RENOTER Project

    Broader source: Energy.gov [DOE]

    Overview of French project on thermoelectric waste heat recovery for cars and trucks with focus on cheap, available, efficient, and sustainable TE materials, as well as efficient material integration and production process.

  13. Categorical Exclusion Determinations: Massachusetts | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    December 3, 2015 CX-100413 Categorical Exclusion Determination The French Modular Impoundment Award Number: DE-FOA-0007244 CX(s) Applied: A9, B3.6 Wind and Water Power Technologies ...

  14. CX-005903: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    State Energy Program American Recovery and Reinvestment Act - French Creek BioenergyCX(s) Applied: B5.1Date: 05/17/2011Location(s): Sheffield, OhioOffice(s): Energy Efficiency and Renewable Energy, Golden Field Office

  15. CX-012171: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    735-11A French Drain Piping Installation CX(s) Applied: B1.3 Date: 04/16/2014 Location(s): South Carolina Offices(s): Savannah River Operations Office

  16. DOE Zero Ready Home Case Study: TC Legend Homes, Cedarwood, Bellingham...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Exhaust fans in the utility area and kitchen provide additional spot ventilation. The home's upstairs windows with two south-facing sliding doors, and south-facing French doors ...

  17. Solar Euromed | Open Energy Information

    Open Energy Info (EERE)

    France Sector: Solar Product: Solar Euromed is a French project developer for STEG plants. References: Solar Euromed1 This article is a stub. You can help OpenEI by expanding...

  18. 2007 - 03 | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    3 Mar 2007 Fri, 2007-03-16 00:00 Jeff Lab director plans retirement (Daily Press) Thu, 2007-03-01 00:00 French Ambassador Pierre Vimont tours JLab (Daily Press)

  19. JLab, Physics Community Mourns Death of Jean Mougey, First Hall...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lab, and a director of the Nuclear Physics Division at CEA Saclay, passed away from a heart attack on Nov. 5, 2015, in Grenoble. Jean was born in the French town of Angers, by...

  20. Zirconium and hafnium separation at Y-12

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the sea by French author Jules Verne. Of course there was then a movie made by Walt Disney in 1954 named 20,000 leagues under the sea that used the same Nautilus sub- marine...

  1. Scientific Societies, E-print Network -- Energy, science, and...

    Office of Scientific and Technical Information (OSTI)

    Chinese Dutch English French German Italian Japanese Nordic Russian SpanishPortuguese Other View list of all societies. Choose desired language(s) andor discipline(s) and select ...

  2. Christina Martos Hilton

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hilton already had performed in Russian, Latin, Czech and Hebrew, and she studied Italian for nearly two hours every morning, with quite a bit of French and German sprinkled...

  3. Summary of the Fall Meeting of the

    U.S. Energy Information Administration (EIA) Indexed Site

    Summary of the Fall Meeting of the American Statistical Association (ASA) Committee on Energy Statistics October 24-25, 2002 .................with the Energy Information Administration 1. Update on the Commercial Buildings Energy Consumption Survey (CBECS), by Dwight French, Office of Energy Markets and End Use, EIA At the Spring, 2002 Committee meeting Dwight French gave a presentation on three major methodological issues being studied in the post-2000 redesign of EIA's Commercial Buildings

  4. file://L:\DOE-hanford.gov\public\boards\hab\advice\advice99.htm

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Tom Fitzsimmons, Director Washington Department of Ecology P.O. Box 47600 Olympia, WA 98504-7600 Dick French, Manager Office of River Protection 2440 Stevens Center Richland, WA 99352 Subject: Tri-Party Response to HAB Advice Dear Messrs. Fitzsimmons and French: The Hanford Advisory Board (HAB) continues to be disappointed in the agencies' response to HAB advice (#90 and #93) that urged the speedy development of Tri-Party Agreement (TPA) milestones governing tank waste treatment. The Board took

  5. Mineral industries of Australia, Canada, and Oceania (including a discussion of Antarctica's mineral resources). Mineral perspective

    SciTech Connect (OSTI)

    Kimbell, C.L.; Lyday, T.Q.; Newman, H.H.

    1985-12-01

    The Bureau of Mines report gives the mineral industry highlights of two of the world's major mineral producing countries, Australia and Canada, and seven Pacific island nations or territories--Fiji, New Caledonia, New Zealand, Papua New Guinea, Republic of Nauru, Solomon Islands, and Vanuatu. The mineral resources of Antarctica are also discussed. Because of the size of the Australian and Canadian mineral industries, summary reviews are presented for each of the States, Provinces, or Territories. The most current information available from all nations is given on major minerals or mineral-commodity production, share of world production, and reserves. Reported also are significant mining companies, locations and capacities of their main facilities, and their share of domestic production. Other information is provided on mineral-related trade with the United States, government mineral policy, energy production-consumption and trade, the mining industry labor force, and prospects for the mineral industry. Maps show the locations of selected mineral deposits, oilfields and gasfields, mines, and processing facilities including iron and steel plants, nonferrous smelters and refineries, and cement plants, as well as infrastructure pertinent to the mineral industry.

  6. Evidence for the existence of a fourth dominantly inherited spinocerebellar ataxia locus

    SciTech Connect (OSTI)

    Lopes-Cendes, I. Montreal Neurological Institute and Hospital, Quebec McGill Univ., Quebec ); Andermann, E. McGill Univ., Quebec ); Rouleau, G.A. Montreal Neurological Institute and Hospital, Quebec )

    1994-05-01

    The autosomal dominantly inherited spinocerebellar ataxias (SCAs) are a heterogeneous group of disorders. To date, three loci have been identified: The SCA1 locus (on chr 6p), the SCA2 locus (on chr 12q), and more recently a Machado-Joseph disease (MJD) locus (on chr 14q). The authors have studied one large French-Canadian kindred with four generations of living affected individuals segregating an autosomal dominant form of SCA. Linkage analysis using anonymous DNA markers that flank the three previously described loci significantly exclude the French-Canadian kindred from the SCA1, SCA2, and MJD loci. Therefore, a fourth, still unmapped SCA locus remains to be identified. In addition, the unique clinical phenotype present in all affected individuals of the French-Canadian kindred might be characteristic of this still unmapped SCA locus. 34 refs., 2 figs., 2 tabs.

  7. 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Space scientist tapped for French knighthood April 11, 2016 ChemCam leader honored for touching the lives of "ambitious earthlings" LOS ALAMOS, N.M., April 11, 2016-Space scientist Roger Wiens was awarded the honorary title of chevalier (knight) in France's Academic Order of Palms for his work in forging strong ties between the French and American scientific communities. Wiens is the principal investigator of the ChemCam, a laser spectroscopy instrument on NASA's Mars Curiosity rover

  8. SR0910.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Monday, June 22, 2009 james-r.giusti@srs.gov Angeline French, (SRNL), (803) 725-2854 angeline.french@srnl.doe.gov Dean Campbell, WSRC, (803) 208-8270 dean.campbell@srs.gov DOE'S SRNL AND DWPF HONORED BY WHITE HOUSE FOR ENVIRONMENTAL ACHIEVEMENT AIKEN, S.C. (June 17, 2009) - The U.S. Department of Energy's Savannah River National Laboratory (SRNL) and its Defense Waste Processing Facility (DWPF) at the Savannah River Site were honored by the White House for an innovative environmental initiative

  9. DOE Community Transition Contacts | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    About Us » Contact Us » DOE Community Transition Contacts DOE Community Transition Contacts Headquarters David Geiser, Director Office of Legacy Management, LM-1 U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 (202) 586-8324 (202) 586-8403 (FAX) david.geiser@hq.doe.gov Field HANFORD Colleen French U.S. Department of Energy Richland Operations Office P.O. Box 550 A7-75 Richland, WA 99352 (509) 373-5985 (509) 373-1563 (FAX) colleen_c_french@rl.gov IDAHO NATIONAL

  10. TPA PM List by TSD as of 09-30-15.xlsx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    TREATMENT, STORAGE AND DISPOSAL UNITS PROJECT MANAGERS LIST AS OF SEPTEMBER 30, 2015 Prepared By MSA TPA Site Wide Integration TSD NO. Description Ecology PM DOE PM Assistant Manager Status Lead Regulatory Agency D-1-2 1301-N Liquid Waste Disposal Facility Menard, N. French, M.S. Corey, R. J. Final Ecology Lead D-1-2 1325-N Liquid Waste Disposal Facility Menard, N. French, M.S. Corey, R. J. Final Ecology Lead D-2-10 216-A-37-1 Crib Menard, N. Cline, M.W. Corey, R. J. Interim Ecology Lead D-2-11

  11. TPA PM List of 09-30-15.xlsx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    OPERABLE UNITS PROJECT MANAGERS LIST AS OF SEPTEMBER 30, 2015 Prepared By MSA TPA Integration TSD NO. Description Ecology PM DOE PM Assistant Manager Status Lead Regulatory Agency D-1-2 1301-N Liquid Waste Disposal Facility Menard, N. French, M.S. Corey, R. J. Final Ecology Lead D-1-2 1325-N Liquid Waste Disposal Facility Menard, N. French, M.S. Corey, R. J. Final Ecology Lead D-2-10 216-A-37-1 Crib Menard, N. Cline, M.W. Corey, R. J. Interim Ecology Lead D-2-11 Integrated Disposal Facility

  12. 2010SR06.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    james-r.giusti@srs.gov Angeline French, SRNL, (803) 725-2854 angeline.french@srnl.doe.gov SRNL Precision Models Aid Recovery Act Cleanup at SRS AIKEN, S.C. - In a project that's part engineering, part history detective, and part high- tech craft project, the U.S. Department of Energy's (DOE) Savannah River National Laboratory (SRNL) is creating computer-produced scale replicas of the Savannah River Site's reactor buildings to support the American Recovery and Reinvestment Act project here. Use

  13. Intel Bug Reports

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Intel » Intel Bug Reports Intel Bug Reports Intel C++ compiler error: stl_iterator_base_types.h December 7, 2015 by Scott French Because the system-supplied version of GCC is relatively old (4.3.4) it is common practice to load the gcc module on our Cray systems when C++11 support is required under the Intel C++ compilers. Read the full post C++11 header files appear missing on Edison December 3, 2014 by Scott French, NERSC USG Status: Reported to Cray (801693), Workaround available Read the

  14. PowerPoint Presentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    SDLE Center, VUV-Lab, Materials Science & Engineering Department, Roger H. French © 2012 http://sdle.case.edu 4/29/13, VuGraph 1 Module level power electronics: Taking commodity components and making them last. Reliability is linked with design, but is good design linked to reliability? Tim Peshek CWRU - SDLE SDLE Center, VUV-Lab, Materials Science & Engineering Department, Roger H. French © 2012 http://sdle.case.edu 4/29/13, VuGraph 2 Intro and scope of talk *Question: Can we make a

  15. F3D Image Processing and Analysis for Many - and Multi-core Platforms

    SciTech Connect (OSTI)

    2014-10-01

    F3D is written in OpenCL, so it achieve[sic] platform-portable parallelism on modern mutli-core CPUs and many-core GPUs. The interface and mechanims to access F3D core are written in Java as a plugin for Fiji/ImageJ to deliver several key image-processing algorithms necessary to remove artifacts from micro-tomography data. The algorithms consist of data parallel aware filters that can efficiently utilizes[sic] resources and can work on out of core datasets and scale efficiently across multiple accelerators. Optimizing for data parallel filters, streaming out of core datasets, and efficient resource and memory and data managements over complex execution sequence of filters greatly expedites any scientific workflow with image processing requirements. F3D performs several different types of 3D image processing operations, such as non-linear filtering using bilateral filtering and/or median filtering and/or morphological operators (MM). F3D gray-level MM operators are one-pass constant time methods that can perform morphological transformations with a line-structuring element oriented in discrete directions. Additionally, MM operators can be applied to gray-scale images, and consist of two parts: (a) a reference shape or structuring element, which is translated over the image, and (b) a mechanism, or operation, that defines the comparisons to be performed between the image and the structuring element. This tool provides a critical component within many complex pipelines such as those for performing automated segmentation of image stacks. F3D is also called a "descendent" of Quant-CT, another software we developed in the past. These two modules are to be integrated in a next version. Further details were reported in: D.M. Ushizima, T. Perciano, H. Krishnan, B. Loring, H. Bale, D. Parkinson, and J. Sethian. Structure recognition from high-resolution images of ceramic composites. IEEE International Conference on Big Data, October 2014.

  16. Intel Bug Reports

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    5 Intel C++ compiler error: stl_iterator_base_types.h December 7, 2015 by Scott French Because the system-supplied version of GCC is relatively old (4.3.4) it is common practice to load the gcc module on our Cray systems when C++11 support is required under the Intel C++ compilers.

  17. Services du Centre de Solutions Pour Les Energies Propres (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-05-01

    This is the French translation of the Clean Energy Solutions Center services fact sheet. The Clean Energy Solutions Center (Solutions Center) helps governments, advisors and analysts create policies and programs that advance the deployment of clean energy technologies. The Solutions Center partners with international organizations to provide online training, expert assistance, and technical resources on clean energy policy.

  18. DOE/NV/11718-594

    National Nuclear Security Administration (NNSA)

    ... 231 FRENCH, N.R., C.D. JORGENSEN, M.H. SMITH, and B.G. MAZA. 1971. Comparison of Some ... E.P., T.E. HUXMAN, M.E. LOIK, and S.D. SMITH. 2000. Effects of extreme high ...

  19. CX-100413 Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    The French Modular Impoundment Award Number: DE-FOA-0007244 CX(s) Applied: A9, B3.6 Wind and Water Power Technologies Office Date: 12/03/2015 Location(s): MA Office(s): Golden Field Office

  20. CRC handbook of agricultural energy potential of developing countries. Volume I

    SciTech Connect (OSTI)

    Duke, J.A.

    1986-01-01

    The contents of this book are: Introduction, Argentina, Bangladesh, Benin, Bolivia, Botswana, Bourkina (Upper Volta), Brazil, Burma, Burundi, Cameroon, Chad, Chile, Columbia, Costa Rica, Djibouti, Dominican Republic, Ecuador, El Salvador, Ethiopia, French Guiana, Gambia, Ghana, Guatemala, Guinea, Guyana, Haiti, Honduras, India, Indonesia, Jamaica, Appendix I. Conventional and Energetic Yields, Appendix II, Phytomass Files, and References.

  1. Diesel Particulate Filters: Market Introducution in Europe | Department of

    Broader source: Energy.gov (indexed) [DOE]

    Energy 4 Diesel Engine Emissions Reduction (DEER) Conference Presentation: Aaqius and Aaqius PDF icon 2004_deer_seguelong2.pdf More Documents & Publications A New Active DPF System for "Stop and Go" Duty-Cycle Vehicles French perspective on diesel engines & emissions Diesel Particulate Filter: A Success for Faurecia Exhaust Systems

  2. Corrective Action Plan for Corrective Action Unit 562: Waste Systems, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2011-04-30

    This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 562, Waste Systems, in accordance with the Federal Facility Agreement and Consent Order (1996; as amended March 2010). CAU 562 consists of 13 Corrective Action Sites (CASs) located in Areas 2, 23, and 25 of the Nevada National Security Site. Site characterization activities were performed in 2009 and 2010, and the results are presented in Appendix A of the Corrective Action Decision Document for CAU 562. The scope of work required to implement the recommended closure alternatives is summarized. (1) CAS 02-26-11, Lead Shot, will be clean closed by removing shot. (2) CAS 02-44-02, Paint Spills and French Drain, will be clean closed by removing paint and contaminated soil. As a best management practice (BMP), asbestos tile will be removed. (3) CAS 02-59-01, Septic System, will be clean closed by removing septic tank contents. As a BMP, the septic tank will be removed. (4) CAS 02-60-01, Concrete Drain, contains no contaminants of concern (COCs) above action levels. No further action is required; however, as a BMP, the concrete drain will be removed. (5) CAS 02-60-02, French Drain, was clean closed. Corrective actions were completed during corrective action investigation activities. As a BMP, the drain grates and drain pipe will be removed. (6) CAS 02-60-03, Steam Cleaning Drain, will be clean closed by removing contaminated soil. As a BMP, the steam cleaning sump grate and outfall pipe will be removed. (7) CAS 02-60-04, French Drain, was clean closed. Corrective actions were completed during corrective action investigation activities. (8) CAS 02-60-05, French Drain, will be clean closed by removing contaminated soil. (9) CAS 02-60-06, French Drain, contains no COCs above action levels. No further action is required. (10) CAS 02-60-07, French Drain, requires no further action. The french drain identified in historical documentation was not located during corrective action investigation activities. (11) CAS 23-60-01, Mud Trap Drain and Outfall, will be clean closed by removing sediment from the mud trap. As a BMP, the mud trap and outfall pipe will be removed. (12) CAS 23-99-06, Grease Trap, will be clean closed by removing sediment from the grease trap and backfilling the grease trap with grout. (13) CAS 25-60-04, Building 3123 Outfalls, will be clean closed by removing contaminated soil and the sludge-containing outfall pipe.

  3. Corrective Action Investigation Plan for Corrective Action Unit 562: Waste Systems Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2009-04-01

    Corrective Action Unit 562 is located in Areas 2, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 562 is comprised of the 13 corrective action sites (CASs) listed below: 02-26-11, Lead Shot 02-44-02, Paint Spills and French Drain 02-59-01, Septic System 02-60-01, Concrete Drain 02-60-02, French Drain 02-60-03, Steam Cleaning Drain 02-60-04, French Drain 02-60-05, French Drain 02-60-06, French Drain 02-60-07, French Drain 23-60-01, Mud Trap Drain and Outfall 23-99-06, Grease Trap 25-60-04, Building 3123 Outfalls 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. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on December 11, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. 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 562. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 562 includes the following activities: Move surface debris and/or materials, as needed, to facilitate sampling. Conduct radiological surveys. Perform field screening. Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. Collect samples of source material to determine the potential for a release. Collect samples of potential remediation wastes. Collect quality control samples. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended February 2008). Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval of the plan.

  4. Closure Report for Corrective Action Unit 562: Waste Systems, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-08-15

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 562, Waste Systems, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 562 were met. 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). CAU 562 consists of the following 13 Corrective Action Sites (CASs), located in Areas 2, 23, and 25 of the Nevada National Security Site: CAS 02-26-11, Lead Shot CAS 02-44-02, Paint Spills and French Drain CAS 02-59-01, Septic System CAS 02-60-01, Concrete Drain CAS 02-60-02, French Drain CAS 02-60-03, Steam Cleaning Drain CAS 02-60-04, French Drain CAS 02-60-05, French Drain CAS 02-60-06, French Drain CAS 02-60-07, French Drain CAS 23-60-01, Mud Trap Drain and Outfall CAS 23-99-06, Grease Trap CAS 25-60-04, Building 3123 Outfalls Closure activities began in October 2011 and were completed in April 2012. Activities were conducted according to the Corrective Action Plan for CAU 562 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste and hazardous waste. Some wastes exceeded land disposal limits and required offsite treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite or offsite landfills. NNSA/NSO requests the following: A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 562 The transfer of CAU 562 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

  5. F3D Image Processing and Analysis for Many - and Multi-core Platforms

    Energy Science and Technology Software Center (OSTI)

    2014-10-01

    F3D is written in OpenCL, so it achieve[sic] platform-portable parallelism on modern mutli-core CPUs and many-core GPUs. The interface and mechanims to access F3D core are written in Java as a plugin for Fiji/ImageJ to deliver several key image-processing algorithms necessary to remove artifacts from micro-tomography data. The algorithms consist of data parallel aware filters that can efficiently utilizes[sic] resources and can work on out of core datasets and scale efficiently across multiple accelerators. Optimizingmore » for data parallel filters, streaming out of core datasets, and efficient resource and memory and data managements over complex execution sequence of filters greatly expedites any scientific workflow with image processing requirements. F3D performs several different types of 3D image processing operations, such as non-linear filtering using bilateral filtering and/or median filtering and/or morphological operators (MM). F3D gray-level MM operators are one-pass constant time methods that can perform morphological transformations with a line-structuring element oriented in discrete directions. Additionally, MM operators can be applied to gray-scale images, and consist of two parts: (a) a reference shape or structuring element, which is translated over the image, and (b) a mechanism, or operation, that defines the comparisons to be performed between the image and the structuring element. This tool provides a critical component within many complex pipelines such as those for performing automated segmentation of image stacks. F3D is also called a "descendent" of Quant-CT, another software we developed in the past. These two modules are to be integrated in a next version. Further details were reported in: D.M. Ushizima, T. Perciano, H. Krishnan, B. Loring, H. Bale, D. Parkinson, and J. Sethian. Structure recognition from high-resolution images of ceramic composites. IEEE International Conference on Big Data, October 2014.« less

  6. Putting icing on the cake

    SciTech Connect (OSTI)

    Not Available

    1985-03-01

    By reclaiming the waste heat in the stacks of a steam boiler and baking ovens, the Pisano French Baking Company of California has reduced the boiler plant natural gas fuel consumption by 40% and has reduced its need for two boilers to one. Since the bakery produces French breads, live steam is required for the glazing operation. Therefore, two steam generators operate at about 12 psig with a design pressure of 15 psig. Due to the additional hardware requirements of the oven steam generator systems, the payback was extended, but fell within the investment company's guidelines. Installed cost for both generators was $26,865. First year savings for this portion of the project was $9,850, resulting in a simple payback of 33 months. The combined payback for both systems is 25 months.

  7. In-core flux sensor evaluations at the ATR critical facility

    SciTech Connect (OSTI)

    Troy Unruh; Benjamin Chase; Joy Rempe; David Nigg; George Imel; Jason Harris; Todd Sherman; Jean-Francois Villard

    2014-09-01

    Flux detector evaluations were completed as part of a joint Idaho State University (ISU) / Idaho National Laboratory (INL) / French Atomic Energy commission (CEA) ATR National Scientific User Facility (ATR NSUF) project to compare the accuracy, response time, and long duration performance of several flux detectors. Special fixturing developed by INL allows real-time flux detectors to be inserted into various ATRC core positions and perform lobe power measurements, axial flux profile measurements, and detector cross-calibrations. Detectors initially evaluated in this program include the French Atomic Energy Commission (CEA)-developed miniature fission chambers; specialized self-powered neutron detectors (SPNDs) developed by the Argentinean National Energy Commission (CNEA); specially developed commercial SPNDs from Argonne National Laboratory. As shown in this article, data obtained from this program provides important insights related to flux detector accuracy and resolution for subsequent ATR and CEA experiments and flux data required for bench-marking models in the ATR V&V Upgrade Initiative.

  8. Carbon Dioxide, Hydrographic, and Chemical Data Obtained During the R/V Maurice Ewing Cruise in the Atlantic Ocean (WOCE Section A17, 4 January - 21 March 1994)

    SciTech Connect (OSTI)

    Kozyr, Alex

    2005-06-30

    This documentation discusses the procedures and methods used to measure total carbon dioxide (TCO2), total alkalinity (TALK), and pH at hydrographic stations during the R/V Maurice Ewing cruise in the South Atlantic Ocean on the A17 WOCE section. Conducted as part of the World Ocean Circulation Experiment (WOCE), this cruise was also a part of the French WOCE program consisting of three expeditions (CITHER 1, 2, and 3) focused on the South Atlantic Ocean. The A17 section was occupied during the CITHER 2 expedition, which began in Montevideo, Uruguay, on January 4, 1994 and finished in Cayenne, French Guyana, on March 21, 1994. During this period the ship stopped in Salvador de Bahia and Recife, Brazil, to take on supplies and exchange personnel. Upon completion of the cruise the ship transited to Fort de France, Martinique. Instructions for accessing the data are provided.

  9. The orbits of the uranian satellites and rings, the gravity field of the uranian system, and the orientation of the pole of Uranus

    SciTech Connect (OSTI)

    Jacobson, R. A.

    2014-11-01

    French et al. determined the orbits of the Uranian rings, the orientation of the pole of Uranus, and the gravity harmonics of Uranus from Earth-based and Voyager ring occultations. Jacobson et al. determined the orbits of the Uranian satellites and the masses of Uranus and its satellites from Earth-based astrometry and observations acquired with the Voyager 2 spacecraft; they used the gravity harmonics and pole from French et al. Jacobson and Rush reconstructed the Voyager 2 trajectory and redetermined the Uranian system gravity parameters, satellite orbits, and ring orbits in a combined analysis of the data used previously augmented with additional Earth-based astrometry. Here we report on an extension of that work that incorporates additional astrometry and ring occultations together with improved data processing techniques.

  10. Locus heterogeneity in autosomal dominant spinocerebellar ataxia: Evidence for the existence of a fifth locus

    SciTech Connect (OSTI)

    Sarrazin, J.; Rouleau, G.A.; Andermann, E.

    1994-09-01

    The autosomal dominantly inherited spinocerebellar ataxias (SCAs) are a heterogeneous group of neurodegenerative disorders. To date, four loci have been identified: the SCA-1 locus (on chromosome (chr) 6p), the SCA-2 locus (on chr 12q), the SCA-3/MJD locus (on chr 14q), and more recently an SCA-4 locus was described (chr 16q) in a Utah kindred. We have studied one large French Canadian kindred with four generations of living affected individuals segregating an autosomal dominant form of SCA. Linkage analysis using anonymous DNA markers which flank the four previously described loci significantly excludes the French Canadian kindred from the SCA-1, SCA-2, SCA-3/MJD and SCA-4 loci. Therefore a fifth, still unmapped, SCA locus remains to be identified.

  11. NASA agreements advance Mars exploration, Los Alamos Rover instrument a key

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    component NASA agreements advance Mars exploration NASA agreements advance Mars exploration, Los Alamos Rover instrument a key component Los Alamos National Laboratory is coordinating with the French science and engineering team on developing SuperCam. June 17, 2015 SuperCam builds upon the successful capabilities demonstrated by ChemCam aboard the Curiosity Rover during NASA's current Mars Mission. SuperCam will allow researchers to sample rocks and other targets from a distance using a

  12. NERSC Announces 4th Annual HPC Achievement Award Winners

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NERSC Announces 4th Annual HPC Achievement Award Winners NERSC Announces 4th Annual HPC Achievement Award Winners March 22, 2016 NERSC winners 2016 Left to right: Charles Koven, Nathan Howard, Scott French. Not pictured: William Riley, David Lawrence, Min Si. Image: Margie Wylie, Berkeley Lab The Department of Energy's National Energy Research Scientific Computing Center (NERSC) announced the winners of the 2016 High Performance Computing (HPC) Achievement Awards today (March 22) during the

  13. 1

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Marianne Francois-Scientific modeling of materials and climate March 11, 2014 Marianne Francois-Scientific modeling of materials and climate With her eyes on the sky, Marianne François left pastoral Normandy in the French countryside to study flight. She landed in Florida, where she obtained her master's of science in aerospace engineering at Embry-Riddle, the world's largest aviation university. She followed with doctoral studies at the University of Florida. Throughout college, she was

  14. Closing Statement to the GNEP Ministerial | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Statement to the GNEP Ministerial Closing Statement to the GNEP Ministerial October 1, 2008 - 3:43pm Addthis Remarks as Prepared for Secretary Bodman Thank you, Minister Borloo . . . and many thanks to the French government for hosting this meeting and for your leadership within GNEP. I also want to acknowledge the four newest members of our Partnership: Armenia, Estonia, Morocco and Oman, each of which signed our Statement of Principles today. As Minister Borloo indicated, today the GNEP

  15. Community College Highlights Paducah Site Groundwater Model | Department of

    Energy Savers [EERE]

    Statement to the GNEP Ministerial Closing Statement to the GNEP Ministerial October 1, 2008 - 3:43pm Addthis Remarks as Prepared for Secretary Bodman Thank you, Minister Borloo . . . and many thanks to the French government for hosting this meeting and for your leadership within GNEP. I also want to acknowledge the four newest members of our Partnership: Armenia, Estonia, Morocco and Oman, each of which signed our Statement of Principles today. As Minister Borloo indicated, today the GNEP

  16. Internal compiler error for function pointer with identically named

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    arguments Internal compiler error for function pointer with identically named arguments Internal compiler error for function pointer with identically named arguments June 9, 2015 by Scott French, NERSC USG Status: Bug 21435 reported to PGI For pgcc versions after 12.x (up through 12.9 is fine, but 13.x and 14.x are not), you may observe an internal compiler error associated with function pointer prototypes when named arguments are used. Specifically, if a function pointer type is defined

  17. United States, France and Japan Increase Cooperation on Sodium-Cooled Fast

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Reactor Prototypes | Department of Energy France and Japan Increase Cooperation on Sodium-Cooled Fast Reactor Prototypes United States, France and Japan Increase Cooperation on Sodium-Cooled Fast Reactor Prototypes February 1, 2008 - 11:13am Addthis WASHINGTON, DC -The U.S Department of Energy (DOE), the French Atomic Energy Commission (CEA) and Japan Atomic Energy Agency (JAEA) today expanded cooperation to coordinate Sodium-Cooled Fast Reactor Prototype development through a Memorandum of

  18. file://L:\DOE-hanford.gov\public\boards\hab\advice\advice100.ht

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Chuck Clarke, Regional Administrator U.S. Environmental Protection Agency, Region 10 1200 Sixth Avenue Seattle, WA 98101 Tom Fitzsimmons, Director Washington Department of Ecology P.O. Box 47600 Olympia, WA 98504-7600 Keith Klein, Manager U.S. Department of Energy, Richland Operations P.O. Box 550 (A7-50) Richland, WA 99352 Dick French, Manager Office of River Protection 2440 Stevens Center Richland, WA 99352 Subject: TPA Agency Processes for Responding to HAB Consensus Advice Dear Messrs.

  19. http://www.hanford.gov/boards/hab/response/104.htm

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    IPI-143 Advice # 104 From: Marla K. Marvin Ms. Merilyn Reeves, Chair Hanford Advisory Board 723 The Parkway, Suite 200: B1 -41 Richland, Washington 99352 Dear Ms. Reeves: HANFORD ADVISORY BOARD (HAB) CONSENSUS ADVICE #104 This letter is in response to the HAB's advice regarding openness at Hanford to Carolyn Huntoon, DOE Headquarters, Keith Klein, RL Manager, and Dick French, ORP Manager, dated February 4, 2000 (Advice Letter #104). The advice letter was a follow up to the discussion at the

  20. http://www.hanford.gov/boards/hab/response/107.htm

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    065 Advice # 107 From: Richard T. French Ms. Merilyn B. Reeves, Chair Hanford Advisory Board 723 The Parkway, Suite 200: B1 -41 Richland, Washington 99352 Dear Ms. Reeves: RESPONSE TO COMMENTS ON HANFORD ADVISORY BOARD (HAB) CONSENSUS ADVICE #107 This letter and its attachments are in response to Advice #107 to the U.S. Department of Energy, Office of River Protection (ORP) on its Fiscal Year (FY) 2002 Integrated Priority List (IPL). We appreciate your participation in the FY 2002 budget

  1. Worldwide report, arms control

    SciTech Connect (OSTI)

    1987-03-18

    This report contains translations/transcriptions of articles and/or broadcasts on Arms Control. Titles include: USSR Journal Review of French Book on SDI; Moscow Talk Show Considers Possibility of Dealing with U.S.; Thatcher, Gorbachev Talks Anticipated; U.S. Presents Draft Treaty to Eliminate INF from Europe; TASS: White House Rejects Treaty of Tatotonga; Soviet Paper on Congressional Divisions on Moratorium; Turkish Officials on Deployment of Nuclear Weapons; and others.

  2. South America, Central America, the Caribbean, and Mexico

    SciTech Connect (OSTI)

    Deal, C.

    1981-10-01

    Summaries of oil and gas drillings, well completions, production, exploratory wells, exploration activity and wildcat drilling were given for South America, Central America, the Caribbean, and Mexico. The countries, islands, etc. included Argentina, Bahamas, Barbados, Belize, Bolivia, Brazil, Colombia, Costa Rica, Cuba, Dominican Republic, Ecuador, French Guiana, Guatemala, Guyana, Haiti, Honduras, Jamaica, Leeward and Windward Islands, Mexico, Netherlands Antilles, Nicaragua, Panama, Paraguay, Peru, Puerto Rico, El Salvador, Surinam, Trinidad and Venezuela. 16 figures, 120 tables. (DP)

  3. A LANL Scientist's Dream Takes Off to Zap Rocks on Mars

    ScienceCinema (OSTI)

    Wiens, Roger

    2012-08-02

    Roger Wiens, with a team of 40 people at Los Alamos National Laboratory and the collaboration of the French space institute IRAP, created ChemCam, a laser spectrometer and telescope device aboard the Curiosity rover. ChemCam will blast rocks from as far as 7 meters, vaporize bits of their surfaces, and spectroscopically determine their chemical composition, aiding in the search for life on Mars, and making this scientist's boyhood dream a reality.

  4. PROJECT PROFILE: Case Western Reserve University (PREDICTS 2) | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy Case Western Reserve University (PREDICTS 2) PROJECT PROFILE: Case Western Reserve University (PREDICTS 2) CWRU Logo.jpg Funding Opportunity: PREDICTS 2 SunShot Subprogram: PV Location: Cleveland, OH Amount Awarded: $1,350,000 Awardee Cost Share: $348,425 Principal Investigator: Roger French Under their PREDICTS 2 award, researchers at Case Western Reserve University will analyze data sets from over 5 million solar photovoltaic (PV) panels around the world to learn how various

  5. Kerry Vahala: Jenkins Professor and Professor of Applied Physics,

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Kent L. Hibben About Us Kent L. Hibben - Acquisition Specialist Kent L. Hibben Kent is an Acquisition Specialist with the U.S. Department of Energy, Office of Small and Disadvantaged Business Utilization. Kent has extensive experience concerning the Office of Energy Efficiency and Renewable Energy, as well as issues related to small businesses and technology transfer, SBIR/STTR. Kent graduated from the University of Maryland, Baltimore County with Bachelor of Arts degrees in Economics, French,

  6. Settlement Agreement between DOE and LG Electronics | Department of Energy

    Energy Savers [EERE]

    Settlement Agreement between DOE and LG Electronics Settlement Agreement between DOE and LG Electronics November 6, 2015 DOE reached an agreement with LG Electronics, USA, Inc. (LG) that modifies a prior agreement under which LG had been making annual payments to consumers who had purchased certain models of LG and Kenmore-brand French Door refrigerators. Download complete agreement from link below. PDF icon Settlement Agreement between DOE and LG Electronics More Documents & Publications

  7. Kent L. Hibben | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Kent L. Hibben About Us Kent L. Hibben - Acquisition Specialist Kent L. Hibben Kent is an Acquisition Specialist with the U.S. Department of Energy, Office of Small and Disadvantaged Business Utilization. Kent has extensive experience concerning the Office of Energy Efficiency and Renewable Energy, as well as issues related to small businesses and technology transfer, SBIR/STTR. Kent graduated from the University of Maryland, Baltimore County with Bachelor of Arts degrees in Economics, French,

  8. NREL: Transmission Grid Integration - Research Staff

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Research Staff NREL's transmission and grid integration research staff work to incorporate renewable energy into the transmission system primarily through NREL's Power Systems Engineering Center. Photo of Barbara O'Neill Barbara O'Neill, Transmission and Grid Integration Group Manager M.S., Energy Management and Policy, University of Pennsylvania Engineering Diploma, Petroleum Economics and Management, French Institute of Petroleum B.S., Electrical Engineering, Pratt Institute Barbara has a

  9. Participants

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Participants Participants Large Scale Computing and Storage Requirements for Basic Energy Sciences A DOE Technical Program Review October 8-9, 2013 Front row, from left: Yun Liu, Dave Goodwin, Eliane Lessner, Jack Deslippe, Nick Woodward, Carl Steefel, Ceren Susut, Katie Antypas, Richard Gerber. Back row, from left: Scott French, Jeff Neaton, Sudip Dosanjh, Harvey Wasserman, Jim Davenport, David Skinner, Andy Felmy, Jacqueline Chen, Sotiris Xantheas, Greg Newman, Mark Pederson. Organizers and

  10. ARM - AMF Data Plots

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    West AfricaAMF Data Plots Niamey Deployment AMF Home Niamey Home Data Plots and Baseline Instruments Rainfall Record (PDF) Publications List, (PDF) Experiment Planning RADAGAST Proposal Outreach Fact Sheets RADAGAST (PDF) Annual Climate Cycle in Niger, Africa (PDF) Posters AMF Poster, French Version We're Going to Sample the Sky in Africa! News Campaign Images AMMA International News AMF Data Plots ARM Mobile Facility data plot example from the Micropulse Lidar on January 1, 2005. ARM Mobile

  11. PROCESS FOR PREPARING RARE EARTH CHROMITE BASED CERAMIC MATERIALS AND THE

    Office of Scientific and Technical Information (OSTI)

    MATERIALS OBTAINED. (Patent) | SciTech Connect Patent: PROCESS FOR PREPARING RARE EARTH CHROMITE BASED CERAMIC MATERIALS AND THE MATERIALS OBTAINED. Citation Details In-Document Search Title: PROCESS FOR PREPARING RARE EARTH CHROMITE BASED CERAMIC MATERIALS AND THE MATERIALS OBTAINED. (in French) Authors: Elston, J. ; Roux, M. Publication Date: 1971-01-01 OSTI Identifier: 4706266 Report Number(s): FR 2045001 . Resource Type: Patent Resource Relation: Other Information: Orig. Receipt Date:

  12. Comparative Study on Exhaust Emissions from Diesel-and CNG-powered Urban Buses

    Office of Scientific and Technical Information (OSTI)

    COMPARATIVE STUDY ON EXHAUST EMISSIONS FROM DIESEL- AND CNG-POWERED URBAN BUSES [ * ] Patrick COROLLER & Gabriel PLASSAT French Agency of Environment and Energy Management (ADEME) Air & Transport Division [ * ] presented at the DEER 2003 Conference by Dr. Thierry SEGUELONG, Aaqius & Aaqius) ABSTRACT Couple years ago, ADEME engaged programs dedicated to the urban buses exhaust emissions studies. The measures associated with the reduction of atmospheric and noise pollution has

  13. Microsoft PowerPoint - E1301037_B.pptx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Committee Briefing on the River Corridor Closure Project Mark French DOE-RL, Federal Project Director for the River Corridor Closure Project Carol Johnson Washington Closure Hanford, President and Project Manager February 2013 Protecting the Columbia River U.S. Department of Energy Richland Operations Office River Corridor Closure Project River Corridor Closure Project DOE's Largest Environmental Cleanup Closure Project RIVER CORRIDOR CLOSURE PROJECT One Team for Safe, Visible Cleanup of the

  14. Frontiers In Science public lectures: Harvesting energy from air

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    INVESTMENT IN COMMODITIES MARKETS: POTENTIAL IMPACT ON COMMODITY PRICES & VOLATILITY IIF Commodities Task Force Submission to the G20 September 2011 IIF Commodities Task Force Submission to the G20 Financial Investment in Commodity Markets: Potential Impact on Commodity Prices & Volatility 1 Preface Amidst increasing concerns about global growth prospects and financial market volatility, commodity prices con- tinue to be a focus for policymakers. The French G-20 presidency has made this

  15. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    French, Roger" Name Name ORCID Search Authors Type: All Book/Monograph Conference/Event Journal Article Miscellaneous Patent Program Document Software Manual Technical Report Thesis/Dissertation Subject: Identifier Numbers: Site: All Alaska Power Administration, Juneau, Alaska (United States) Albany Research Center (ARC), Albany, OR (United States) Albuquerque Complex - NNSA Albuquerque Operations Office, Albuquerque, NM (United States) Amarillo National Resource Center for Plutonium,

  16. ARM - Site Instruments

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Niamey, Niger, West AfricaInstruments Niamey Deployment AMF Home Niamey Home Data Plots and Baseline Instruments Rainfall Record (PDF) Publications List, (PDF) Experiment Planning RADAGAST Proposal Outreach Fact Sheets RADAGAST (PDF) Annual Climate Cycle in Niger, Africa (PDF) Posters AMF Poster, French Version We're Going to Sample the Sky in Africa! News Campaign Images AMMA International News Instruments : Niamey, Niger Active Retired Active instruments are currently deployed at fixed or

  17. ARM - Events Article

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    July 31, 2007 [Events] Second International African Monsoon Multidisciplinary Analyses (AMMA) Conference Abstracts Due August 15 Bookmark and Share The Second International AMMA Conference will take place in Karlsruhe, Germany, November 26-30. Abstracts will be accepted in English and French until August 15. The conference aims to bring together researchers from around the world working on the Western African monsoon and its impacts, to review ongoing research and modeling activities, and to

  18. Hanford Waste Vitrification Plant foreign alternatives feasibility study

    SciTech Connect (OSTI)

    Not Available

    1990-05-01

    The impacts and uncertainties of changing from the current Hanford Waste Vitrification Plant technology and plant design based on the liquid-fed ceramic melter to the French Ateliers Vitrification La Hague vitrification technology and plant design for vitrifying high-level defense wastes are considered in this report. An evaluation has been made as to whether the change might be a source of significant cost savings. The French Ateliers Vitrification La Hague technology is the only alternative at a sufficiently advanced stage of development to consider as a replacement for the current Hanford Waste Vitrification Plant technology. This study concludes that a significant cost savings could not be realized by changing to the French Ateliers Vitrification La Hague technology and design for the Hanford Waste Vitrification Plant. The study provides a rough comparison of plant costs based on available information. An improved cost estimate could be developed through more detailed study, but it would be unlikely to change the overall conclusion. 7 figs., 3 tabs.

  19. Corrective Action Decision Document for Corrective Action Unit 562: Waste Systems Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Krause

    2010-08-01

    This Corrective Action Decision Document (CADD) presents information supporting the selection of corrective action alternatives (CAAs) leading to the closure of Corrective Action Unit (CAU) 562, Waste Systems, in Areas 2, 23, and 25 of the Nevada Test Site, Nevada. This complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 562 comprises the following corrective action sites (CASs): 02-26-11, Lead Shot 02-44-02, Paint Spills and French Drain 02-59-01, Septic System 02-60-01, Concrete Drain 02-60-02, French Drain 02-60-03, Steam Cleaning Drain 02-60-04, French Drain 02-60-05, French Drain 02-60-06, French Drain 02-60-07, French Drain 23-60-01, Mud Trap Drain and Outfall 23-99-06, Grease Trap 25-60-04, Building 3123 Outfalls The purpose of this CADD is to identify and provide the rationale for the recommendation of CAAs for the 13 CASs within CAU 562. Corrective action investigation (CAI) activities were performed from July 27, 2009, through May 12, 2010, as set forth in the CAU 562 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective (DQO) process: Determine whether COCs are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. A data quality assessment (DQA) performed on the CAU 562 data demonstrated the quality and acceptability of the data for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against appropriate final action levels (FALs) to identify the COCs for each CAS. The results of the CAI identified COCs at 10 of the 13 CASs in CAU 562, and thus corrective action is required. Assessment of the data generated from investigation activities conducted at CAU 562 is shown in Table ES-1. Based on the evaluation of analytical data from the CAI, review of future and current operations at the 13 CASs, and the detailed and comparative analysis of the potential CAAs, the following corrective actions are recommended for CAU 562. No further action is the preferred corrective action for CASs 02-60-01, 02-60-06, and 02-60-07. Clean closure is the preferred corrective action for CASs 02-26-11, 02-44-02, 02-59-01, 02-60-02, 02-60-03, 02-60-04, 02-60-05, 23-60-01, 23-99-06, and 25-60-04. The preferred CAAs were evaluated on technical merit focusing on performance, reliability, feasibility, safety, and cost. The alternatives were judged to meet all requirements for the technical components evaluated. The alternatives meet all applicable federal and state regulations for closure of the site and will reduce potential exposures to contaminated media to acceptable levels. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: No further corrective action is required at CASs 02-60-01, 02-60-06, and 02-60-07. Clean closure is recommended for the remaining 10 CASs in CAU 562. A Corrective Action Plan will be submitted to the Nevada Division of Environmental Protection that contains a detailed description of the proposed actions that will be taken to implement the selected corrective actions.

  20. New developments and prospects on COSI, the simulation software for fuel cycle analysis

    SciTech Connect (OSTI)

    Eschbach, R.; Meyer, M.; Coquelet-Pascal, C.; Tiphine, M.; Krivtchik, G.; Cany, C.

    2013-07-01

    COSI, software developed by the Nuclear Energy Direction of the CEA, is a code simulating a pool of nuclear power plants with its associated fuel cycle facilities. This code has been designed to study various short, medium and long term options for the introduction of various types of nuclear reactors and for the use of associated nuclear materials. In the frame of the French Act for waste management, scenario studies are carried out with COSI, to compare different options of evolution of the French reactor fleet and options of partitioning and transmutation of plutonium and minor actinides. Those studies aim in particular at evaluating the sustainability of Sodium cooled Fast Reactors (SFR) deployment and the possibility to transmute minor actinides. The COSI6 version is a completely renewed software released in 2006. COSI6 is now coupled with the last version of CESAR (CESAR5.3 based on JEFF3.1.1 nuclear data) allowing the calculations on irradiated fuel with 200 fission products and 100 heavy nuclides. A new release is planned in 2013, including in particular the coupling with a recommended database of reactors. An exercise of validation of COSI6, carried out on the French PWR historic nuclear fleet, has been performed. During this exercise quantities like cumulative natural uranium consumption, or cumulative depleted uranium, or UOX/MOX spent fuel storage, or stocks of reprocessed uranium, or plutonium content in fresh MOX fuel, or the annual production of high level waste, have been computed by COSI6 and compared to industrial data. The results have allowed us to validate the essential phases of the fuel cycle computation, and reinforces the credibility of the results provided by the code.

  1. Industrial Program of Waste Management - Cigeo Project - 13033

    SciTech Connect (OSTI)

    Butez, Marc [Agence nationale pour la gestion des dechets radioactifs - Andra, 1-7, rue Jean Monnet 92298 Chatenay-Malabry (France)] [Agence nationale pour la gestion des dechets radioactifs - Andra, 1-7, rue Jean Monnet 92298 Chatenay-Malabry (France); Bartagnon, Olivier; Gagner, Laurent [AREVA NC Tour AREVA 1 place de la Coupole 92084 Paris La Defense (France)] [AREVA NC Tour AREVA 1 place de la Coupole 92084 Paris La Defense (France); Advocat, Thierry; Sacristan, Pablo [Commissariat a l'energie atomique et aux energies alternatives - CEA, CEA-SACLAY 91191 Gif sur Yvette Cedex (France)] [Commissariat a l'energie atomique et aux energies alternatives - CEA, CEA-SACLAY 91191 Gif sur Yvette Cedex (France); Beguin, Stephane [Electricite de France - EDF, Division Combustible Nucleaire, 1, Place Pleyel Site Cap Ampere93282 Saint Denis (France)] [Electricite de France - EDF, Division Combustible Nucleaire, 1, Place Pleyel Site Cap Ampere93282 Saint Denis (France)

    2013-07-01

    The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

  2. NUG Webinar Sep. 11, 2014

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sep 11, 2014 NUG Webinar Sep. 11, 2014 September 11, 2014 Date: Thursday, Sep. 11 Time: 11:00 PDT Connection Info Attendance: 62 Agenda Hopper and Edison Utilization, Backlog, and Queue Waits Carver SL6 OS upgrade and CHOS Update on the NESAP program and NERSC Application Readiness for Cori (NERSC-8) Dirac retirement reminder Edison memory replacement: downtime 9/25-9/29 NUGEX Elections Mini Seminar New NERSC HPC consultant Scott French will give a short (~20 minute) presentation on his

  3. Triangle Universities Nuclear Laboratory : 2011

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Shuttles Shuttle service will be provided for TUNL 50 guests according to the following schedule: Friday, Nov. 6 - From noon until 9 PM, shuttles will circulate every half-hour between Residence Inn by Marriott, Hilton Garden Inn, and the French Family Science Center (FFSC). Saturday, Nov. 7: 7:30 AM - 10 AM - Every half-hour between the hotels and FFSC Noon - 3 PM - Every half-hour between the hotels and FFSC 5 PM - 7 PM Every half-hour between the hotels, FFSC, and Trent Semans Center 9 PM -

  4. OSTI, US Dept of Energy, Office of Scientific and Technical Information |

    Office of Scientific and Technical Information (OSTI)

    Speeding access to science information from DOE and Beyond WorldWideScience.org Multilingual Search of Chemistry and Other Sciences ACS National Meeting Slide15 Slide16 Slide17 Slide18 Slide19 Slide20 Slide01 Slide02 Slide03 Slide04 Slide05 Slide06 Slide07 Slide08 Slide09 Slide10 Slide11 Slide12 Slide13 Slide14 Slide15 Slide15 Multilingual Translations Translating ten languages, with potential for more Arabic Chinese German Deutsch English Spanish Español French Français Japanese Korean

  5. Intel C++ compiler error: stl_iterator_base_types.h

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    C++ compiler error: stl_iterator_base_types.h Intel C++ compiler error: stl_iterator_base_types.h December 7, 2015 by Scott French Because the system-supplied version of GCC is relatively old (4.3.4) it is common practice to load the gcc module on our Cray systems when C++11 support is required under the Intel C++ compilers. While this works as expected under the GCC 4.8 and 4.9 series compilers, the 5.x series can cause Intel C++ compile-time errors similar to the following:

  6. Intel uses very old version of libstdc++ by default [updated]

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    uses very old version of libstdc++ by default [updated] Intel uses very old version of libstdc++ by default [updated] January 15, 2014 by Mike Stewart, NERSC USG Status: Reported to Cray as case 84319, became bug 806610. Updated October 13, 2014 by Scott French, NERSC USG When PrgEnv-intel is loaded, the Intel compiler gets libstdc++ from on the default environment on the login node, which is typically quite old. This test case illustrates the problem on Edison: > cat TestLibVersion.C

  7. The MIRTE Experimental Program: An Opportunity to Test Structural Materials in Various Configurations in Thermal Energy Spectrum

    SciTech Connect (OSTI)

    Leclaire, Nicolas; Le Dauphin, Francois-Xavier; Duhamel, Isabelle; Briggs, Blair; Piot, Jerome; Rennesson, Malvina; Laville, Arnaud

    2014-11-04

    The MIRTE (Materials in Interacting and Reflecting configurations, all Thicknesses) program was established to answer the needs of criticality safety practitioners in terms of experimental validation of structural materials and to possibly contribute to nuclear data improvement, which ultimately supports reactor safety analysis as well. MIRTE took the shape of a collaboration between the AREVA and ANDRA French industrialists and a noncommercial international funding partner such as the U.S. Department of Energy. The aim of this paper is to present the configurations of the MIRTE 1 and MIRTE 2 programs and to highlight the results of the titanium experiments recently published in the International Handbook of Evaluated Criticality Safety Benchmark Experiments.

  8. Modes of Occurrence of Trace and Minor Elements in Some Australian Coals

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Modes of Occurrence of Trace and Minor Elements in Some Australian Coals Citation Details In-Document Search Title: Modes of Occurrence of Trace and Minor Elements in Some Australian Coals Authors: Riley K. ; French, D ; Farrell, O ; Wood, R ; Huggins, F Publication Date: 2012-05-01 OSTI Identifier: 1069931 Report Number(s): BNL--100503-2013-JA Journal ID: ISSN 0166-5162 DOE Contract Number: DE-AC02-98CH10886 Resource Type: Journal Article Resource

  9. Experiment vs simulation RT WFNDEC 2014 benchmark: CIVA results

    SciTech Connect (OSTI)

    Tisseur, D. Costin, M. Rattoni, B. Vienne, C. Vabre, A. Cattiaux, G.; Sollier, T.

    2015-03-31

    The French Atomic Energy Commission and Alternative Energies (CEA) has developed for years the CIVA software dedicated to simulation of NDE techniques such as Radiographic Testing (RT). RT modelling is achieved in CIVA using combination of a determinist approach based on ray tracing for transmission beam simulation and a Monte Carlo model for the scattered beam computation. Furthermore, CIVA includes various detectors models, in particular common x-ray films and a photostimulable phosphor plates. This communication presents the results obtained with the configurations proposed in the World Federation of NDEC 2014 RT modelling benchmark with the RT models implemented in the CIVA software.

  10. exploration, Los Alamos Rover

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NASA agreements advance Mars exploration, Los Alamos Rover instrument a key component June 17, 2015 SuperCam's body to be built at Los Alamos and the mast in France LOS ALAMOS, N.M., June 17, 2015-NASA Administrator Charles Bolden and Jean-Yves Le Gall, president of the French space agency, Centre National d'Etudes Spatiales (CNES), signed an agreement Tuesday at the Paris Air Show for France to provide the mast unit for the SuperCam component of NASA's Mars 2020 rover. Los Alamos National

  11. COP 21 Shelby Cobra | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    COP 21 Shelby Cobra COP 21 Shelby Cobra Addthis 1 of 12 U.S. Secretary of Agriculture Tom Vilsack visits the Shelby Cobra at the COP 21 conference in Paris. Image: Photo courtesy U.S. Department of Energy 2 of 12 U.S. Ambassador to France and Monaco Jane Hartley discusses 3D printing technology and advanced manufacturing with Rob Ivester from EERE's Advanced Manufacturing Office Image: Photo courtesy U.S. Department of Energy 3 of 12 French Minister of Foreign Affairs and International

  12. Jefferson Lab Weekly Briefs May 11, 2016 | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Jefferson Lab Weekly Briefs May 11, 2016 Jefferson Lab Weekly Briefs May 11, 2016 12 GeV Upgrade After effectively completing repairs, the cryogenic distribution box has been moved from the Technology and Engineering Development Building high bay to Hall B. The distribution box is now installed on the third level of the CLAS12 platform. Work is progressing on the pump-out of the Torus magnet in preparation for cool-down next month. The French magnet factory, Sigmaphi, finished measuring the

  13. LOS ALAMOS, N.M., January 15, 2013-Researchers from Los Alamos National

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    follows the 'Yellowknife Road' to Martian wet area January 15, 2013 Instrument confirms presence of gypsum and related minerals LOS ALAMOS, N.M., January 15, 2013-Researchers from Los Alamos National Laboratory and the French Space Agency have tracked a trail of minerals that point to the prior presence of water at the Curiosity rover site on Mars. Researchers from the Mars Science Laboratory's ChemCam team today described how the laser instrument aboard the Curiosity Rover-an SUV-sized vehicle

  14. DOE Reaches Agreement with LG Electronics | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Agreement with LG Electronics DOE Reaches Agreement with LG Electronics November 6, 2015 - 1:28pm Addthis DOE reached an agreement with LG Electronics, USA, Inc. (LG) that modifies a prior agreement under which LG had been making annual payments to consumers who had purchased certain models of LG and Kenmore-brand French Door refrigerators. Under the modified agreement, LG will issue one larger, lump-sum payment to each of the approximately 92,000 customers who are currently receiving annual

  15. Eddy current NDE performance demonstrations using simulation tools

    SciTech Connect (OSTI)

    Maurice, L.; Costan, V.; Guillot, E.; Thomas, P.

    2013-01-25

    To carry out performance demonstrations of the Eddy-Current NDE processes applied on French nuclear power plants, EDF studies the possibility of using simulation tools as an alternative to measurements on steam generator tube mocks-up. This paper focuses on the strategy led by EDF to assess and use code{sub C}armel3D and Civa, on the case of Eddy-Current NDE on wears problem which may appear in the U-shape region of steam generator tubes due to the rubbing of anti-vibration bars.

  16. LANL Researcher Roger Wiens Discusses ChemCam

    ScienceCinema (OSTI)

    Wiens, Roger

    2014-08-12

    Discussion of the ChemCam instrument on the Curiosity Rover that occurred during the NASA press conference prior to launch of the Mars Science Laboratory. The ChemCam instrument was developed by Los Alamos National Laboratory and the French Space Institute. Los Alamos National Laboratory researcher Roger Wiens discusses the instrument on this video. ChemCam uses a laser to "zap" features of the Martian landscape and then uses a spectrometer to gather information about the composition of the sample. ChemCam will help the Curiosity Rover determine whether Mars is or was habitable. The Rover is expected to touch down on the Red Planet on August 5, 2012.

  17. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  18. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  19. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  20. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  1. Department of Energy to Take Steps to Remove ENERGY STAR Label on Certain

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    LG Refrigerator-Freezer Models | Department of Energy to Take Steps to Remove ENERGY STAR Label on Certain LG Refrigerator-Freezer Models Department of Energy to Take Steps to Remove ENERGY STAR Label on Certain LG Refrigerator-Freezer Models December 7, 2009 - 12:00am Addthis Washington, DC - The Department of Energy announced today that as part of the expanded enforcement efforts under the ENERGY STAR® program, effective January 2, 2010, certain LG French-door refrigerator-freezers are

  2. ENERGY OF THE DEFECTS INDUCED BY NEUTRON IRRADIATION IN MgO. (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect ENERGY OF THE DEFECTS INDUCED BY NEUTRON IRRADIATION IN MgO. Citation Details In-Document Search Title: ENERGY OF THE DEFECTS INDUCED BY NEUTRON IRRADIATION IN MgO. (in French) Authors: Roux, A. ; Elston, J. Publication Date: 1970-01-01 OSTI Identifier: 4170057 Resource Type: Journal Article Resource Relation: Journal Name: Compt. Rend., Ser. C 270: 505-8(9 Feb 1970).; Other Information: Orig. Receipt Date: 31-DEC-70 Research Org: Institut National des Sciences

  3. C++11 header files appear missing on Edison

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    C++11 header files appear missing on Edison C++11 header files appear missing on Edison December 3, 2014 by Scott French, NERSC USG Status: Reported to Cray (801693), Workaround available When using the default Intel compiler environment on Edison to compile C++11 code (-std=c++11), it appears that the associated header files cannot be found: edison03:~ > CC -std=c++11 test.cxx -o test.x test.cxx(2): catastrophic error: cannot open source file "chrono" #include <chrono> ^

  4. A FAR-out experience | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    FAR-out experience A FAR-out experience Posted: April 19, 2013 - 1:09pm Y-12 lawyer Chuck Young discusses the Federal Acquisition Regulation with intern Leigh Outten. Y-12's current Legal intern, Leigh Outten, is something of a degree collector. She holds a bachelor's degree in mechanical engineering; two master's degrees from MIT - one in nuclear engineering, the other in technology and policy; and an MBA from a French school. Now she's in her third year of UT's law program. What does one do

  5. CP2K

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    COP 21 Shelby Cobra COP 21 Shelby Cobra Addthis 1 of 12 U.S. Secretary of Agriculture Tom Vilsack visits the Shelby Cobra at the COP 21 conference in Paris. Image: Photo courtesy U.S. Department of Energy 2 of 12 U.S. Ambassador to France and Monaco Jane Hartley discusses 3D printing technology and advanced manufacturing with Rob Ivester from EERE's Advanced Manufacturing Office Image: Photo courtesy U.S. Department of Energy 3 of 12 French Minister of Foreign Affairs and International

  6. R I

    Office of Legacy Management (LM)

    . [b, R I c ~ ~ & F, INC. L A ~ & L E ' , - F~ZVICES \ : " ' May 11,2004 Pamela S. French Stoller-Navarro 7710 West Cheyenne Avenue Las Vegas, NV 89129 Re: Tatum Salt Dome site Lamas County, Mississippi Dear Pamela, Enclosed you will fmd the original title opinion that we have prepared for the abo referenced property owned by the United States of America. I have also enclose supporting documents for the ownership interests as reflected in the title opinion. Thank you for allowing

  7. Angels and Demons: The Science Behind the Scenes

    SciTech Connect (OSTI)

    Graf, Norman

    2009-05-12

    Does antimatter really exist? How and why do scientists produce and use it? Does CERN exist and is there an underground complex deep beneath the Swiss/French border? Is truth stranger than fiction? Find out at the coming public lecture. On Tuesday, May 12, SLAC physicist Norman Graf will discuss the real science behind Angels & Demons, Dan Brown's blockbuster novel and the basis of an upcoming Tom Hanks movie. Graf's' talk is one in a series of public lectures across the U.S., Canada and Puerto Rico to share the science of antimatter and the Large Hadron Collider, and the excitement of particle physics research.

  8. RAP Committee 3-Month Work Plan

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    /19/16 Facilitator notes in blue * Placeholder dates for April committee meetings and committee calls are combined February March April * Committee meeting placeholder: Tuesday, Feb. 9 Call placeholder: Tuesday, Feb. 16, 1:30 p.m. Committee meeting placeholder: Tuesday, Mar. 5 Call placeholder: Tuesday, Mar. 22, 1:30 p.m. Committee meeting placeholder: Tuesday, Apr. 26 Call placeholder: Tuesday, Apr. 26, 1:30 p.m.  618-10 Burial Ground Vertical Pipe Units update o Mark French, DOE-RL, subject

  9. Microsoft PowerPoint - E1111057_A.pptx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Ri d Pl t C itt DOE's Largest Environmental Cleanup Closure Project River and Plateau Committee 618-10/11 Burial Grounds and 324 Ri C id Grounds and 324 Building Update River Corridor Closure Project River Corridor Closure Project Mark French and Jamie Zeisloft U.S. Department of Energy D b 7 2011 December 7, 2011 Protecting the Columbia River U.S. Department of Energy Richland Operations Office RIVER CORRIDOR CLOSURE PROJECT One Team for Safe, Visible Cleanup of the River Corridor 618-10 Burial

  10. High-tech tool predicts fire behavior in bark beetle-ravaged forests

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Better computer models High-tech tool predicts fire behavior in bark beetle-ravaged forests A high-tech computer model called HIGRAD/FIRETEC provides insights that are essential for front-line fire fighters. August 9, 2012 Researchers from LANL and the French Space Agency examine data from the Mars Science Laboratory Curiosity rover from inside the ChemCam Operations Center at NASA's Jet Propulsion Laboratory on Monday, Aug. 6, 2012, less than a day after the rover landed on Mars. The ChemCam

  11. BSM Newsletter May 2016

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Newsletter » May 2016 At the Bradbury Latest Issue:May 2016 all issues All Issues » submit IN THIS ISSUE Space scientist tapped for French knighthood Lab scientist honored and had quite a day Before there were computers, there were calculators The lack of calculators in our collection didn't add up Holistic data analysis and modeling poised to transform protein X-ray crystallography From our pages Why did they blow up 100 tons of TNT before the Trinity Test? Science question of the month

  12. Energy resources in southern Africa: a select bibliography

    SciTech Connect (OSTI)

    Cavan, A.

    1981-01-01

    The aims, progress, and possibilities involved in Southern Africa's energy development are the subject of this 473-item bibliography. The primary items of information described in this document are relatively recent (1975-81), originate from both indigenous and international sources, and are mostly in English, although a few are in French and Portuguese. The presented information focuses on the African continent, the Southern African region, and the nations of Angola, Botswana, Lesotho, Malawi, Mozambique, Namibia, Swaziland, South Africa, Tanzania, Zambia, and Zimbabwe. The energy source topics include alcohol, coal, gas, oil, solar, uranium, water, wind, and wood; as well as a general energy-development category.

  13. Compiling with -ipo produces "unresolved" warning messages at link time on

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cray systems Compiling with -ipo produces "unresolved" warning messages at link time on Cray systems Compiling with -ipo produces "unresolved" warning messages at link time on Cray systems November 18, 2013 by Mike Stewart, NERSC USG Status: Reported to the darshan developers. Updated June 12, 2015 by Scott French, NERSC USG Updated March 9, 2016 by Jialin Liu, NERSC DAS This bug affects our Cray systems Edison and Cori, and is still present as of March 2016. When a code

  14. Cray C/C++ predefined _RELEASE macro returns wrong value [updated]

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Reports » Cray C/C++ predefined _RELEASE macro returns wrong value [updated] Cray C/C++ predefined _RELEASE macro returns wrong value [updated] November 18, 2013 by Mike Stewart, NERSC USG Status: Reported to Cray as bug 797442, became documentation bug 805340. Updated October 14, 2014 by Scott French, NERSC USG According to the Sept, 2013, version of the Cray C/C++ manual at docs.cray.com, Chapter 10, "Using Predefined Macros": Macro Description _RELEASE Defined as the major release

  15. MB3a Infrasound Sensor Evaluation.

    SciTech Connect (OSTI)

    Merchant, Bion J.; McDowell, Kyle D.

    2014-11-01

    Sandia National Laboratories has tested and evaluated a new infrasound sensor, the MB3a, manufactured by Seismo Wave. These infrasound sensors measure pressure output by a methodology developed by researchers at the French Alternative Energies and Atomic Energy Commission (CEA) and the technology was recently licensed to Seismo Wave for production and sales. The purpose of the infrasound sensor evaluation was to determine a measured sensitivity, transfer function, power, self-noise, dynamic range, seismic sensitivity, and self- calibration ability. The MB3a infrasound sensors are being evaluated for potential use in the International Monitoring System (IMS) of the Comprehensive Nuclear Test-Ban-Treaty Organization (CTBTO).

  16. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  17. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  18. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  19. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the cellular electron transport chain. However, not all fungi are sensitive to copper toxicity. Some, called

  20. Formation of Metallic Copper Nanoparticles at the Soil-Root Interface

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Formation of Metallic Copper Nanoparticles at the Soil-Root Interface Print Wednesday, 26 March 2008 00:00 The first commercial fungicide-the "Bordeaux mixture" of copper sulfate and lime-was used to fight downy mildew in French vineyards. The fungicide worked by catalyzing the production of free radicals that damage proteins and enzymes involved in cycling copper between Cu(I) and Cu(II) oxidation states in the

  1. PLEASE RETURN TO PDCC FOR CORRECTIONS

    Office of Legacy Management (LM)

    PLEASE RETURN TO PDCC FOR CORRECTIONS ~ F : S : R : D R : C ~ H : R : o L N : S F T I L : E M. se~;/:~~;: : : : : :::::EHC~DATA : B : E ~ H ~ '"" ENVIRON SAFETY & HEALTH :::s ~ FSRD NOTEBOOKS SAFETY & HEALTH BEH ~ ~ READING FILE ENVIR COMPLIANCE BEH '\.. ....... ~ DOE/P&CD: French/Sislrunk DCa WASTE MGMT & TREATMENT BEH § ~ DOE/HQ: J. Wagoner DHQ PROCUREMENT BPO ::::s ~ 1-~~~~~~~~~~+~+~t---t~TM-Al-E-B-E-RL-IN-E-------+-B-ET-+-+-+-:-::-~-:-~-~

  2. ChemCam sends digital 'thumbs up'

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ChemCam sends digital 'thumbs up' ChemCam sends digital 'thumbs up' Members of the team got a digital thumbs up about the operational readiness of their instrument just hours after the rover landed on Martian soil. August 8, 2012 Researchers from LANL and the French Space Agency examine data from the Mars Science Laboratory Curiosity rover from inside the ChemCam Operations Center at NASA's Jet Propulsion Laboratory on Monday, Aug. 6, 2012, less than a day after the rover landed on Mars. The

  3. DOE Authorizes SRR to Assume LW Operations at SRS on 07 01...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Media Contacts: For Immediate Release DOE: Julie Petersen, (803) 952-75690 July 1, 2009 julie.petersen@srs.gov SRR: Rick Kelley, (803) 208-1707 rick.kelley@srs.gov DOE AUTHORIZES NEW CONTRACTOR TO ASSUME LIQUID WASTE OPERATIONS AT SRS AIKEN, S.C. - On June 30, 2009, the U.S. Department of Energy Savannah River Operations Office (DOE-SR) Manager Jeffrey M. Allison and the Savannah River Remediation, LLC (SRR) President Jim French signed the final documents authorizing SRR to assume the duties as

  4. The dosimetric consequences of the new DOT LSA definition

    SciTech Connect (OSTI)

    Mis, F.J.

    1996-10-01

    As a result of the new regulations for the transportation of radioactive materials, the DOT and the NRC have implemented a rule designed to limit the activity in an LSA container. This is a new regulation designed to insure that the spirit of the law as well as the letter of the law are followed for LSA shipments. Specifically, it limits the dose rate at any location on an unshielded LSA container to less than 1 rem/hr at 3 meters. Other possible alternatives had been discussed prior to the implementation of this regulation including multiples of A{sub 2} values, as implemented by the French.

  5. LLNL Results from CALIBAN-PROSPERO Nuclear Accident Dosimetry Experiments in September 2014

    SciTech Connect (OSTI)

    Lobaugh, M. L.; Hickman, D. P.; Wong, C. W.; Wysong, A. R.; Merritt, M. J.; Heinrichs, D. P.; Topper, J. D.

    2015-05-21

    Lawrence Livermore National Laboratory (LLNL) uses thin neutron activation foils, sulfur, and threshold energy shielding to determine neutron component doses and the total dose from neutrons in the event of a nuclear criticality accident. The dosimeter also uses a DOELAP accredited Panasonic UD-810 (Panasonic Industrial Devices Sales Company of America, 2 Riverfront Plaza, Newark, NJ 07102, U.S.A.) thermoluminescent dosimetery system (TLD) for determining the gamma component of the total dose. LLNL has participated in three international intercomparisons of nuclear accident dosimeters. In October 2009, LLNL participated in an exercise at the French Commissariat à l’énergie atomique et aux énergies alternatives (Alternative Energies and Atomic Energy Commission- CEA) Research Center at Valduc utilizing the SILENE reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison at CEA Valduc, this time with exposures at the CALIBAN reactor (Hickman et al. 2011). This paper discusses LLNL’s results of a third intercomparison hosted by the French Institut de Radioprotection et de Sûreté Nucléaire (Institute for Radiation Protection and Nuclear Safety- IRSN) with exposures at two CEA Valduc reactors (CALIBAN and PROSPERO) in September 2014. Comparison results between the three participating facilities is presented elsewhere (Chevallier 2015; Duluc 2015).

  6. Treatment of G1 Baskets at the CEA Marcoule Site - 12027

    SciTech Connect (OSTI)

    Fourquet, Line; Boya, Didier

    2012-07-01

    In the dismantling program for the first-generation French reactors in accordance with the nonproliferation treaty, the CEA is in charge of cleanup and dismantling operations for the facilities at Marcoule, including the decladding units. The G1 decladding was built between 1955 and 1957 in order to de-clad spent fuel elements from the G1 plutonium-producing reactor and prepare them for dissolution. The facility was also used for interim storage of G1, G2 and G3 fuel dissolution baskets, which had been used during plant operation for transfer (from the decladding facility to the UP1 plant) and/or dissolution of spent fuel elements. One of the cleanup projects involves recovery of the baskets, which will be cut up, sorted, and conditioned in metal bins. The bins will be immobilized with cement grout, then transferred to the onsite solid waste conditioning facility (CDS) and to the repository operated by the French National Radioactive Waste Management Agency (ANDRA). The project is now in progress, after special safety permits were issued and measurement stations and dedicated tools were developed to handle all types of baskets (which differed according to their origin and use). The disposal of all the baskets is scheduled to last 2 years and will produce 55 metal waste bins. (authors)

  7. Bomb tests attack the food chain

    SciTech Connect (OSTI)

    Ruff, T. )

    1990-03-01

    Ciguatera poisoning, the most common type of fish poisoning in the world, has become a major public health problem in some parts of the South Pacific. This area has always been the site of periodic outbreaks, especially after severe storms or natural disasters that damage core reefs. But since World War II it has become evident that military activities and major construction projects that wreak havoc on corals also lead to ciguatera outbreaks. Extraordinarily high rates of ciguatera poisoning have occurred on the small Pacific islands that have been used for nuclear tests and on the islands that host the military infrastructures and activities that accompany the tests. This is true for both the Marshall Islands near Bikini and Eniwetok, where U.S. tests took place, and in French Polynesia, in the area around Moruroa Atoll where the French government continues to test. Ciguatera poisoning has a disastrous effect on people who depend on fishing as a way of life and on fish as the major source of protein. 10 refs.

  8. Validation of the new code package APOLLO2.8 for accurate PWR neutronics calculations

    SciTech Connect (OSTI)

    Santamarina, A.; Bernard, D.; Blaise, P.; Leconte, P.; Palau, J. M.; Roque, B.; Vaglio, C.; Vidal, J. F.

    2013-07-01

    This paper summarizes the Qualification work performed to demonstrate the accuracy of the new APOLLO2.S/SHEM-MOC package based on JEFF3.1.1 nuclear data file for the prediction of PWR neutronics parameters. This experimental validation is based on PWR mock-up critical experiments performed in the EOLE/MINERVE zero-power reactors and on P.I. Es on spent fuel assemblies from the French PWRs. The Calculation-Experiment comparison for the main design parameters is presented: reactivity of UOX and MOX lattices, depletion calculation and fuel inventory, reactivity loss with burnup, pin-by-pin power maps, Doppler coefficient, Moderator Temperature Coefficient, Void coefficient, UO{sub 2}-Gd{sub 2}O{sub 3} poisoning worth, Efficiency of Ag-In-Cd and B4C control rods, Reflector Saving for both standard 2-cm baffle and GEN3 advanced thick SS reflector. From this qualification process, calculation biases and associated uncertainties are derived. This code package APOLLO2.8 is already implemented in the ARCADIA new AREVA calculation chain for core physics and is currently under implementation in the future neutronics package of the French utility Electricite de France. (authors)

  9. (Environmental technology)

    SciTech Connect (OSTI)

    Boston, H.L.

    1990-10-12

    The traveler participated in a conference on environmental technology in Paris, sponsored by the US Embassy-Paris, US Environmental Protection Agency (EPA), the French Environmental Ministry, and others. The traveler sat on a panel for environmental aspects of energy technology and made a presentation on the potential contributions of Oak Ridge National Laboratory (ORNL) to a planned French-American Environmental Technologies Institute in Chattanooga, Tennessee, and Evry, France. This institute would provide opportunities for international cooperation on environmental issues and technology transfer related to environmental protection, monitoring, and restoration at US Department of Energy (DOE) facilities. The traveler also attended the Fourth International Conference on Environmental Contamination in Barcelona. Conference topics included environmental chemistry, land disposal of wastes, treatment of toxic wastes, micropollutants, trace organics, artificial radionuclides in the environment, and the use biomonitoring and biosystems for environmental assessment. The traveler presented a paper on The Fate of Radionuclides in Sewage Sludge Applied to Land.'' Those findings corresponded well with results from studies addressing the fate of fallout radionuclides from the Chernobyl nuclear accident. There was an exchange of new information on a number of topics of interest to DOE waste management and environmental restoration needs.

  10. Ion source development for a photoneutralization based NBI system for fusion reactors

    SciTech Connect (OSTI)

    Simonin, A.; Esch, H. P. L. de; Garibaldi, P.; Grand, C.; Bechu, S.; Bs, A.; Lacoste, A.

    2015-04-08

    The next step after ITER is to demonstrate the viability and generation of electricity by a future fusion reactor (DEMO). The specifications required to operate an NBI system on DEMO are very demanding. The system has to provide a very high level of power and energy, ~100MW of D beam at 1MeV, including high wall-plug efficiency (? > 60%). For this purpose, a new injector concept, called Siphore, is under investigation between CEA and French universities. Siphore is based on the stripping of the accelerated negative ions by photo-detachment provided by several Fabry-Perot cavities (3.5MW of light power per cavity) implemented along the D{sup ?} beam. The beamline is designed to be tall and narrow in order that the photon flux overlaps the entire negative ion beam. The paper will describe the present R and D at CEA which addresses the development of an ion source and pre-accelerator prototypes for Siphore, the main goal being to produce an intense negative ion beam sheet. The negative ion source Cybele is based on a magnetized plasma column where hot electrons are emitted from the source center. Parametric studies of the source are performed using Langmuir probes in order to characterize the plasma and to compare with numerical models being developed in French universities.

  11. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    SciTech Connect (OSTI)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-15

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample-taking to characterize solvent contained in one tank of Petrus installation (NLF 57, building 18) for radiological and chemical analysis needed to prepare the treatment and the evacuation of these wastes : internal authorization ; realised in june 2005. It was possible to plan the whole decommissioning process on the Nuclear Licensed Facilities of Fontenay-aux-Roses's Center (CEA/FAR) taking into account the French new regulation and to plan a coherent and continue program activity for the dismantling process. For the program not to be interrupted during the administrative process (2003-2006), specific authorisations have been delivered by the French Nuclear Safety Authority or by the General Executive Director (GED) on the CEA Fontenay-aux- Roses's Center (internal authorization). The time schedule to complete the entire program is until 2017 for NLF 'Procede' (NLF no 165) and until 2018 for NLF 'Support' (NLF no 166). Since 1999, an annual press meeting has been organised by the Fontenay-aux-Roses's Center Head Executive Manager.

  12. Subsea control system undergoes qualification test

    SciTech Connect (OSTI)

    Lia, A.

    1996-10-01

    The booming market for subsea equipment has spawned the development of new control technologies. Proper testing is required before incorporating these new systems in production applications. In early 1996, French firm ECA began a 6-month test of a lightweight subsea control system at the offshore premises of Frame Engineering in Bergen, Norway. The purpose of the 6-month experiment is to test the various components of a control system. These include the tele-operated valve (TOV), a 66-lb (30-kg) module which provides electrohydraulic control of a Christmas tree, the subsea hydro-electric pump (HPU), the electrical inductively coupled link which provides power and data transmission on a single wire cable, and the subsea mateable optical connector.

  13. Development and application of modeling tools for sodium fast reactor inspection

    SciTech Connect (OSTI)

    Le Bourdais, Florian; Marchand, Benoît; Baronian, Vahan

    2014-02-18

    To support the development of in-service inspection methods for the Advanced Sodium Test Reactor for Industrial Demonstration (ASTRID) project led by the French Atomic Energy Commission (CEA), several tools that allow situations specific to Sodium cooled Fast Reactors (SFR) to be modeled have been implemented in the CIVA software and exploited. This paper details specific applications and results obtained. For instance, a new specular reflection model allows the calculation of complex echoes from scattering structures inside the reactor vessel. EMAT transducer simulation models have been implemented to develop new transducers for sodium visualization and imaging. Guided wave analysis tools have been developed to permit defect detection in the vessel shell. Application examples and comparisons with experimental data are presented.

  14. IN-CORE FLUX SENSOR EVALUATIONS AT THE ATR CRITICAL FACILITY.

    SciTech Connect (OSTI)

    Troy Unruh; Benjamin Chase; Joy Rempe; David Nigg; George Imel; Jason Harris; Todd Sherman; Jean-Francois VIllard

    2014-12-01

    As part of an Idaho State University (ISU)–led Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) collaborative project that includes Idaho National Laboratory (INL) and the French Alternative Energies and Atomic Energy Commission (CEA), flux detector evaluations were completed to compare their accuracy, response time, and longduration performance. Special fixturing, developed by INL, allows real-time flux detectors to be inserted into various Advanced Test Reactor Critical Facility (ATRC) core positions to perform lobe power measurements, axial flux profile measurements, and detector crosscalibrations. Detectors initially evaluated in this program included miniature fission chambers, specialized self-powered neutron detectors (SPNDs), and specially developed commercial SPNDs. Results from this program provide important insights related to flux detector accuracy and resolution for subsequent ATR and CEA experiments and yield new flux data required for benchmarking models in the ATR Life Extension Program (LEP) Modeling Update Project.

  15. Fbis report. Science and technology: Economic review, September 19, 1995

    SciTech Connect (OSTI)

    1995-09-19

    ;Partial Contents: Germany: Braunschweig University Tests Organic Semiconductors; France: Ariane-5 Tests Suspended; First Tests in Euro-Russian RECORD Rocket Engine Program; France: Renault`s Multi-Model Assembly Line Presented; Germany: New High Speed Trains Under Development; France: Matra Test Drone, Missile Systems; France: Experimental Project for Automobile Recycling; Germany: Survey of Flexible Manufacturing Developments; Germany: Heinrich Hertz Institute Produces Polymer-Based Circuit; French Firms Introduce Computerized Control Room for Nuclear Plants; German Machine Tool Industry Calls for Information Technology Projects; Germany: R&D Achievements in Digital HDTV Reported; Hungary: Secondary Telecommunications Networks Described; EU: Mergers in Pharmaceutical Industry Reported; SGS-Thomson Business Performance Analyzed; Germany`s Siemens Invest Heavily in UK Semiconductor Plant.

  16. Experimental determination of the radial dose function of {sup 90}Sr/{sup 90}Y IVBT sources

    SciTech Connect (OSTI)

    Holmes, Shannon M.; DeWerd, Larry A.; Micka, John A.

    2006-09-15

    A series of measurements were undertaken using both high sensitivity radiochromic film and new lithium fluoride thermoluminescent dosimeters in a liquid water medium to define the radial dose function of {sup 90}Sr/{sup 90}Y beta emitting intravascular brachytherapy sources more accurately. These measurements of a single 5 French source pellet served to verify current Monte Carlo transport models and extrapolation chamber measurements of the radial dose function, thus providing the recommended independent published measurements for g(r) of these sources. A slight deviation in the published radial dose function at depth leads the authors to recommend that treatment planning be performed using updated g(r) values from current Monte Carlo transport models verified by measurements such as those shown in this investigation.

  17. Experimental power density distribution benchmark in the TRIGA Mark II reactor

    SciTech Connect (OSTI)

    Snoj, L.; Stancar, Z.; Radulovic, V.; Podvratnik, M.; Zerovnik, G.; Trkov, A.; Barbot, L.; Domergue, C.; Destouches, C.

    2012-07-01

    In order to improve the power calibration process and to benchmark the existing computational model of the TRIGA Mark II reactor at the Josef Stefan Inst. (JSI), a bilateral project was started as part of the agreement between the French Commissariat a l'energie atomique et aux energies alternatives (CEA) and the Ministry of higher education, science and technology of Slovenia. One of the objectives of the project was to analyze and improve the power calibration process of the JSI TRIGA reactor (procedural improvement and uncertainty reduction) by using absolutely calibrated CEA fission chambers (FCs). This is one of the few available power density distribution benchmarks for testing not only the fission rate distribution but also the absolute values of the fission rates. Our preliminary calculations indicate that the total experimental uncertainty of the measured reaction rate is sufficiently low that the experiments could be considered as benchmark experiments. (authors)

  18. Overview of the ARGOS X-ray framing camera for Laser MegaJoule

    SciTech Connect (OSTI)

    Trosseille, C. Aubert, D.; Auger, L.; Bazzoli, S.; Brunel, P.; Burillo, M.; Chollet, C.; Jasmin, S.; Maruenda, P.; Moreau, I.; Oudot, G.; Raimbourg, J.; Soullié, G.; Stemmler, P.; Zuber, C.; Beck, T.; Gazave, J.

    2014-11-15

    Commissariat à l’Énergie Atomique et aux Énergies Alternatives has developed the ARGOS X-ray framing camera to perform two-dimensional, high-timing resolution imaging of an imploding target on the French high-power laser facility Laser MegaJoule. The main features of this camera are: a microchannel plate gated X-ray detector, a spring-loaded CCD camera that maintains proximity focus in any orientation, and electronics packages that provide remotely-selectable high-voltages to modify the exposure-time of the camera. These components are integrated into an “air-box” that protects them from the harsh environmental conditions. A miniaturized X-ray generator is also part of the device for in situ self-testing purposes.

  19. High Density Fuel Development for Research Reactors

    SciTech Connect (OSTI)

    Daniel Wachs; Dennis Keiser; Mitchell Meyer; Douglas Burkes; Curtis Clark; Glenn Moore; Jan-Fong Jue; Totju Totev; Gerard Hofman; Tom Wiencek; Yeon So Kim; Jim Snelgrove

    2007-09-01

    An international effort to develop, qualify, and license high and very high density fuels has been underway for several years within the framework of multi-national RERTR programs. The current development status is the result of significant contributions from many laboratories, specifically CNEA in Argentina, AECL in Canada, CEA in France, TUM in Germany, KAERI in Korea, VNIIM, RDIPE, IPPE, NCCP and RIARR in Russia, INL, ANL and Y-12 in USA. These programs are mainly engaged with UMo dispersion fuels with densities from 6 to 8 gU/cm3 (high density fuel) and UMo monolithic fuel with density as high as 16 gU/cm3 (very high density fuel). This paper, mainly focused on the French & US programs, gives the status of high density UMo fuel development and perspectives on their qualification.

  20. The prospect of nuclear energy in Türkiye especially after Fukushima accident

    SciTech Connect (OSTI)

    Şahin, Sümer

    2014-09-30

    Türkiye considers since mid-50's to use nuclear electricity, but Government and bureaucracy have continuously postponed reactor construction. However, since 2010 the case has gained a real shape. Official agreement has been signed for the construction of 4 units of Russian VVER type reactors with installed power of 4×1200 MW{sub el}. It is expected that they will begin to deliver electricity early 20's. Further negotiations are being conducted with Japanese Mitsubashi and French AREVA. The target is to have nuclear electricity by 2023 at the 100{sup th} anniversary of Turkish Republic. Turkish Nuclear Energy Strategy aims; • Decrease country's dependency on foreign suppliers of energy sources • Provide fuel supply mix diversification • Utilization of environmentally friendly energy production technologies Possess advanced and prestigious power generation technologies.

  1. Radiant flash pyrolysis of biomass as a source of fuels and chemicals

    SciTech Connect (OSTI)

    Antal, M.J. Jr.; Hofman, L.; Moreira, J.R.

    1980-01-01

    Last year a team of US and French scientists using the Odeillo (France) 1MW/sub th/ solar furnace showed concentrated solar radiation to be an effective means for rapidly volatilizing biomass materials. The results of continuing research in the U.S. on radiant flash pyrolysis of biomass as a source of fluid fuels, industrial feedstocks and chemicals are described. Bench scale sources of intense, visible radiant energy have been used to simulate the concentrated solar flux available at the focus of solar towers. Windowed transport reactors are being developed, which act as cavity receivers for the focused radiant energy and provide a means for direct use of the radiation to rapidly pyrolyze the entering biomass. One of these reactors will be operated at the focus of the Georgia Tech 400kW/sub th/ solar furnace next August. Preliminary results from the bench scale reactor experiments, and plans for the Georgia Tech experiments are detailed.

  2. The DAFT/FADA survey. I.Photometric redshifts along lines of sight to clusters in the z=[0.4,0.9] interval

    SciTech Connect (OSTI)

    Guennou, L.; Adami, C.; Ulmer, M.P.; LeBrun, V.; Durret, F.; Johnston, D.; Ilbert, O.; Clowe, D.; Gavazzi, R.; Murphy, K.; Schrabback, T.; /Leiden Observ. /Fermilab

    2010-08-01

    As a contribution to the understanding of the dark energy concept, the Dark energy American French Team (DAFT, in French FADA) has started a large project to characterize statistically high redshift galaxy clusters, infer cosmological constraints from Weak Lensing Tomography, and understand biases relevant for constraining dark energy and cluster physics in future cluster and cosmological experiments. Aims. The purpose of this paper is to establish the basis of reference for the photo-z determination used in all our subsequent papers, including weak lensing tomography studies. This project is based on a sample of 91 high redshift (z {ge} 0.4), massive ({approx}> 3 x 10{sup 14} M{sub {circle_dot}}) clusters with existing HST imaging, for which we are presently performing complementary multi-wavelength imaging. This allows us in particular to estimate spectral types and determine accurate photometric redshifts for galaxies along the lines of sight to the first ten clusters for which all the required data are available down to a limit of I{sub AB} = 24./24.5 with the LePhare software. The accuracy in redshift is of the order of 0.05 for the range 0.2 {le} z {le} 1.5. We verified that the technique applied to obtain photometric redshifts works well by comparing our results to with previous works. In clusters, photo-z accuracy is degraded for bright absolute magnitudes and for the latest and earliest type galaxies. The photo-z accuracy also only slightly varies as a function of the spectral type for field galaxies. As a consequence, we find evidence for an environmental dependence of the photo-z accuracy, interpreted as the standard used Spectral Energy Distributions being not very well suited to cluster galaxies. Finally, we modeled the LCDCS 0504 mass with the strong arcs detected along this line of sight.

  3. Mobile Technology and Social Media in the Clinical Practice of Young Radiation Oncologists: Results of a Comprehensive Nationwide Cross-sectional Study

    SciTech Connect (OSTI)

    Bibault, Jean-Emmanuel; Leroy, Thomas; Blanchard, Pierre; Biau, Julian; Cervellera, Mathilde; Diaz, Olivia; Faivre, Jean Christophe; and others

    2014-09-01

    Purpose: Social media and mobile technology are transforming the way in which young physicians are learning and practicing medicine. The true impact of such technologies has yet to be evaluated. Methods and Materials: We performed a nationwide cross-sectional survey to better assess how young radiation oncologists used these technologies. An online survey was sent out between April 24, 2013, and June 1, 2013. All residents attending the 2013 radiation oncology French summer course were invited to complete the survey. Logistic regressions were performed to assess predictors of use of these tools in the hospital on various clinical endpoints. Results: In all, 131 of 140 (93.6%) French young radiation oncologists answered the survey. Of these individuals, 93% owned a smartphone and 32.8% owned a tablet. The majority (78.6%) of the residents owning a smartphone used it to work in their department. A total of 33.5% had more than 5 medical applications installed. Only 60.3% of the residents verified the validity of the apps that they used. In all, 82.9% of the residents had a social network account. Conclusions: Most of the residents in radiation oncology use their smartphone to work in their department for a wide variety of tasks. However, the residents do not consistently check the validity of the apps that they use. Residents also use social networks, with only a limited impact on their relationship with their patients. Overall, this study highlights the irruption and the risks of new technologies in the clinical practice and raises the question of a possible regulation of their use in the hospital.

  4. Quantitative comparison between PGNAA measurements and MCNP calculations in view of the characterization of radioactive wastes in Germany and France

    SciTech Connect (OSTI)

    Mauerhofer, E.; Havenith, A.; Kettler, J.; Carasco, C.; Payan, E.; Ma, J. L.; Perot, B.

    2013-04-19

    The Forschungszentrum Juelich GmbH (FZJ), together with the Aachen University Rheinisch-Westfaelische Technische Hochschule (RWTH) and the French Alternative Energies and Atomic Energy Commission (CEA Cadarache) are involved in a cooperation aiming at characterizing toxic and reactive elements in radioactive waste packages by means of Prompt Gamma Neutron Activation Analysis (PGNAA). The French and German waste management agencies have indeed defined acceptability limits concerning these elements in view of their projected geological repositories. A first measurement campaign was performed in the new Prompt Gamma Neutron Activation Analysis (PGNAA) facility called MEDINA, at FZJ, to assess the capture gamma-ray signatures of some elements of interest in large samples up to waste drums with a volume of 200 liter. MEDINA is the acronym for Multi Element Detection based on Instrumental Neutron Activation. This paper presents MCNP calculations of the MEDINA facility and quantitative comparison between measurement and simulation. Passive gamma-ray spectra acquired with a high purity germanium detector and calibration sources are used to qualify the numerical model of the crystal. Active PGNAA spectra of a sodium chloride sample measured with MEDINA then allow for qualifying the global numerical model of the measurement cell. Chlorine indeed constitutes a usual reference with reliable capture gamma-ray production data. The goal is to characterize the entire simulation protocol (geometrical model, nuclear data, and postprocessing tools) which will be used for current measurement interpretation, extrapolation of the performances to other types of waste packages or other applications, as well as for the study of future PGNAA facilities.

  5. HLW Return from France to Germany - 15 Years of Experience in Public Acceptance and Technical Aspects - 12149

    SciTech Connect (OSTI)

    Graf, Wilhelm

    2012-07-01

    Since in 1984 the national reprocessing concept was abandoned the reprocessing abroad was the only existing disposal route until 1994. With the amendment of the Atomic Energy Act in 2001 spent fuel management changed completely since from 1 June 2005 any delivery of spent fuel to reprocessing plants was prohibited and the direct disposal of spent fuel became mandatory. Until 2005 the total amount of spent fuel to be reprocessed abroad added up to 6080 t HM, 5309 t HM thereof in France. The waste generated from reprocessing - alternatively an equivalent amount of radioactive material - has to be returned to the country of origin according to the commercial contracts signed between the German utilities and COGEMA, now AREVA NC, in France and BNFL, now INS in UK. In addition the German and the French government exchanged notes with the obligation of both sides to enable and support the return of reprocessing residues or equivalents to Germany. The return of high active vitrified waste from La Hague to the interim storage facility at Gorleben was demanding from the technical view i. e. the cask design and the transport. Unfortunately the Gorleben area served as a target for nuclear opponents from the first transport in 1996 to the latest one in 2011. The protection against sabotage of the railway lines and mass protests needed highly improved security measures. In France and Germany special working forces and projects have been set up to cope with this extraordinary situation. A complex transport organization was established to involve all parties in line with the German and French requirements during transport. The last transport of vitrified residues from France has been completed successfully so far thus confirming the efficiency of the applied measures. Over 15 years there was and still is worldwide no comparable situation it is still unique. Summing up, the exceptional project handling challenge that resulted from the continuous anti-nuclear civil disobedience in Germany over the whole 15-year long project running time could be faced efficiently. It has to be concluded that despite of all problems the anti-nuclear activities have caused so far, all transports of vitrified HLW have always been completed successfully by adapting the commonly established safety, security and public acceptance measures to the special conditions and needs in Germany and coordinating the activities of all parties involved but at the expense of high costs for industry and government and a challenging operational complexity. Apart from an anticipatory project planning a good communication between all involved industrial parties and the French and the German government was the key to the effective management of such shipments and to minimize the radiological, economic, environmental, public and political impact. The future will show how efficiently the gained experience can be used for further return projects which are to be realized since no reprocessed waste has yet been returned from UK and neither the medium-level nor the low-level radioactive waste has been transferred from France to Germany. (author)

  6. The evaluation of an analytical protocol for the determination of substances in waste for hazard classification

    SciTech Connect (OSTI)

    Hennebert, Pierre; Papin, Arnaud; Padox, Jean-Marie; Hasebrouck, Benoît

    2013-07-15

    Highlights: • Knowledge of wastes in substances will be necessary to assess HP1–HP15 hazard properties. • A new analytical protocol is proposed for this and tested by two service laboratories on 32 samples. • Sixty-three percentage of the samples have a satisfactory analytical balance between 90% and 110%. • Eighty-four percentage of the samples were classified identically (Seveso Directive) for their hazardousness by the two laboratories. • The method, in progress, is being normalized in France and is be proposed to CEN. - Abstract: The classification of waste as hazardous could soon be assessed in Europe using largely the hazard properties of its constituents, according to the the Classification, Labelling and Packaging (CLP) regulation. Comprehensive knowledge of the component constituents of a given waste will therefore be necessary. An analytical protocol for determining waste composition is proposed, which includes using inductively coupled plasma (ICP) screening methods to identify major elements and gas chromatography/mass spectrometry (GC–MS) screening techniques to measure organic compounds. The method includes a gross or indicator measure of ‘pools’ of higher molecular weight organic substances that are taken to be less bioactive and less hazardous, and of unresolved ‘mass’ during the chromatography of volatile and semi-volatile compounds. The concentration of some elements and specific compounds that are linked to specific hazard properties and are subject to specific regulation (examples include: heavy metals, chromium(VI), cyanides, organo-halogens, and PCBs) are determined by classical quantitative analysis. To check the consistency of the analysis, the sum of the concentrations (including unresolved ‘pools’) should give a mass balance between 90% and 110%. Thirty-two laboratory samples comprising different industrial wastes (liquids and solids) were tested by two routine service laboratories, to give circa 7000 parameter results. Despite discrepancies in some parameters, a satisfactory sum of estimated or measured concentrations (analytical balance) of 90% was reached for 20 samples (63% of the overall total) during this first test exercise, with identified reasons for most of the unsatisfactory results. Regular use of this protocol (which is now included in the French legislation) has enabled service laboratories to reach a 90% mass balance for nearly all the solid samples tested, and most of liquid samples (difficulties were caused in some samples from polymers in solution and vegetable oil). The protocol is submitted to French and European normalization bodies (AFNOR and CEN) and further improvements are awaited.

  7. Thermal Behavior of Advanced UO{sub 2} Fuel at High Burnup

    SciTech Connect (OSTI)

    Muller, E.; Lambert, T.; Silberstein, K.; Therache, B.

    2007-07-01

    To improve the fuel performance, advanced UO{sub 2} products are developed to reduce significantly Pellet-Cladding Interaction and Fission Gas Release to increase high burnup safety margins on Light Water Reactors. To achieve the expected improvements, doping elements are currently used, to produce large grain viscoplastic UO{sub 2} fuel microstructures. In that scope, AREVA NP is conducting the qualification of a new UO{sub 2} fuel pellet obtained by optimum chromium oxide doping. To assess the fuel thermal performance, especially the fuel conductivity degradation with increasing burnup and also the kinetics of fission gas release under transient operating conditions, an instrumented in-pile experiment, called REMORA, has been developed by the CEA. One segment base irradiated for five cycles in a French EDF commercial PWR ({approx} 62 GWd/tM) was consequently re-instrumented with a fuel centerline thermocouple and an advanced pressure sensor. The design of this specific sensor is based on the counter-pressure principle and avoids any drift phenomenon due to nuclear irradiation. This rodlet was then irradiated in the GRIFFONOS rig of the Osiris experimental reactor at CEA Saclay. This device, located in the periphery of the core, is designed to perform test under conditions close to those prevailing in French PWR reactor. Power variations are carried out by translating the device relatively to the core. Self - powered neutron detectors are positioned in the loop in order to monitor the power the whole time of the irradiation. The re-irradiation of the REMORA experiment consisted of a stepped ramp to power in order to point out a potential degradation of the fuel thermal conductivity with increasing burnup. During the first part of the irradiation, most of the measurements were performed at low power in order to take into account the irradiation effects on UO{sub 2} thermal conductivity at high burnup in low range of temperature. The second part of the irradiation consisted in power cycling with one steady-state at several powers (290 W/cm and 360 W/cm) to assess both the thermal conductivity at higher temperature (until 1600 deg. C) and the fission gas release kinetic. This paper summarizes and discusses the main results assessed for this advanced UO{sub 2} fuel: on the one hand, the thermal performances indicate that the fuel thermal conductivity is similar to the one of the standard UO{sub 2} fuel type (the thermal conductivity damage under irradiation can be modelling alike) and, on the other hand, the test results show low fission gas release in comparison with UO{sub 2} standard fuel. (authors)

  8. Ocean thermal energy conversion: Historical highlights, status, and forecast

    SciTech Connect (OSTI)

    Dugger, G.L.; Avery, W.H.; Francis, E.J.; Richards, D.

    1983-07-01

    In 1881, d'Arsonval conceived the closed-Rankine-cycle ocean thermal energy conversion (OTEC) system in which a working fluid is vaporized by heat exchange with cold water drawn from a 700-1200 m depth. In 1930, Claude demonstrated an open-cycle process in Cuba. Surface water was flash-vaporized at 3 kPa to drive a turbine directly (no secondary working fluid) and then was condensed by direct contact with water drawn from a 700-m depth through a 1.6m-diam, 1.75-km-long cold-water pipe (CWP). From a delta T of 14/sup 0/C his undersized turbine generated 22 kW. In 1956 a French team designed a 3.5-MW (net) open-cycle plant for installation off Abidjan on the Ivory Coast of Africa and demonstrated the necessary CWP deployment. The at-sea demonstrations by Mini-OTEC and OTEC-1 and other recent advances in OTEC technology summarized herein represent great progress. All of the types of plants proposed for the DOE's PON program may be worthy of development; certainly work on a grazing plant is needed. Our estimates indicate that the U.S. goals established by Public Law 96-310 leading to 10 GW of OTEC power and energy product equivalents by 1999 are achievable, provided that adequate federal financial incentives are retained to assure the building of the first few plants.

  9. Ocean thermal energy conversion: a review

    SciTech Connect (OSTI)

    Yuen, P.C.

    1981-10-01

    The OTEC principle is discussed along with general system and cycle types, specific OTEC designs, OTEC applications, and the ocean thermal resource. The historic development of OTEC is briefly reviewed, and the status of French, Japanese, EUROCEAN, and US programs is assessed. US efforts are detailed and DOE's strategy outlined with OTEC-1 and Mini-OTEC information. Power system components of the more technically advanced closed-cycle OTEC concept are discussed. These include: heat exchangers, corrosion and biofouling countermeasures, working fluids, ammonia power systems, and on-platform seawater systems. Several open-cycle features are also discussed. A critical review is presented of the ocean engineering aspects of OTEC power systems. Major subsystems such as platform, cold water pipe, mooring system, dynamic positioning system, power transmission cable system are assessed for their relationships with the ocean environment and with each other. Nine available studies of OTEC costs are reviewed. Tentative comparisons are made between OTEC and traditional fuel costs, and OTEC products and markets are considered. Possible environmental and social effects of OTEC development are discussed. International, national, and local laws regulating OTEC plants and OTEC energy products are reviewed. Tax incentives, attitudes of the utilities, and additional legislative needs are considered. (LEW)

  10. Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies

    SciTech Connect (OSTI)

    Gourgiotis, A.; Isnard, H.; Aubert, M.; Dupont, E.; AlMahamid, I.; Cassette, P.; Panebianco, S.; Letourneau, A.; Chartier, F.; Tian, G.; Rao, L.; Lukens, W.

    2011-02-01

    The French Atomic Energy Commission has carried out several experiments including the mini-INCA (INcineration of Actinides) project for the study of minor-actinide transmutation processes in high intensity thermal neutron fluxes, in view of proposing solutions to reduce the radiotoxicity of long-lived nuclear wastes. In this context, a Cm sample enriched in {sup 248}Cm ({approx}97 %) was irradiated in thermal neutron flux at the High Flux Reactor (HFR) of the Laue-Langevin Institute (ILL). This work describes a quadrupole ICP-MS (ICP-QMS) analytical procedure for precise and accurate isotopic composition determination of Cm before sample irradiation and of Cm and Cf after sample irradiation. The factors that affect the accuracy and reproducibility of isotopic ratio measurements by ICP-QMS, such as peak centre correction, detector dead time, mass bias, abundance sensitivity and hydrides formation, instrumental background, and memory blank were carefully evaluated and corrected. Uncertainties of the isotopic ratios, taking into account internal precision of isotope ratio measurements, peak tailing, and hydrides formations ranged from 0.3% to 1.3%. This uncertainties range is quite acceptable for the nuclear data to be used in transmutation studies.

  11. Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly

    SciTech Connect (OSTI)

    Miller, Thomas Martin; Celik, Cihangir; McMahan, Kimberly L.; Lee, Yi-kang; Gagnier, Emmanuel; Authier, Nicolas; Piot, Jerome; Jacquet, Xavier; Rousseau, Guillaume; Reynolds, Kevin H.

    2015-09-01

    This benchmark experiment was conducted as a joint venture between the US Department of Energy (DOE) and the French Commissariat à l'Energie Atomique (CEA). Staff at the Oak Ridge National Laboratory (ORNL) in the US and the Centre de Valduc in France planned this experiment. The experiment was conducted on October 11, 2010 in the SILENE critical assembly facility at Valduc. Several other organizations contributed to this experiment and the subsequent evaluation, including CEA Saclay, Lawrence Livermore National Laboratory (LLNL), the Y-12 National Security Complex (NSC), Babcock International Group in the United Kingdom, and Los Alamos National Laboratory (LANL). The goal of this experiment was to measure neutron activation and thermoluminescent dosimeter (TLD) doses from a source similar to a fissile solution critical excursion. The resulting benchmark can be used for validation of computer codes and nuclear data libraries as required when performing analysis of criticality accident alarm systems (CAASs). A secondary goal of this experiment was to qualitatively test performance of two CAAS detectors similar to those currently and formerly in use in some US DOE facilities. The detectors tested were the CIDAS MkX and the Rocky Flats NCD-91. These detectors were being evaluated to determine whether they would alarm, so they were not expected to generate benchmark quality data.

  12. Optimization of a heterogeneous fast breeder reactor core with improved behavior during unprotected transients

    SciTech Connect (OSTI)

    Poumerouly, S.; Schmitt, D.; Massara, S.; Maliverney, B.

    2012-07-01

    Innovative Sodium-cooled Fast Reactors (SFRs) are currently being investigated by CEA, AREVA and EDF in the framework of a joint French collaboration, and the construction of a GEN IV prototype, ASTRID (Advanced Sodium Technical Reactor for Industrial Demonstration), is scheduled in the years 2020. Significant improvements are expected so as to improve the reactor safety: the goal is to achieve a robust safety demonstration of the mastering of the consequences of a Core Disruptive Accident (CDA), whether by means of prevention or mitigation features. In this framework, an innovative design was proposed by CEA in 2010. It aims at strongly reducing the sodium void effect, thereby improving the core behavior during unprotected loss of coolant transients. This design is strongly heterogeneous and includes, amongst others, a fertile plate, a sodium plenum associated with a B{sub 4}C upper blanket and a stepwise modulation of the fissile height of the core (onwards referred to as the 'diabolo shape'). In this paper, studies which were entirely carried out at EDF are presented: the full potential of this heterogeneous concept is thoroughly investigated using the SDDS methodology. (authors)

  13. Selecting a plutonium vitrification process

    SciTech Connect (OSTI)

    Jouan, A. [Centre d`Etudes de la Vallee du Rhone, Bagnols sur Ceze (France)

    1996-05-01

    Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO{sub 2} or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO{sub 2} mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

  14. Implementing Stakeholders' Access to Expertise: Experimenting on Nuclear Installations' Safety Cases - 12160

    SciTech Connect (OSTI)

    Gilli, Ludivine; Charron, Sylvie

    2012-07-01

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) led two pilot actions dealing with nuclear installations' safety cases. One concerned the periodical review of the French 900 MWe nuclear reactors, the other concerned the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of both these programs was to test ways for IRSN and a small number of stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the stakeholders to review future applications and provide valuable input. The test cases confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues, in particular the fact that most expertise reports were not public and the conflict that exists between the contrary demands of transparency and confidentiality of information. The test case also confirmed there are ways to further improvement of stakeholders' involvement. (authors)

  15. R and D in France and in Western Europe

    SciTech Connect (OSTI)

    Bastin, A.J.F. )

    1991-06-01

    This paper deals with worldwide electric utility R and D, but focuses on France first, and not on Western Europe as a whole. Apart from the fact that the R and D of European utilities hardly show a homogeneous set, there are four basic reasons. To begin with, France represents roughly 20 percent of Western Europe by itself. Germany, now extended to the late DDR, is the only country to have a larger share. Second, Electricite de France (EDF) is the largest electric utility worldwide, with annual sales of about 410 TWh. Third, EDF has consistently shown one of the lowest electricity prices: as an average .44 FF par kWh (about $.08 per kWh) which comes up on comparing the 410 TWh sales with a 165 GFF turnover. Beyond these three points, which are more or less permanent, it appears that both EDF and its R and D division have been stable over the last three years. So the French power system is the largest subsystem in Western Europe where a single well-defined R and D policy can be described and assessed; this is what the authors are going to do now.

  16. Graphite Waste Tank Cleanup and Decontamination under the Marcoule UP1 D and D Program - 13166

    SciTech Connect (OSTI)

    Thomasset, Philippe [AREVA D and D BU, Marcoule (France)] [AREVA D and D BU, Marcoule (France); Chabeuf, Jean-Michel [AREVA D and D BU, La Hague (France)] [AREVA D and D BU, La Hague (France); Thiebaut, Valerie [CEA/DEN/DAPD/CPUP, Marcoule (France)] [CEA/DEN/DAPD/CPUP, Marcoule (France); Chambon, Frederic [AREVA FEDERAL SERVICES, Columbia, MD (United States)] [AREVA FEDERAL SERVICES, Columbia, MD (United States)

    2013-07-01

    The UP1 plant in Marcoule reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. During more than 40 years, the decladding operations produced thousands of tons of processed waste, mainly magnesium and graphite fragments. In the absence of a French repository for the graphite waste, the graphite sludge content of the storage pits had to be retrieved and transferred into a newer and safer pit. After an extensive R and D program, the equipment and process necessary for retrieval operations were designed, built and tested. The innovative process is mainly based on the use of two pumps (one to capture and the other one to transfer the sludge) working one after the other and a robotic arm mounted on a telescopic mast. A dedicated process was also set up for the removal of the biggest fragments. The retrieval of the most irradiating fragments was a challenge. Today, the first pit is totally empty and its stainless steel walls have been decontaminated using gels. In the second pit, the sludge retrieval and transfer operations have been almost completed. Most of the non-pumpable graphite fragments has been removed and transferred to a new storage pit. After more than 6 years of operations in sludge retrieval, a lot of experience was acquired from which important 'lessons learned' could be shared. (authors)

  17. Main results of Phenix final core physics tests

    SciTech Connect (OSTI)

    Pascal, V.; Prulhiere, G.; Vanier, M.; Fontaine, B.

    2012-07-01

    The French sodium cooled fast reactor Phenix was shut down in 2009 after 35 years of operation. Before decommissioning a final set of tests was performed. This paper focuses on the following core physics tests: - measurement of control rod reactivity worth by several methods (sub-critical, critical, rod-drop methods), - control rod shifting during a full power operation state, - measurement of individual subassembly reactivity worth (fresh and burned fuel and fertile, sodium hole), - simulation of a gas bubble crossing the core. The control rod measurement test has shown some discrepancies between the different measurement methods, mainly for the rod bank worth. Considering a macroscopic parameter (the reactivity loss estimation), NSMM method seems to produce the better results. The control rod shifting test has highlighted the impact of the spatial effects generated by control rods movements over the power map. These spatial effects, known as shadowing effects, can modify up to 15% the individual control rod worth. The tests concerning individual subassembly worth and gas bubble have permit to evaluate the impact of local perturbations on the reactivity. All these tests can be considered as successful and the ability of the European neutronic code for fast reactors, ERANOS 2.2, to reproduce complex and atypical configuration has been demonstrated by good agreement between measured and computed values. (authors)

  18. Evolution of the surface area of a snow layer

    SciTech Connect (OSTI)

    Hanot, L.; Domine, F.

    1999-12-01

    Atmospheric trace gases can partition between the atmosphere and the snow surface. Because snow has a large surface-to-volume ratio, an important interaction potential between ice and atmospheric trace gases exists. Quantifying this partitioning requires the knowledge of the surface area (SA) of snow. Eleven samples were taken from a 50 cm thick snow fall at Col de Porte, near Grenoble (French Alps) between January 20 and February 4, 1998. Fresh snow and 3, 8, and 15-day-old snow were sampled at three different depths. Surface hoar, formed after the fall, was also sampled. Air and surface snow temperature, snow density, and snow fall rate were measured. Snow temperature always remained below freezing. Snow SA was measured using methane adsorption at 77.15 K. Values ranged from 2.25 m{sup 2}/g for fresh snow to 0.25 m{sup 2}/g for surface hoar and surface snow after 15 days. These values are much too high to be explained by the macroscopic aspect of snow crystals, and microstructures such as small rime droplets must have been present. Large decrease in SA with time were observed. The first meter of snowpack had a total surface area of about 50,000 m{sup 2} per m{sup 2} of ground. Reduction in SA will lead to the emission of adsorbed species by the snowpack, with possible considerable increase in atmospheric concentrations.

  19. Selection of materials for sodium fast reactor steam generators

    SciTech Connect (OSTI)

    Dubiez-Le Goff, S.; Garnier, S.; Gelineau, O.; Dalle, F.; Blat-Yrieix, M.; Augem, J. M.

    2012-07-01

    Sodium Fast Reactor (SFR) is considered in France as the most mature technology of the different Generation IV systems. In the short-term the designing work is focused on the identification of the potential tracks to demonstrate licensing capability, availability, in-service inspection capability and economical performance. In that frame materials selection for the major components, as the steam generator, is a particularly key point managed within a French Research and Development program launched by AREVA, CEA and EDF. The choice of the material for the steam generator is indeed complex because various aspects shall be considered like mechanical and thermal properties at high temperature, interaction with sodium on one side and water and steam on the other side, resistance to wastage, procurement, fabrication, weldability and ability for inspection and in-situ intervention. The following relevant options are evaluated: the modified 9Cr1Mo ferritic-martensitic grade and the Alloy 800 austenitic grade. The objective of this paper is to assess for both candidates their abilities to reach the current SFR needs regarding material design data, from AFCEN RCC-MRx Code in particular, compatibility with environments and manufacturability. (authors)

  20. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT165: AREA 25 AND 26 DRY WELL AND WASH DOWN AREAS, NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    BECHTEL NEVADA

    2005-12-01

    This Closure Report (CR) documents the closure activities for Corrective Action Unit (CAU) 165, Area 25 and 26 Dry Well and Washdown Areas, according to the Federal Facility Agreement and Consent Order (FFACO) of 1996. CAU 165 consists of 8 Corrective Action Sites (CASs) located in Areas 25 and 26 of the Nevada Test Site (NTS). The NTS is located approximately 105 kilometers (65 miles) northwest of Las Vegas, nevada. Site closure activities were performed according to the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 165. CAU 165 consists of the following CASs: (1) CAS 25-07-06, Train Decontamination Area; (2) CAS 25-07-07, Vehicle Washdown; (3) CAS 25-20-01, Lab Drain Dry Well; (4) CAS 25-47-01, Reservoir and French Drain; (5) CAS 25-51-02, Drywell; (6) CAS 25-59-01, Septic System; (7) CAS 26-07-01, Vehicle Washdown Station; and (8) CAS 26-59-01, Septic System. CAU 165, Area 25 and 26 Dry Well and Washdown Areas, consists of eight CASs located in Areas 25 and 26 of the NTS. The approved closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls.

  1. Carbon dioxide, hydrographic, and chemical data obtained in the South Pacific Ocean (WOCE Sections P16A/P17A, P17E/P19S, and P19C, R/V Knorr, October 1992--April 1993)

    SciTech Connect (OSTI)

    Rubin, S.; Goddard, J.G.; Chipman, D.W.; Takahashi, Taro; Sutherland, S.C.; Reid, J.L.; Swift, J.H.; Talley, L.D.

    1998-06-01

    This data documentation discusses the procedures and methods used to measure total carbon dioxide concentration (TCO{sub 2}) and partial pressure of CO{sub 2} (pCO{sub 2}) in discrete water samples collected during three expeditions of the Research Vessel (R/V) Knorr in the South Pacific Ocean. Conducted as part of the World Ocean Circulation Experiment (WOCE), the first cruise (WOCE Section P16A/P17A) began in Papeete, Tahiti, French Polynesia, on October 6, 1992, and returned to Papeete on November 25, 1992. The second cruise (WOCE Section P17E/P19S) began in Papeete on December 4, 1992, and finished in Punta Arenas, Chile, on January 22, 1993. The third expedition (WOCE Section P19C) started in Punta Arenas, on February 22 and finished in Panama City, Panama, on April 13, 1993. During the three expeditions, 422 hydrographic stations were occupied. Hydrographic and chemical measurements made along WOCE Sections P16A/P17A, P17E/P19S, and P19C included pressure, temperature, salinity, and oxygen [measured by conductivity, temperature, and depth (CTD) sensor], as well as discrete measurements of salinity, oxygen, phosphate, nitrate, nitrite, silicate, chlorofluorocarbons (CFC-11, CFC-12), TCO{sub 2}, and pCO{sub 2} measured at 4 and 20 C. In addition, potential temperatures were calculated from the measured variables.

  2. Elemental characterization of LL-MA radioactive waste packages with the associated particle technique

    SciTech Connect (OSTI)

    Perot, B.; Carasco, C.; Toure, M.; El Kanawati, W.; Eleon, C.

    2011-07-01

    The French Alternative Energies and Atomic Energy Commission (CEA) and National Radioactive Waste Management Agency (ANDRA) are conducting an R and D program to improve the characterization of long-lived and medium activity (LL-MA) radioactive waste packages with analytical methods and with non-destructive nuclear measurements. This paper concerns fast neutron interrogation with the associated particle technique (APT), which brings 3D information about the waste material composition. The characterization of volume elements filled with iron, water, aluminium, and PVC in bituminized and fibre concrete LL-MA waste packages has been investigated with MCNP [1] and MODAR data analysis software [2]. APT provides usable information about major elements presents in the volumes of interest. However, neutron scattering on hydrogen nuclei spreads the tagged neutron beam out of the targeted volume towards surrounding materials, reducing spatial selectivity. Simulation shows that small less than 1 L targets can be characterised up to the half-radius of a 225 L bituminized drum, the matrix of which is very rich in hydrogen. Deeper characterization in concrete is possible but limited by counting statistics due to photon attenuation in this dense matrix and, unless large inspection volumes are considered, by the lack of spatial selectivity of the tagged neutron beam due to neutron scattering. (authors)

  3. Low energy electrons and swift ion track structure in PADC

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Fromm, Michel; Quinto, Michele A.; Weck, Philippe F.; Champion, Christophe

    2015-05-27

    The current work aims at providing an accurate description of the ion track-structure in poly-allyl dyglycol carbonate (PADC) by using an up-to-date Monte-Carlo code-called TILDA-V (a French acronym for Transport d’Ions Lourds Dans l’Aqua & Vivo). In this simulation the ion track-structure in PADC is mainly described in terms of ejected electrons with a particular attention done to the Low Energy Electrons (LEEs). After a brief reminder of the most important channels through which LEEs are prone to break a chemical bond, we will report on the simulated energetic distributions of LEEs along an ion track in PADC for particularmore » incident energies located on both sides of the Bragg-peak position. Lastly, based on the rare data dealing with LEEs interaction with polymers or organic molecules, we will emphasise the role played by the LEEs in the formation of a latent track in PADC, and more particularly the one played by the sub-ionization electrons.« less

  4. Low energy electrons and swift ion track structure in PADC

    SciTech Connect (OSTI)

    Fromm, Michel; Quinto, Michele A.; Weck, Philippe F.; Champion, Christophe

    2015-05-27

    The current work aims at providing an accurate description of the ion track-structure in poly-allyl dyglycol carbonate (PADC) by using an up-to-date Monte-Carlo code-called TILDA-V (a French acronym for Transport d’Ions Lourds Dans l’Aqua & Vivo). In this simulation the ion track-structure in PADC is mainly described in terms of ejected electrons with a particular attention done to the Low Energy Electrons (LEEs). After a brief reminder of the most important channels through which LEEs are prone to break a chemical bond, we will report on the simulated energetic distributions of LEEs along an ion track in PADC for particular incident energies located on both sides of the Bragg-peak position. Lastly, based on the rare data dealing with LEEs interaction with polymers or organic molecules, we will emphasise the role played by the LEEs in the formation of a latent track in PADC, and more particularly the one played by the sub-ionization electrons.

  5. Low energy electrons and swift ion track structure in PADC

    SciTech Connect (OSTI)

    Fromm, Michel; Quinto, Michele A.; Weck, Philippe F.; Champion, Christophe

    2015-05-27

    The current work aims at providing an accurate description of the ion track-structure in poly-allyl dyglycol carbonate (PADC) by using an up-to-date Monte-Carlo code-called TILDA-V (a French acronym for Transport dIons Lourds Dans lAqua & Vivo). In this simulation the ion track-structure in PADC is mainly described in terms of ejected electrons with a particular attention done to the Low Energy Electrons (LEEs). After a brief reminder of the most important channels through which LEEs are prone to break a chemical bond, we will report on the simulated energetic distributions of LEEs along an ion track in PADC for particular incident energies located on both sides of the Bragg-peak position. Lastly, based on the rare data dealing with LEEs interaction with polymers or organic molecules, we will emphasise the role played by the LEEs in the formation of a latent track in PADC, and more particularly the one played by the sub-ionization electrons.

  6. Treatment of Uranium and Plutonium Solutions Generated in the Atalante Facility, France - 12004

    SciTech Connect (OSTI)

    Lagrave, Herve

    2012-07-01

    The Atalante complex operated by the French Alternative Energies and Atomic Energy Commission (CEA) at the Rhone Valley Research Center consolidates research programs on actinide chemistry, especially separation chemistry, processing for recycling spent fuel, and fabrication of actinide targets for innovative concepts in future nuclear systems. The design of future systems (Generation IV reactors, material recycling) will increase the uranium and plutonium flows in the facility, making it important to anticipate the stepped-up activity and provide Atalante with equipment dedicated to processing these solutions to obtain a mixed uranium-plutonium oxide that will be stored pending reuse. Ongoing studies for integral recycling of the actinides have highlighted the need for reserving equipment to produce actinides mixed oxide powder and also minor actinides bearing oxide for R and D purpose. To meet this double objective a new shielded line should be built in the facility and should be operational 6 years after go decision. The main functions of the new unit would be to receive, concentrate and store solutions, purify them, ensure group conversion of actinides and conversion of excess uranium. This new unit will be constructed in a completely refurbished building devoted to subcritical and safe geometry of the process equipments. (author)

  7. Sol-gel optical coatings for lasers, 3

    SciTech Connect (OSTI)

    Floch, H.G.; Belleville, P.F.; Priotton, J.J.; Pegon, P.M.; Dijonneau, C.S.; Guerain, J.

    1995-12-01

    The planned megajoule-class neodymium-glass laser system will be the world`s largest. The proposed CEL-V design, based on the use of 240 beams, will use 50--150 times more optical material than did Phebus. Almost 10,000 m{sup 2} of coated area are required for optical coatings; this is a factor of almost 500 increase over Phebus. Lens, flashlamp, blastshield, harmonic converter, debris shield, window and cavity-end mirror coatings by the sol-gel process represent >96% of the entire coated area. The remaining <4% are high-rejection-ratio polarizers, pick-off cavity mirrors and transport mirrors. Cost estimates show that, for coating deposition, the sol-gel technique provides considerable saving compared to the more conventional e-beam deposition technique. Highly reflective and polarizing sol-gel-derived optical coatings have been prepared and tested for the proposed French megajoule neodymium-glass laser. Laser damage studies are reported here.

  8. Sol-gel optical coatings for lasers, 2

    SciTech Connect (OSTI)

    Floch, H.G.; Belleville, P.F.; Priotton, J.J.; Pegon, P.M.; Dijonneau, C.S.; Guerain, J.

    1995-11-01

    There are three basic types of antireflective (AR) coatings. The first is a single-layer coating in which the coating index is equal to the square root of the index of the substrate, assuming air is the external medium. The second type is a system of two or more layers of different indexes. The third type is a graded-index system, where the index is uniformly and continuously graded from the substrate to the external medium. Low reflection ranges from narrow for the single-layer to broad for the graded-layer and multilayered with a large number of layers. Four types of sol-gel AR coatings have been developed at CEL-V. They are based on single-layer or multilayer designs. They consist mainly of amorphous silica in the polymeric and/or colloidal state, combined in certain cases with other metallic oxides, binders, fillers, hydrophobic and lubricating agents, and adhesion promoters. These antireflective sol-gel-derived optical coatings have been prepared and tested for the proposed French megajoule neodymium-glass laser.

  9. Effectiveness of 700{degrees}C thermal treatment on primary water stress corrosion sensitivity of Alloy 600 steam generator tubes: Laboratory tests and in field experience

    SciTech Connect (OSTI)

    Cattant, F.; Keroulas, F. de; Garriga-Majo, D.; Todeschini, P.; Van Duysen, J.C.

    1992-12-31

    In France, the steam generators of some 900 MWe reactors, and of all the 1 300 MWe reactors in service are equipped with heat treated Alloy 600 tubes. The purpose of the heat treatment, performed at 700{degrees}C, is to relieve the residual stresses. Generally, it also increases the SCC resistance of the alloy. A laboratory study has been carried out in order to gain a better understanding of the metallurgical factors influencing the PWSCC resistance of Alloy 600 after heat treatment. It has been shown that there are two kinds of tubes for which the heat treatment does not produce a microstructure having a potentially high resistance to SCC: tubes with a high carbon content (over 0.032%) or tubes mill-annealed at high temperatures and heavily cold-worked by the straightening. The analysis of the behaviour of french steam generators reveals that the heat treatment generally had the expected beneficial effect. However, the early cracking in service of some treated tubes led EDF (national power company) to proceed with removals. The majority of the cracked pulled-out tubes exhibit microstructures having a potentially high PWSCC sensibility in laboratory tests. It has been shown that these microstructures can be correlated to a high carbon content.

  10. Analysis of the cracking behavior of Alloy 600 RVH penetrations. Part 1: Stress analysis and K computation

    SciTech Connect (OSTI)

    Bhandari, S.; Vagner, J.; Garriga-Majo, D.; Amzallag, C.; Faidy, C.

    1996-12-01

    The study presented here concerns the analysis of crack propagation behavior in the Alloy 600 RVH penetrations used in the French 900 and 1300 MWe PWR series. The damage mechanism identified is clearly the SCC in primary water environment. Consequently the analysis presented here is based on: (1) the stress analysis carried out on the RVH penetrations, (2) the SCC model developed in primary water environment and at the operating temperatures, and (3) the fracture mechanics concepts. The different steps involved in the study are: (1) Evaluation of the stress state for the case of the peripheral configuration of RVH penetrations; the case retained here is that of a conic tube with stress analysis conducted using multi-pass welding. (2) Computation of the influence functions (IF) for a polynomial stress distribution in case of a tube of Ri/t ratio (internal diameter/thickness) corresponding to that of an RVH penetration. (3) Establishment of a propagation law based on study and review of data available in the literature. (4) Conduction of a parametric study of crack propagation using several initial defects. (5) Analysis of crack propagation of defects observed in various reactors and comparison with measured propagation rates. This paper (Part 1) deals with the first two steps namely Stress Analysis and K Computation.

  11. Improvement in Thermal-Ionization Mass Spectrometry (TIMS) using Total Flash Evaporation (TFE) method for lanthanides isotope ratio measurements in transmutation targets

    SciTech Connect (OSTI)

    Mialle, S.; Gourgiotis, A.; Aubert, M.; Stadelmann, G.; Gautier, C.; Isnard, H.

    2011-07-01

    The experiments involved in the PHENIX french nuclear reactor to obtain precise and accurate data on the total capture cross sections of the heavy isotopes and fission products require isotopic ratios measurements with uncertainty of a few per mil. These accurate isotopic ratio measurements are performed with mass spectrometer equipped with multi-collector system. The major difficulty for the analyses of these actinides and fission products is the low quantity of the initial powder enclosed in steel container (3 to 5 mg) and the very low quantities of products formed (several {mu}g) after irradiation. Specific analytical developments are performed by Thermal Ionization Mass Spectrometry (TIMS) to be able to analyse several nanograms of elements with this technique. A specific method of acquisition named Total Flash Evaporation was adapted in this study in the case of lanthanide measurements for quantity deposited on the filament in the order of 2 ng and applied on irradiated fuel. To validate the analytical approach and discuss about the accuracy of the data, the isotopic ratios obtained by TIMS are compared with other mass spectrometric techniques such as Multiple-Collector Inductively Coupled Plasma Mass Spectrometer (MC-ICPMS). (authors)

  12. Confirmation of the SCA-2 locus as an alternative locus for dominantly inherited spinocerebellar ataxias and refinement of the candidate region

    SciTech Connect (OSTI)

    Lopes-Cendes, I.; Rouleau, G.A. ); Andermann, E.; Andermann, F. ); Attig, E. ); Bosch, S.; Wagner, M. )

    1994-05-01

    The autosomal dominant spinocerebellar ataxias (SCAs) are a clinically heterogeneous group of neurodegenerative diseases. To date, two SCA loci have been identified - one locus (SCA-1) on the short arm of chromosome 6 and the second locus (SCA-2) on the long arm of chromosome 12. The authors have studied two large kindreds from different ethnic backgrounds, segregating an autosomal dominant form of SCA. A total of 207 living individuals, including 50 affected, were examined, and blood was collected. Linkage analysis was performed using anonymous DNA markers which flank the two previously described loci. The results demonstrate that the two kindreds, one Austrian-Canadian and one French-Canadian, are linked to SCA-2 (chromosome 12q). Multipoint linkage analysis places the SCA-2 locus within a region of approximately 16 cM between the microsatellites D12S58 and D12S84/D12S105 (odds ratio 2,371:1 in favor of this position). The authors show that the SCA-2 locus is not a private gene and represents an alternative SCA locus. 51 refs., 2 figs., 2 tabs.

  13. Analysis of the April 10, 1987 UF{sub 6} release test

    SciTech Connect (OSTI)

    Just, R.A.; Bloom, S.G.

    1989-02-01

    A series of controlled uranium hexafluoride (UF{sub 6}) release tests are being conducted at a CESTA (a French government agency) test site near Bordeaux, France. The results of the first release test are documented in Analysis of the April 18,1986 UF{sub 6}, Release Test. The first UF{sub 6} release test was designated as a qualification test. The primary objective of this test was to provide the information required to obtain approval for a series of UF{sub 6} release tests. As a result of the experimental difficulties and the compromises associated with obtaining the required qualification data, results from the first release test were used primarily to qualify the site and to plan for additional release tests. Utilizing the lessons learned during the first release test it was possible to conduct a very successful second release test. The second release test was conducted on April 10, 1987. The data collected during the two UF{sub 6} release tests at the CESTA test site are the only known information on UF{sub 6} releases that can be used to evaluate the accuracy of the UF{sub 6} dispersion model. In this report the data collected during the April 10, 1987 release test will be evaluated and compared with the predictions of the UF{sub 6}, dispersion model.

  14. Analysis of the April 10, 1987 UF[sub 6] release test

    SciTech Connect (OSTI)

    Just, R.A.; Bloom, S.G.

    1989-02-01

    A series of controlled uranium hexafluoride (UF[sub 6]) release tests are being conducted at a CESTA (a French government agency) test site near Bordeaux, France. The results of the first release test are documented in Analysis of the April 18,1986 UF[sub 6], Release Test. The first UF[sub 6] release test was designated as a qualification test. The primary objective of this test was to provide the information required to obtain approval for a series of UF[sub 6] release tests. As a result of the experimental difficulties and the compromises associated with obtaining the required qualification data, results from the first release test were used primarily to qualify the site and to plan for additional release tests. Utilizing the lessons learned during the first release test it was possible to conduct a very successful second release test. The second release test was conducted on April 10, 1987. The data collected during the two UF[sub 6] release tests at the CESTA test site are the only known information on UF[sub 6] releases that can be used to evaluate the accuracy of the UF[sub 6] dispersion model. In this report the data collected during the April 10, 1987 release test will be evaluated and compared with the predictions of the UF[sub 6], dispersion model.

  15. The IPHI Project

    SciTech Connect (OSTI)

    Ferdinand, Robin; Beauvais, Pierre-Yves

    2005-06-08

    High Power Proton Accelerators (HPPAs) are studied for several projects based on high-flux neutron sources driven by proton or deuteron beams. Since the front end is considered as the most critical part of such accelerators, the two French national research agencies CEA and CNRS decided to collaborate in 1997 to study and build a High-Intensity Proton Injector (IPHI). The main objective of this project is to master the complex technologies used and the concepts of manufacturing and controlling the HPPAs. Recently, a collaboration agreement was signed with CERN and led to some evolutions in the design and in the schedule. The IPHI design current was maintained at 100 mA in Continuous Wave mode. This choice should allow to produce a high reliability beam at reduced intensity (typically 30 mA) tending to fulfill the Accelerator Driven System requirements. The output energy of the Radio Frequency Quadrupole (RFQ), was reduced from 5 to 3 MeV, allowing then the adjunction and the test, in pulsed operation of a chopper line developed by CERN for the Superconducting Proton Linac (SPL). In a final step, the IPHI RFQ and the chopper line should become parts of the SPL injector. In this paper, the IPHI project and the recent evolutions are reported together with the construction and operation schedule.

  16. BNL ALARA Center: ALARA Notes, No. 9

    SciTech Connect (OSTI)

    Khan, T.A.; Xie, J.W.; Beckman, M.C.

    1994-02-01

    This issue of the Brookhaven National Laboratory`s Alara Notes includes the agenda for the Third International Workshop on ALARA and specific instructions on the use of the on-line fax-on-demand service provided by BNL. Other topics included in this issue are: (1) A discussion of low-level discharges from Canadian nuclear plants, (2) Safety issues at French nuclear plants, (3) Acoustic emission as a means of leak detection, (4) Replacement of steam generators at Doel-3, Beaznau, and North Anna-1, (5) Remote handling equipment at Bruce, (6) EPRI`s low level waste program, (7) Radiation protection during concrete repairs at Savannah River, (8) Reactor vessel stud removal/repair at Comanche Peak-1, (9) Rework of reactor coolant pump motors, (10) Restoration of service water at North Anna-1 and -2, (11) Steam generator tubing problems at Mihama-1, (12) Full system decontamination at Indian Point-2, (13) Chemical decontamination at Browns Ferry-2, and (14) Inspection methodolody in France and Japan.

  17. Elf well turns 90/degree/- and stays there

    SciTech Connect (OSTI)

    Astier, B.; Jourdan, A.; Baron, G.

    1981-01-01

    As part of an intensive research program, the French association IFP (Institut Francais du Petrole) and Elf-Aquitaine have drilled the first European horizontal hole. The well was spudded conventionally and then deviated so that its final path was horizontal, 2,198 ft (670 m) below the surface. More than 330 ft (100 m) were drilled between 89/degree/ and 92/degree/ of inclination. The project started with reservoir engineering studies aimed at demonstrating, on mathematical models, the effectiveness of a horizontal drain hole in areas where hydrocarbon recovery is poor or unsatisfactory, due to gas or water coning, poor flooding patterns, intersection of fractures in tight but fractured producing formations, or other causes. This technique has a number of potential applications both in and out of the oil industry. The well was drilled in 44 days. Horizontal displacement was 2,192 ft (668 m) with a total vertical depth of 2,198 ft (670 m). To accomplish this, it was necessary to drill 3,563 ft (1,086 m) of hole. In the 17/one-half/-in. hole, 73/4-in. drill collars and 5-in. heavy weight drill pipe were run above the bent sub and the monel collar. While reaming the hole, the drill string was rotated conventionally, one near bit and one stabilizer (30 ft above) being included in the string.

  18. Overall results of and lessons learned from the IAEA CRP on sodium natural circulation test performed during the Phenix end-of-life experiments

    SciTech Connect (OSTI)

    Monti, S.; Toti, A.; Tenchine, D.; Pialla, D.

    2012-07-01

    In 2007, the International Atomic Energy Agency (IAEA) launched the Coordinated Research Project (CRP) 'Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the Phenix End-of-Life Experiments'. The overall purpose of the CRP, performed within the framework of the IAEA programme in support of innovative fast reactor technology development and deployment, is to improve the Member States' analytical capabilities in the various fields of research and design of sodium-cooled fast reactors through data and codes verification and validation. In particular the CRP, taking advantage of the End-of-Life set of experiments performed before the final shut-down of the French prototype fast breeder power reactor Phenix, aims at improving fast reactor simulation methods and design capabilities in the field of temperature and power distribution evaluation, as well as of the analysis of sodium natural circulation phenomena. The paper presents the overall results of the CRP, including blind calculations and post-test and sensitivity analyses carried out by the CRP participants, as well as lessons learned and recommendations for further future implementations to resolve open issues. (authors)

  19. Direct Experimental Evaluation of the Grain Boundaries Gas Content in PWR fuels: New Insight and Perspective of the ADAGIO Technique

    SciTech Connect (OSTI)

    Pontillon, Y.; Noirot, J.; Caillot, L.

    2007-07-01

    Over the last decades, many analytical experiments (in-pile and out-of-pile) have underlined the active role of the inter-granular gases on the global fuel transient behavior under accidental conditions such as RIA and/or LOCA. In parallel, the improvement of fission gas release modeling in nuclear fuel performance codes needs direct experimental determination/validation regarding the local gas distribution inside the fuel sample. In this context, an experimental program, called 'ADAGIO' (French acronym for Discriminating Analysis of Accumulation of Inter-granular and Occluded Gas), has been initiated through a joint action of CEA, EDF and AREVA NP in order to develop a new device/technique for quantitative and direct measurement of local fission gas distribution within an irradiated fuel pellet. ADAGIO technique is based on the fact that fission gas inventory (intra and inter-granular parts) can be distinguished by controlled fuel oxidation, since grain boundaries oxidize faster than the bulk. The purpose of the current paper is to present both the methodology and the associated results of the ADAGIO program performed at CEA. It has been divided into two main parts: (i) feasibility (UO{sub 2} and MOX fuels), (ii) application on high burn up UO{sub 2} fuel. (authors)

  20. Fibre optique à la maison en Pays de Gex et de Bellegarde

    ScienceCinema (OSTI)

    None

    2011-10-06

    Le Syndicat Intercommunal d’Electricité de l’Ain(SIEA) déploie un réseau FTTH (Fiber To The Home) de fibres optiques dans le département de l’Ain vers l’ensemble des habitations. Le déploiement sur la zone pilote du Pays de Gex et du Bassin Bellegardien arrive dans la phase terminale vers les habitations. Le SIEA présentera ses activités, l’état du développement du réseau, les implications d’une connexion fibre optique et les procédures d’abonnement. La présentation sera donnée en Français. -------------------------------------------------------------------------------------------------------------------------------Public conference "Optical fiber To The Home in Pays de Gex et de Bellegarde" Michel Chanel et Jean Paul Goy (SIEA) Wednesday, 19th May at 11.30 hrs., Council Chamber, CERN The ‘’ Syndicat Intercommunal d’Electricité de l’Ain’’(SIEA) is deploying an optical fiber network FTTH (Fiber To The Home) in the Ain department towards the ensemble of houses. The installation on the pilot areas of Pays de Gex and Bassin Bellegardien is arriving in the phase of connecting houses. The SIEA will show its activities, the state of the network development, the implications of an optical fiber connection and the contract procedures. The presentation will be given in French

  1. Pretreatment status report on the identification and evaluation of alternative processes. Milestone Report No. C064

    SciTech Connect (OSTI)

    Sutherland, D.G.; Brothers, A.J.; Beary, M.M.; Nicholson, G.A.

    1993-09-01

    The purpose of this report is to support the development and demonstration of a pretreatment system that will (1) destroy organic materials and ferrocyanide in tank wastes so that the wastes can be stored safely, (2) separate the high-activity and low-activity fractions, (3) remove radionuclides and remove or destroy hazardous chemicals in LLW as necessary to meet waste form feed requirements, (4) support development and demonstration of vitrification technology by providing representative feeds to the bench-scale glass melter, (5) support full-scale HLW vitrification operations, including near-term operation, by providing feed that meets specifications, and (6) design and develop pretreatment processes that accomplish the above objectives and ensure compliance with environmental regulations. This report is a presentation of candidate technologies for pretreatment of Hanford Site tank waste. Included are descriptions of studies by the Pacific Northwest Laboratory of Battelle Memorial Institute; Science Applications International Corporation, an independent consultant; BNFL, Inc. representing British technologies; Numatec, representing French technologies; and brief accounts of other relevant activities.

  2. Polyvalent fuel treatment facility (TCP): shearing and dissolution of used fuel at La Hague facility

    SciTech Connect (OSTI)

    Brueziere, J.; Tribout-Maurizi, A.; Durand, L.; Bertrand, N.

    2013-07-01

    Although many used nuclear fuel types have already been recycled, recycling plants are generally optimized for Light Water Reactor (LWR) UO{sub x} fuel. Benefits of used fuel recycling are consequently restricted to those fuels, with only limited capacity for the others like LWR MOX, Fast Reactor (FR) MOX or Research and Test Reactor (RTR) fuel. In order to recycle diverse fuel types, an innovative and polyvalent shearing and dissolving cell is planned to be put in operation in about 10 years at AREVA's La Hague recycling plant. This installation, called TCP (French acronym for polyvalent fuel treatment) will benefit from AREVA's industrial feedback, while taking part in the next steps towards a fast reactor fuel cycle development using innovative treatment solutions. Feasibility studies and R/Development trials on dissolution and shearing are currently ongoing. This new installation will allow AREVA to propose new services to its customers, in particular in term of MOX fuel, Research Test Reactors fuel and Fast Reactor fuel treatment. (authors)

  3. Chooz A, First Pressurized Water Reactor to be Dismantled in France - 13445

    SciTech Connect (OSTI)

    Boucau, Joseph; Mirabella, C.; Nilsson, Lennart; Kreitman, Paul J.; Obert, Estelle

    2013-07-01

    Nine commercial nuclear power plants have been permanently shut down in France to date, of which the Chooz A plant underwent an extensive decommissioning and dismantling program. Chooz Nuclear Power Station is located in the municipality of Chooz, Ardennes region, in the northeast part of France. Chooz B1 and B2 are 1,500 megawatt electric (MWe) pressurized water reactors (PWRs) currently in operation. Chooz A, a 305 MWe PWR implanted in two caves within a hill, began operations in 1967 and closed in 1991, and will now become the first PWR in France to be fully dismantled. EDF CIDEN (Engineering Center for Dismantling and Environment) has awarded Westinghouse a contract for the dismantling of its Chooz A reactor vessel (RV). The project began in January 2010. Westinghouse is leading the project in a consortium with Nuvia France. The project scope includes overall project management, conditioning of the reactor vessel (RV) head, RV and RV internals segmentation, reactor nozzle cutting for lifting the RV out of the pit and seal it afterwards, dismantling of the RV thermal insulation, ALARA (As Low As Reasonably Achievable) forecast to ensure acceptable doses for the personnel, complementary vacuum cleaner to catch the chips during the segmentation work, needs and facilities, waste characterization and packaging, civil work modifications, licensing documentation. The RV and RV internals will be segmented based on the mechanical cutting technology that Westinghouse applied successfully for more than 13 years. The segmentation activities cover the cutting and packaging plan, tooling design and qualification, personnel training and site implementation. Since Chooz A is located inside two caves, the project will involve waste transportation from the reactor cave through long galleries to the waste buffer area. The project will end after the entire dismantling work is completed, and the waste storage is outside the caves and ready to be shipped either to the ANDRA (French National Radioactive Waste Management Agency) waste disposal facilities - (for low-level waste [LLW] and very low-level waste [VLLW], which are considered short lived) - or to the EDF Interim Storage Facility planned to be built on another site - (for low- and intermediate-level waste [LILW], which is considered long lived). The project has started with a detailed conceptual study that determines the step-by-step approach for dismantling the reactor and eventually supplying the packed containers ready for final disposal. All technical reports must be verified and approved by EDF and the French Nuclear Safety Authority before receiving the authorization to start the site work. The detailed conceptual study has been completed to date and equipment design and manufacturing is ongoing. This paper will present the conceptual design of the reactor internals segmentation and packaging process that will be implemented at Chooz A, including the planning, methodology, equipment, waste management, and packaging strategy. (authors)

  4. Macrophysical and optical properties of midlatitude cirrus clouds from four ground-based lidars and collocated CALIOP observations

    SciTech Connect (OSTI)

    Dupont, Jean-Charles; Haeffelin, M.; Morille, Y.; Noel, V.; Keckhut, P.; Winker, D.; Comstock, Jennifer M.; Chervet, P.; Roblin, A.

    2010-05-27

    Ground-based lidar and CALIOP datasets gathered over four mid-latitude sites, two US and two French sites, are used to evaluate the consistency of cloud macrophysical and optical property climatologies that can be derived by such datasets. The consistency in average cloud height (both base and top height) between the CALIOP and ground datasets ranges from -0.4km to +0.5km. The cloud geometrical thickness distributions vary significantly between the different datasets, due in part to the original vertical resolutions of the lidar profiles. Average cloud geometrical thicknesses vary from 1.2 to 1.9km, i.e. by more than 50%. Cloud optical thickness distributions in subvisible, semi-transparent and moderate intervals differ by more than 50% between ground and space-based datasets. The cirrus clouds with 2 optical thickness below 0.1 (not included in historical cloud climatologies) represent 30-50% of the non-opaque cirrus class. The differences in average cloud base altitude between ground and CALIOP datasets of 0.0-0.1 km, 0.0-0.2 km and 0.0-0.2 km can be attributed to irregular sampling of seasonal variations in the ground-based data, to day-night differences in detection capabilities by CALIOP, and to the restriction to situations without low-level clouds in ground-based data, respectively. The cloud geometrical thicknesses are not affected by irregular sampling of seasonal variations in the ground-based data, while up to 0.0-0.2 km and 0.1-0.3 km differences can be attributed to day-night differences in detection capabilities by CALIOP, and to the restriction to situations without lowlevel clouds in ground-based data, respectively.

  5. A preliminary investigation of the structure of southern Yucca Flat, Massachusetts Mountain, and CP basin, Nevada Test Site, Nevada, based on geophysical modeling.

    SciTech Connect (OSTI)

    Geoffrey A. Phelps; Leigh Justet; Barry C. Moring, and Carter W. Roberts

    2006-03-17

    New gravity and magnetic data collected in the vicinity of Massachusetts Mountain and CP basin (Nevada Test Site, NV) provides a more complex view of the structural relationships present in the vicinity of CP basin than previous geologic models, helps define the position and extent of structures in southern Yucca Flat and CP basin, and better constrains the configuration of the basement structure separating CP basin and Frenchman Flat. The density and gravity modeling indicates that CP basin is a shallow, oval-shaped basin which trends north-northeast and contains ~800 m of basin-filling rocks and sediment at its deepest point in the northeast. CP basin is separated from the deeper Frenchman Flat basin by a subsurface ridge that may represent a Tertiary erosion surface at the top of the Paleozoic strata. The magnetic modeling indicates that the Cane Spring fault appears to merge with faults in northwest Massachusetts Mountain, rather than cut through to Yucca Flat basin and that the basin is downed-dropped relative to Massachusetts Mountain. The magnetic modeling indicates volcanic units within Yucca Flat basin are down-dropped on the west and supports the interpretations of Phelps and KcKee (1999). The magnetic data indicate that the only faults that appear to be through-going from Yucca Flat into either Frenchman Flat or CP basin are the faults that bound the CP hogback. In general, the north-trending faults present along the length of Yucca Flat bend, merge, and disappear before reaching CP hogback and Massachusetts Mountain or French Peak.

  6. Hydrological conditions at the 317/319 Area at Argonne National Laboratory

    SciTech Connect (OSTI)

    Patton, T.L.; Pearl, R.H.; Tsai, S.Y.

    1990-08-01

    This study examined the hydrological conditions of the glacial till underlying the 317/319 Area at Argonne National Laboratory (ANL) near Lemont, Illinois. The study's purpose was to review and summarize hydrological data collected by ANL's Environment, Safety, and Health Department and to characterize, based on these data, the groundwater movement and migration of potential contaminants in the area. Recommendations for further study have been made based on the findings of this review. The 317/319 Area is located between Meridian Road and the southern border of ANL. The 317 Area was commissioned in the late 1940s for the temporary storage of radioactive waste. Low- and high-level solid radioactive waste is stored in partially buried concrete vaults. Low-level radioactive waste awaiting shipment for off-site disposal is stored in aboveground steel bins north of the vaults. The 319 Area is an inactive landfill, located east of the 317 Area that was used for the disposal of general refuse, demolition debris, and laboratory equipment. Fluorescent light bulbs, chemical containers, and suspect waste were also placed in the landfill. Liquid chemical wastes were disposed of at each site in gravel-filled trenches called French drains.'' The 317/319 Area is underlain by a silty clay glacial till. Dolomite bedrock underlies the till at an average depth of about 19.5m. Organic contaminants and radionuclides have been detected in groundwater samples from wells completed in the till. Fractures in the clay as well as sand and gravel lenses present in the till could permit these contaminants to migrate downward to the dolomite aquifer. At the time of this report, no chemical quality analyses had been made on groundwater samples from the dolomite. The study found that existing information about subsurface characteristics at the site is inadequate to identify potential pathways for contaminant migration. 14 refs., 13 figs., 6 tabs.

  7. Hydrological conditions at the 800 Area at Argonne National Laboratory

    SciTech Connect (OSTI)

    Patton, T.L.; Pearl, R.H.; Tsai, S.Y.

    1990-08-01

    This study examined the hydrological conditions of the glacial till underlying the 800 Area sanitary landfill at Argonne National Laboratory (ANL) near Lemont, Illinois. The study's purpose was to review and summarize hydrological data collected by ANL's Environment, Safety, and Health Department and to characterize, on the basis of these data, the groundwater movement and migration of potential contaminants in the area. Recommendations for further study have been made based on the findings of this review. The 800 Area landfill is located on the western edge of ANL, just south of Westgate Road. It has been in operation since 1966 and has been used for the disposal of sanitary, general refuse. From 1969 through 1978, however, substantial quantities of liquid organic and inorganic wastes were disposed of in a French drain'' at the northeast corner of the landfill. The 800 Area landfill is underlain by a silty clay glacial till. Dolomite bedrock underlies the till at an average depth of about 45.6 m. Trace levels of organic contaminants and radionuclides have been detected in groundwater samples from wells completed in the till. Fractures in the clay as well as sand and gravel lenses present in the till could permit these contaminants to migrate downward to the dolomite aquifer. When this report was prepared, no chemical quality analysis have been made on groundwater samples from the dolomite. The study found that existing information about subsurface characteristics at the site is inadequate to identify potential pathways for contaminant migration. Recommended actions include installation of five new well clusters and one background well, thorough record-keeping, sample collection and analysis during borehole drilling, slug testing to measure hydraulic conductivity, topographic mapping, continued monitoring of groundwater levels and quality, and monitoring of the unsaturated zone. 17 refs., 13 figs., 4 tabs.

  8. Integrated Pilot Plant for a Large Cold Crucible Induction Melter

    SciTech Connect (OSTI)

    Do Quang, R.; Jensen, A.; Prod'homme, A.; Fatoux, R.; Lacombe, J.

    2002-02-26

    COGEMA has been vitrifying high-level liquid waste produced during nuclear fuel reprocessing on an industrial scale for over 20 years, with two main objectives: containment of the long lived fission products and reduction of the final volume of waste. Research performed by the French Atomic Energy Commission (CEA) in the 1950s led to the selection of borosilicate glass as the most suitable containment matrix for waste from spent nuclear fuel and to the development of the induction melter technology. This was followed by the commissioning of the Marcoule Vitrification Facility (AVM) in 1978. The process was implemented at a larger scale in the late 1980s in the R7 and T7 facilities of the La Hague reprocessing plant. COGEMA facilities have produced more than 11,000 high level glass canisters, representing more than 4,500 metric tons of glass and 4.5 billion curies. To further improve the performance of the vitrification lines in the R7 and T7 facilities, the CEA and COGEMA have been developing the Cold Crucible Melter (CCM) technology since the 1980s. This technology benefits from the 20 years of COGEMA HLW vitrification experience and ensures a virtually unlimited equipment service life and extensive flexibility in dealing with different types of waste. The high specific power directly transferred by induction to the melt allows high operating temperatures without any impact on the process equipment. In addition, the mechanical stirring of the melter significantly reduces operating constraints. COGEMA is already providing the CCM technology to international customers for nuclear and non-nuclear applications and plans to implement it in the La Hague vitrification plant for the vitrification of highly concentrated and corrosive solutions produced by uranium/molybdenum fuel reprocessing. The paper presents the CCM project that led to the building and start-up of this evolutionary and flexible pilot plant. It also describes the plant's technical characteristics and reports commissioning results.

  9. Non-US electrodynamic launchers research and development

    SciTech Connect (OSTI)

    Parker, J.V.; Batteh, J.H.; Greig, J.R.; Keefer, D.; McNab, I.R.; Zabar, Z.

    1994-11-01

    Electrodynamic launcher research and development work of scientists outside the United States is analyzed and assessed by six internationally recognized US experts in the field of electromagnetic and electrothermal launchers. The assessment covers five broad technology areas: (1) Experimental railguns; (2) Railgun theory and design; (3) Induction launchers; (4) Electrothermal guns; (5) Energy storage and power supplies. The overall conclusion is that non-US work on electrodynamic launchers is maturing rapidly after a relatively late start in many countries. No foreign program challenges the US efforts in scope, but it is evident that the United States may be surpassed in some technologies within the next few years. Until recently, published Russian work focused on hypervelocity for research purposes. Within the last two years, large facilities have been described where military-oriented development has been underway since the mid-1980s. Financial support for these large facilities appears to have collapsed, leaving no effective effort to develop practical launchers for military or civilian applications. Electrodynamic launcher research in Europe is making rapid progress by focusing on a single application, tactical launchers for the military. Four major laboratories, in Britain, France, Germany, and the Netherlands, are working on this problem. Though narrower in scope than the US effort, the European work enjoys a continuity of support that has accelerated its progress. The next decade will see the deployment of electrodynamic launcher technology, probably in the form of an electrothermal-chemical upgrade for an existing gun system. The time scale for deployment of electromagnetic launchers is entirely dependent on the level of research-and-development effort. If resources remain limited, the advantage will lie with cooperative efforts that have reasonably stable funding such as the present French-German program.

  10. Rocky Flats Neutron Detector Testing at Valduc, France

    SciTech Connect (OSTI)

    Kim, S S; Dulik, G M

    2011-01-03

    Recent program requirements of the US Department of Energy/NNSA have led to a need for a criticality accident alarm system to be installed at a newly activated facility. The Criticality Safety Group of the Lawrence Livermore National Laboratory (LLNL) was able to recover and store for possible future use approximately 200 neutron criticality detectors and 20 master alarm panels from the former Rocky Flats Plant in Golden, Colorado when the plant was closed. The Criticality Safety Group participated in a facility analysis and evaluation, the engineering design and review process, as well as the refurbishment, testing, and recalibration of the Rocky Flats criticality alarm system equipment to be used in the new facility. In order to demonstrate the functionality and survivability of the neutron detectors to the effects of an actual criticality accident, neutron detector testing was performed at the French CEA Valduc SILENE reactor from October 7 to October 19, 2010. The neutron detectors were exposed to three criticality events or pulses generated by the SILENE reactor. The first excursion was performed with a bare or unshielded reactor, and the second excursion was made with a lead shielded/reflected reactor, and the third excursion with a polyethylene reflected core. These tests of the Rocky Flats neutron detectors were performed as a part of the 2010 Criticality Accident Alarm System Benchmark Measurements at the SILENE Reactor. The principal investigators for this series of experiments were Thomas M. Miller and John C. Wagner of the Oak Ridge National Laboratory, with Nicolas Authier and Nathalie Baclet of CEA Valduc. Several other organizations were also represented, including the Y-12 National Security Complex, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, CEA Saclay, and Babcock International Group.

  11. Radioluminescent lighting technology

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    The glow-in-the-dark stereotype that characterizes the popular image of nuclear materials is not accidental. When the French scientist, Henri Becquerel, first discovered radioactivity in 1896, he was interested in luminescence. Radioluminescence, the production of light from a mixture of energetic and passive materials, is probably the oldest practical application of the unstable nucleus. Tritium-based radioluminescent lighting, in spite of the biologically favorable character of the gaseous tritium isotope, was included in the general tightening of environmental and safety regulations. Tritium light manufacturers would have to meet two fundamental conditions: (1) The benefit clearly outweighed the risk, to the extent that even the perceived risk of a skeptical public would be overcome. (2) The need was significant enough that the customer/user would be willing and able to afford the cost of regulation that was imposed both in the manufacture, use and eventual disposal of nuclear materials. In 1981, researchers at Oak Ridge National Laboratory were investigating larger radioluminescent applications using byproduct nuclear material such as krypton-85, as well as tritium. By 1982, it appeared that large source, (100 Curies or more) tritium gas tube, lights might be useful for marking runways and drop zones for military operations and perhaps even special civilian aviation applications. The successful development of this idea depended on making the light bright enough and demonstrating that large gas tube sources could be used and maintained safely in the environment. This successful DOE program is now in the process of being completed and closed-out. Working closely with the tritium light industry, State governments and other Federal agencies, the basic program goals have been achieved. This is a detailed report of what they have learned, proven, and discovered. 91 refs., 29 figs., 5 tabs. (JF)

  12. The Full Scale Seal Experiment - A Seal Industrial Prototype for Cigeo - 13106

    SciTech Connect (OSTI)

    Lebon, P.; Bosgiraud, J.M.; Foin, R.; Armand, G.

    2013-07-01

    The Full Scale Seal (FSS) Experiment is one of various experiments implemented by Andra, within the frame of the Cigeo (the French Deep Geological Repository) Project development, to demonstrate the technical construction feasibility and performance of seals to be constructed, at time of Repository components (shafts, ramps, drifts, disposal vaults) progressive closure. FSS is built inside a drift model fabricated on surface for the purpose. Prior to the scale 1:1 seal construction test, various design tasks are scheduled. They include the engineering work on the drift model to make it fit with the experimental needs, on the various work sequences anticipated for the swelling clay core emplacement and the concrete containment plugs construction, on the specialized handling tools (and installation equipment) manufactured and delivered for the purpose, and of course on the various swelling clay materials and low pH (below 11) concrete formulations developed for the application. The engineering of the 'seal-as-built' commissioning means (tools and methodology) must also be dealt with. The FSS construction experiment is a technological demonstrator, thus it is not focused on the phenomenological survey (and by consequence, on the performance and behaviour forecast). As such, no hydration (forced or natural) is planned. However, the FSS implementation (in particular via the construction and commissioning activities carried out) is a key milestone in view of comforting phenomenological extrapolation in time and scale. The FSS experiment also allows for qualifying the commissioning methods of a real sealing system in the Repository, as built, at time of industrial operations. (authors)

  13. Fertility and Pregnancy Outcome After Abdominal Irradiation That Included or Excluded the Pelvis in Childhood Tumor Survivors

    SciTech Connect (OSTI)

    Sudour, Helene; Chastagner, Pascal; Claude, Line; Desandes, Emmanuel; Klein, Marc; Carrie, Christian; Bernier, Valerie

    2010-03-01

    Purpose: To evaluate fertility after abdominal and/or pelvic irradiation in long-term female survivors. Methods and Materials: Puberty and pregnancy outcome were analyzed in female survivors of childhood cancer (aged <18 years) treated with abdominal and/or pelvic radiotherapy (RT) at one of two French centers (Nancy and Lyon) between 1975 and 2004. Data were obtained from medical records and questionnaires sent to the women. Results: A total of 84 patients who had received abdominal and/or pelvic RT during childhood and were alive and aged more than 18 years at the time of the study made up the study population. Of the 57 female survivors treated with abdominal RT that excluded the pelvis, 52 (91%) progressed normally through puberty and 23 (40%) had at least one recorded pregnancy. Of the 27 patients treated with pelvic RT, only 10 (37%) progressed normally through puberty and 5 (19%) had at least one recorded pregnancy. Twenty-two women (seventeen of whom were treated with pelvic RT) had certain subfertility. A total of 50 births occurred in 28 women, with one baby dying at birth; one miscarriage also occurred. There was a high prevalence of prematurity and low birth weight but not of congenital malformations. Conclusions: Fertility can be preserved in patients who undergo abdominal RT that excludes the pelvis, taking into account the other treatments (e.g., chemotherapy with alkylating agents) are taken into account. When RT includes the pelvis, fertility is frequently impaired and women can have difficulty conceiving. Nevertheless, pregnancies can occur in some of these women. The most important factor that endangers a successful pregnancy after RT is the total dose received by the ovaries and uterus. This radiation dose has to be systematically recorded to improve our ability to follow up patients.

  14. Second Malignant Neoplasms in Digestive Organs After Childhood Cancer: A Cohort-Nested Case-Control Study

    SciTech Connect (OSTI)

    Tukenova, Markhaba; Diallo, Ibrahima; Anderson, Harald; Hawkins, Mike; Garwicz, Stanislaw; Sankila, Risto; El Fayech, Chiraz; Winter, Dave; Rubino, Carole; Adjadj, Elisabeth; Haddy, Nadia; Oberlin, Odile; Moller, Torgil; Langmark, Froydis; and others

    2012-03-01

    Purpose: Cancers of the digestive system constitute a major risk for childhood cancer survivors treated with radiotherapy once they reach adulthood. The aim of this study was to determine therapy-related risk factors for the development of a second malignancy in the digestive organs (SMDO) after a childhood cancer. Methods and Materials: Among 4,568 2-year survivors of a childhood solid cancer diagnosed before 17 years of age at eight French and British centers, and among 25,120 patients diagnosed as having a malignant neoplasm before the age of 20 years, whose data were extracted from the Nordic Cancer Registries, we matched 58 case patients (41 men and 17 women) of SMDO and 167 controls, in their respective cohort, for sex, age at first cancer, calendar year of occurrence of the first cancer, and duration of follow-up. The radiation dose received at the site of each second malignancy and at the corresponding site of its matched control was estimated. Results: The risk of developing a SMDO was 9.7-fold higher in relation to the general populations in France and the United Kingdom. In the case-control study, a strong dose-response relationship was estimated, compared with that in survivors who had not received radiotherapy; the odds ratio was 5.2 (95% CI, 1.7-16.0) for local radiation doses between 10 and 29 Gy and 9.6 (95% CI, 2.6-35.2) for doses equal to or greater than 30 Gy. Chemotherapy was also found to increase the risk of developing SMDO. Conclusions: This study confirms that childhood cancer treatments strongly increase the risk of SMDO, which occur only after a very long latency period.

  15. CloudSat as a Global Radar Calibrator

    SciTech Connect (OSTI)

    Protat, Alain; Bouniol, Dominique; O'Connor, E. J.; Baltink, Henk K.; Verlinde, J.; Widener, Kevin B.

    2011-03-01

    The calibration of the CloudSat spaceborne cloud radar has been thoroughly assessed using very accurate internal link budgets before launch, comparisons with predicted ocean surface backscatter at 94 GHz, direct comparisons with airborne cloud radars, and statistical comparisons with ground-based cloud radars at different locations of the world. It is believed that the calibration of CloudSat is accurate to within 0.5 to 1 dB. In the present paper it is shown that an approach similar to that used for the statistical comparisons with ground-based radars can now be adopted the other way around to calibrate other ground-based or airborne radars against CloudSat and / or detect anomalies in long time series of ground-based radar measurements, provided that the calibration of CloudSat is followed up closely (which is the case). The power of using CloudSat as a Global Radar Calibrator is demonstrated using the Atmospheric Radiation Measurement cloud radar data taken at Barrow, Alaska, the cloud radar data from the Cabauw site, The Netherlands, and airborne Doppler cloud radar measurements taken along the CloudSat track in the Arctic by the RASTA (Radar SysTem Airborne) cloud radar installed in the French ATR-42 aircraft for the first time. It is found that the Barrow radar data in 2008 are calibrated too high by 9.8 dB, while the Cabauw radar data in 2008 are calibrated too low by 8.0 dB. The calibration of the RASTA airborne cloud radar using direct comparisons with CloudSat agrees well with the expected gains and losses due to the change in configuration which required verification of the RASTA calibration.

  16. MO-D-16A-01: International Day of Medical Physics

    SciTech Connect (OSTI)

    Cheung, K; Damilakis, J

    2014-06-15

    International Organization for Medical Physics (IOMP) which represents medical physicists in more than 80 countries decided to celebrate 7th November, birth date of the Polish and naturalized-French physicist Marie Sklodowska-Curie, as International Day of Medical Physics (IDMP). The main purpose of the initiative is to raise the visibility and awareness of medical physicist in the global community, to introduce ourselves to the general public, and bring a message to the community that a group of health professionals, the medical physicists are there to help the patients and other health professionals. First celebration was done in 2013 and now IDMP will be celebrated every year. The theme of IDMP will be different each year. The theme for 2013 was Radiation exposure from medical procedures, ask the Medical Physicist. The inaugural event was celebrated in 23 countries and the amount of attention gained was remarkable. Main IDMP events were held in Poland, birthplace of Marie Curie, and France, workplace of Marie Curie. This year IOMP celebrates the 2nd IDMP and theme will be Looking into the body-Advancement in Imaging through Medical Physics to draw attention to the profound contributions Medical Physics has made to the use of ionizing and non-ionizing radiation for the imaging of human body. A number of countries have informed about events that they are going to organize on IDMP. This gives wide attention to medical physics globally. AAPM is a major and important member of IOMP. It is hoped that AAPM will join in organizing activities. Learning Objectives: To learn about International Day of Medical Physics To become familiar with how first IDMP was celebrated in 2013 and learning achieved To understand on future plans for IDMPs.

  17. Book review of Dragonfly Genera of the New World. An Illustrated and Annotated Key to the Anisoptera. Garrison, R.W., N. Von Ellenrieder and J.A. Louton, Johns Hopkins Univ. Press, Baltimore, MD. xi+368 pp. Hardback, ISBN 0-8018-8446-2

    SciTech Connect (OSTI)

    Cannings, R.A.

    2007-03-15

    This superb book is the most important reference on the Order Odonata to appear since the 1999 publication of Philip Corbet's monumental work on the behavior and ecology of Odonata. In the context of specimen identification and faunistics, it is the most significant contribution in decades, for it opens a new door to the most diverse and least known dragonfly fauna on Earth, that of the Neotropical Region. The book treats the genera of all the New World dragonflies, but while the Nearctic Anisoptera (at least north of the Mexican border) is extensively summarized in many taxonomic and identification manuals (e.g., Needham et al. 2000), the Neotropical fauna remains rather poorly known. Much of it still is undescribed and taxonomic syntheses are few and far between. This is partly because of its huge diversity, the remoteness of much of the region, and the relative scarcity of specimens in collections. As T. W. Donnelly (2006) noted in a recent review of this book, the New World tropics have always been a challenge to biologists in many disciplines because the region was first colonized by the Spanish and Portuguese who largely lacked the tradition of natural history studies characteristic of the British, French, Dutch and Germans in Africa, India or Southeast Asia. In South America there simply was no F. C. Fraser to write an equivalent to his three volumes on the Odonata in The Fauna of British India. Borror (1945) was an early and wonderful resource for deciphering the genera of the large family Libellulidae in the Americas. Calvert's hard-to-find contributions on the Odonata (1902-1908) in the Biologia Centrali-Americana helped students of the Central American fauna; the updated equivalent by Foerster (2001) for Mesoamerican genera is also important. But as far as syntheses and overviews, that's about all there was - until now.

  18. Monotoring of mangrove ecosystem in relation with exploration and production activities

    SciTech Connect (OSTI)

    Alamsyah, C.; Dwistiadi, D.

    1996-11-01

    From Indonesia`s initial 13 million hectares of mangrove forests, presently only 2.6 million hectares remains which must be certainly protected. Mangrove swamps are of considerable ecological importance not only because of their use as spawning and feeding grounds for a many variety of fish and shrimps but also of economical importance and last but not least as coastal protection. In such a sensitive ecosystem, i.e. in the mangrove swamp area of Mahakam Delta in East Kalimantan, Indonesia, TOTAL Indonesie, an affiliate of the French oil company {open_quotes}TOTAL{close_quotes} and one of the production sharing contractors of PERTAMINA, the Indonesian owned state oil company, has undertaken its E&P operations since 1974. Realizing the sensitivity of the mangrove area, TOTAL Indonesie has undertaken continuous monitoring of the environment as part of its Environmental Management System. This monitoring is very important not only to measure the impact to the mangrove ecosystem in particular due to TOTAL Indonesie activities but also as a feed back for the environmental management. Physicochemical and biological aspects of the environment are monitored and various measurements are taken covering: (1) Hydrology and hydrodynamics of the water streams i.e. the water quality, productivity and flow characteristic of the region (2) Sedimentation and biodegradation (3) The influence of accidental and chronic pollution mangrove ecosystem (3) Sensitivity of the mangroves. The above monitoring has led to the conclusion that after more than 20 years of operation, there has significant adverse impact to the mangrove ecosystem by the exploration and production activities of Indonesie.

  19. Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

    SciTech Connect (OSTI)

    Seidensticker, R.W.

    1987-01-01

    The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

  20. Electricity storage using a thermal storage scheme

    SciTech Connect (OSTI)

    White, Alexander

    2015-01-22

    The increasing use of renewable energy technologies for electricity generation, many of which have an unpredictably intermittent nature, will inevitably lead to a greater demand for large-scale electricity storage schemes. For example, the expanding fraction of electricity produced by wind turbines will require either backup or storage capacity to cover extended periods of wind lull. This paper describes a recently proposed storage scheme, referred to here as Pumped Thermal Storage (PTS), and which is based on “sensible heat” storage in large thermal reservoirs. During the charging phase, the system effectively operates as a high temperature-ratio heat pump, extracting heat from a cold reservoir and delivering heat to a hot one. In the discharge phase the processes are reversed and it operates as a heat engine. The round-trip efficiency is limited only by process irreversibilities (as opposed to Second Law limitations on the coefficient of performance and the thermal efficiency of the heat pump and heat engine respectively). PTS is currently being developed in both France and England. In both cases, the schemes operate on the Joule-Brayton (gas turbine) cycle, using argon as the working fluid. However, the French scheme proposes the use of turbomachinery for compression and expansion, whereas for that being developed in England reciprocating devices are proposed. The current paper focuses on the impact of the various process irreversibilities on the thermodynamic round-trip efficiency of the scheme. Consideration is given to compression and expansion losses and pressure losses (in pipe-work, valves and thermal reservoirs); heat transfer related irreversibility in the thermal reservoirs is discussed but not included in the analysis. Results are presented demonstrating how the various loss parameters and operating conditions influence the overall performance.

  1. Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312

    SciTech Connect (OSTI)

    Fournel, B.; Barre, Y.; Lepeytre, C.; Peycelon, H.; Grandjean, A.; Prevost, T.; Valery, J.F.; Shilova, E.; Viel, P.

    2012-07-01

    Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

  2. The Phenix ultimate natural convection test

    SciTech Connect (OSTI)

    Gauthe, P.; Pialla, D.; Tenchine, D.; Vasile, A.; Rochwerger, D.

    2012-07-01

    The French sodium cooled fast reactor Phenix was shut down in 2009 after 35 years of operation. Before decommissioning, a final set of tests were performed by the CEA during 9 months. Several topics were involved such as thermal hydraulics, core physics and fuel behaviour. Among these ultimate experiments, two thermal hydraulic tests were performed: an asymmetrical test consisting in a trip of one secondary pump and a natural convection test in the primary circuit. Recognizing the unique opportunity offered by these Phenix ultimate tests, IAEA decided in 2007 to launch a Coordinated Research Project (CRP) devoted to benchmarking analyses with system codes on the Phenix natural convection test. One objective of the natural convection test in Phenix reactor is the assessment of the CATHARE system code for safety studies on future and advanced sodium cooled fast reactors. The aim of this paper is to describe this test, which was performed on June 22-23, 2009, and the associated benchmark specifications for the CRP work. The paper reminds briefly the Phenix reactor with the main physical parameters and the instrumentation used during the natural convection test. After that, the test scenario is described: - initial state at a power of 120 MWth, - test beginning resulting from a manual dry out of the two steam generators, - manual scram, - manual trip on the three primary pumps without back-up by pony motors, - setting and development of natural convection in the primary circuit, in a first phase without significant heat sink in the secondary circuits and in a second phase with significant heat sink in the secondary circuits, by opening the casing of steam generators to create an efficient heat sink, by air natural circulation in the steam generators casing. The benchmark case ends after this second phase, which corresponds to the experimental test duration of nearly 7 hours. The paper presents also the benchmark specifications data supplied by the CEA to all participants of this CRP in order to perform calculations (core, primary circuit, primary pumps, IHX, shutdown system, operating parameters, test scenario and real test conditions). Finally, main test results and analyses are presented including the evolution of the core and of the heat exchangers inlet and outlet temperatures, and some local temperature measurements. The natural convection has been easily set up in the pool type reactor Phenix with different boundary conditions at the secondary side, with or without heat sink. The data obtained during this unique test represent some very useful and precious results for the development of SFR in a wide range of thematic such as numerical methods dedicated to thermal-hydraulics safety analyses (system codes, CFD codes and coupling system and CFD codes) and instrumentation. (authors)

  3. Drain Tank Information for Developing Design Basis of the Preliminary Design

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2012-02-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout and dimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  4. Accident source terms for pressurized water reactors with high-burnup cores calculated using MELCOR 1.8.5.

    SciTech Connect (OSTI)

    Gauntt, Randall O.; Powers, Dana Auburn; Ashbaugh, Scott G.; Leonard, Mark Thomas; Longmire, Pamela

    2010-04-01

    In this study, risk-significant pressurized-water reactor severe accident sequences are examined using MELCOR 1.8.5 to explore the range of fission product releases to the reactor containment building. Advances in the understanding of fission product release and transport behavior and severe accident progression are used to render best estimate analyses of selected accident sequences. Particular emphasis is placed on estimating the effects of high fuel burnup in contrast with low burnup on fission product releases to the containment. Supporting this emphasis, recent data available on fission product release from high-burnup (HBU) fuel from the French VERCOR project are used in this study. The results of these analyses are treated as samples from a population of accident sequences in order to employ approximate order statistics characterization of the results. These trends and tendencies are then compared to the NUREG-1465 alternative source term prescription used today for regulatory applications. In general, greater differences are observed between the state-of-the-art calculations for either HBU or low-burnup (LBU) fuel and the NUREG-1465 containment release fractions than exist between HBU and LBU release fractions. Current analyses suggest that retention of fission products within the vessel and the reactor coolant system (RCS) are greater than contemplated in the NUREG-1465 prescription, and that, overall, release fractions to the containment are therefore lower across the board in the present analyses than suggested in NUREG-1465. The decreased volatility of Cs2MoO4 compared to CsI or CsOH increases the predicted RCS retention of cesium, and as a result, cesium and iodine do not follow identical behaviors with respect to distribution among vessel, RCS, and containment. With respect to the regulatory alternative source term, greater differences are observed between the NUREG-1465 prescription and both HBU and LBU predictions than exist between HBU and LBU analyses. Additionally, current analyses suggest that the NUREG-1465 release fractions are conservative by about a factor of 2 in terms of release fractions and that release durations for in-vessel and late in-vessel release periods are in fact longer than the NUREG-1465 durations. It is currently planned that a subsequent report will further characterize these results using more refined statistical methods, permitting a more precise reformulation of the NUREG-1465 alternative source term for both LBU and HBU fuels, with the most important finding being that the NUREG-1465 formula appears to embody significant conservatism compared to current best-estimate analyses.

  5. SILENE Benchmark Critical Experiments for Criticality Accident Alarm Systems

    SciTech Connect (OSTI)

    Miller, Thomas Martin; Reynolds, Kevin H.

    2011-01-01

    In October 2010 a series of benchmark experiments was conducted at the Commissariat a Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE [1] facility. These experiments were a joint effort between the US Department of Energy (DOE) and the French CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems (CAASs). This presentation will discuss the geometric configuration of these experiments and the quantities that were measured and will present some preliminary comparisons between the measured data and calculations. This series consisted of three single-pulsed experiments with the SILENE reactor. During the first experiment the reactor was bare (unshielded), but during the second and third experiments it was shielded by lead and polyethylene, respectively. During each experiment several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor, and some of these detectors were themselves shielded from the reactor by high-density magnetite and barite concrete, standard concrete, and/or BoroBond. All the concrete was provided by CEA Saclay, and the BoroBond was provided by Y-12 National Security Complex. Figure 1 is a picture of the SILENE reactor cell configured for pulse 1. Also included in these experiments were measurements of the neutron and photon spectra with two BICRON BC-501A liquid scintillators. These two detectors were provided and operated by CEA Valduc. They were set up just outside the SILENE reactor cell with additional lead shielding to prevent the detectors from being saturated. The final detectors involved in the experiments were two different types of CAAS detectors. The Babcock International Group provided three CIDAS CAAS detectors, which measured photon dose and dose rate with a Geiger-Mueller tube. CIDAS detectors are currently in use at Y-12 in the newly constructed Highly Enriched Uranium Materials Facility. The second CAAS detector used a {sup 6}LiF TLD to absorb neutrons and a silicon detector to count the charge particles released by these absorption events. Lawrence Livermore National Laboratory provided four of these detectors, which had formerly been used at the Rocky Flats facility in the United States.

  6. Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in COGEMA's Cold Crucible Melter

    SciTech Connect (OSTI)

    Do Quang, R.; Petitjean, V.; Hollebecque, F.; Pinet, O.; Flament, T.; Prod'homme, A.

    2003-02-25

    The performance of the vitrification process currently used in the La Hague commercial reprocessing plants has been continuously improved during more than ten years of operation. In parallel COGEMA (industrial Operator), the French Atomic Energy Commission (CEA) and SGN (respectively COGEMA's R&D provider and Engineering) have developed the cold crucible melter vitrification technology to obtain greater operating flexibility, increased plant availability and further reduction of secondary waste generated during operations. The cold crucible is a compact water-cooled melter in which the radioactive waste and the glass additives are melted by direct high frequency induction. The cooling of the melter produces a solidified glass layer that protects the melter's inner wall from corrosion. Because the heat is transferred directly to the melt, high operating temperatures can be achieved with no impact on the melter itself. COGEMA plans to implement the cold crucible technology to vitrify high level liquid waste from reprocessed spent U-Mo-Sn-Al fuel (used in gas cooled reactor). The cold crucible was selected for the vitrification of this particularly hard-to-process waste stream because it could not be reasonably processed in the standard hot induction melters currently used at the La Hague vitrification facilities : the waste has a high molybdenum content which makes it very corrosive and also requires a special high temperature glass formulation to obtain sufficiently high waste loading factors (12 % in molybdenum). A special glass formulation has been developed by the CEA and has been qualified through lab and pilot testing to meet standard waste acceptance criteria for final disposal of the U-Mo waste. The process and the associated technologies have been also being qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification cell. This paper will present the results obtained in the framework of these qualification programs.

  7. AGR-2 Irradiated Test Train Preliminary Inspection and Disassembly First Look

    SciTech Connect (OSTI)

    Ploger, Scott; Demkowciz, Paul; Harp, Jason

    2015-05-01

    The AGR 2 irradiation experiment began in June 2010 and was completed in October 2013. The test train was shipped to the Materials and Fuels Complex in July 2014 for post-irradiation examination (PIE). The first PIE activities included nondestructive examination of the test train, followed by disassembly of the test train and individual capsules and detailed inspection of the capsule contents, including the fuel compacts and their graphite fuel holders. Dimensional metrology was then performed on the compacts, graphite holders, and steel capsule shells. AGR 2 disassembly and metrology were performed with the same equipment used successfully on AGR 1 test train components. Gamma spectrometry of the intact test train gave a preliminary look at the condition of the interior components. No evidence of damage to compacts or graphite components was evident from the isotopic and gross gamma scans. Disassembly of the AGR 2 test train and its capsules was conducted rapidly and efficiently by employing techniques refined during the AGR 1 disassembly campaign. Only one major difficulty was encountered while separating the test train into capsules when thermocouples (of larger diameter than used in AGR 1) and gas lines jammed inside the through tubes of the upper capsules, which required new tooling for extraction. Disassembly of individual capsules was straightforward with only a few minor complications. On the whole, AGR 2 capsule structural components appeared less embrittled than their AGR 1 counterparts. Compacts from AGR 2 Capsules 2, 3, 5, and 6 were in very good condition upon removal. Only relatively minor damage or markings were visible using high resolution photographic inspection. Compact dimensional measurements indicated radial shrinkage between 0.8 to 1.7%, with the greatest shrinkage observed on Capsule 2 compacts that were irradiated at higher temperature. Length shrinkage ranged from 0.1 to 0.9%, with by far the lowest axial shrinkage on Capsule 3 compacts—possibly as a consequence of lower packing fraction or larger particle size. Differences in fast neutron fluence among compacts from these four capsules had no obvious effect on radial and axial shrinkage. (The AGR 2 experiment included Capsule 1 containing French compacts and Capsule 4 with compacts made at Oak Ridge National Laboratory using South African fuel particles. Information on these two batches of AGR 2 fuel compacts is confined to restricted Appendices A and B because of proprietary information limitations.)

  8. CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT

    SciTech Connect (OSTI)

    Marra, J.

    2010-05-05

    The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

  9. FLUX SENSOR EVALUATIONS AT THE ATR CRITICAL FACILITY

    SciTech Connect (OSTI)

    Troy Unruh; Joy Rempe; David Nigg; George Imel; Jason Harris; Eric Bonebrake

    2010-11-01

    The Advanced Test Reactor (ATR) and the ATR Critical (ATRC) facilities lack real-time methods for detecting thermal neutron flux and fission reaction rates for irradiation capsules. Direct measurements of the actual power deposited into a test are now possible without resorting to complicated correction factors. In addition, it is possible to directly measure minor actinide fission reaction rates and to provide time-dependent monitoring of the fission reaction rate or fast/thermal flux during transient testing. A joint Idaho State University /Idaho National Laboratory ATR National Scientific User Facility (ATR NSUF) project was recently initiated to evaluate new real-time state-of-the-art in-pile flux detection sensors. Initially, the project is comparing the accuracy, response time, and long duration performance of French Atomic Energy Commission (CEA)-developed miniature fission chambers, specialized self-powered neutron detectors (SPNDs) by the Argentinean National Energy Commission (CNEA), specially developed commercial SPNDs, and back-to-back fission (BTB) chambers developed by Argonne National Laboratory (ANL). As discussed in this paper, specialized fixturing and software was developed by INL to facilitate these joint ISU/INL evaluations. Calculations were performed by ISU to assess the performance of and reduce uncertainties in flux detection sensors and compare data obtained from these sensors with existing integral methods employed at the ATRC. Ultimately, project results will be used to select the detector that can provide the best online regional ATRC power measurement. It is anticipated that project results may offer the potential to increase the ATRCs current power limit and its ability to perform low-level irradiation experiments. In addition, results from this effort will provide insights about the viability of using these detectors in the ATR. Hence, this effort complements current activities to improve ATR software tools, computational protocols and in-core instrumentation under the ATR Modeling, Simulation and V&V Upgrade initiative, as well as the work to replace nuclear instrumentation under the ATR Life Extension Project (LEP) and provide support to the ATR NSUF.

  10. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    SciTech Connect (OSTI)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria and design data needs to evolve as the design progresses, operating conditions are refined, and materials characteristics in the unique environment are established. This paper develops the relationship between the designers' data needs and the structural design criteria recently adopted for the Target Blanket System of the APT. The latter, the newly-developed APT Supplemental Structural Design Requirements (APT SSDR), was patterned after the design criteria developed for the International Thermonuclear Experimental (Fusion) Reactor (ITER). A summary description of the design rules based on the APT SSDR is presented, and the impact of these rules of changes in materials properties resulting from exposure in the APT proton/neutron irradiation environment are discussed.

  11. The technical and economic impact of minor actinide transmutation in a sodium fast reactor

    SciTech Connect (OSTI)

    Gautier, G. M.; Morin, F.; Dechelette, F.; Sanseigne, E.; Chabert, C.

    2012-07-01

    Within the frame work of the French National Act of June 28, 2006 pertaining to the management of high activity, long-lived radioactive waste, one of the proposed processes consists in transmuting the Minor Actinides (MA) in the radial blankets of a Sodium Fast Reactor (SFR). With this option, we may assess the additional cost of the reactor by comparing two SFR designs, one with no Minor Actinides, and the other involving their transmutation. To perform this exercise, we define a reference design called SFRref, of 1500 MWe that is considered to be representative of the Reactor System. The SFRref mainly features a pool architecture with three pumps, six loops with one steam generator per loop. The reference core is the V2B core that was defined by the CEA a few years ago for the Reactor System. This architecture is designed to meet current safety requirements. In the case of transmutation, for this exercise we consider that the fertile blanket is replaced by two rows of assemblies having either 20% of Minor Actinides or 20% of Americium. The assessment work is performed in two phases. - The first consists in identifying and quantifying the technical differences between the two designs: the reference design without Minor Actinides and the design with Minor Actinides. The main differences are located in the reactor vessel, in the fuel handling system and in the intermediate storage area for spent fuel. An assessment of the availability is also performed so that the impact of the transmutation can be known. - The second consists in making an economic appraisal of the two designs. This work is performed using the CEA's SEMER code. The economic results are shown in relative values. For a transmutation of 20% of MA in the assemblies (S/As) and a hypothesis of 4 kW allowable for the washing device, there is a large external storage demanding a very long cooling time of the S/As. In this case, the economic impact may reach 5% on the capital part of the Levelized Unit Electricity Cost (LUEC). A diminished concentration at 10% of MA, reduces the size of the external storage and the cooling time of the assemblies becomes compatible with the management of the irradiated fuel. Even with a low allowable power for the washing device, the economic impact on the capital cost is less than 2.5%. (authors)

  12. Small fields output factors measurements and correction factors determination for several detectors for a CyberKnife{sup Registered-Sign} and linear accelerators equipped with microMLC and circular cones

    SciTech Connect (OSTI)

    Bassinet, C.; Huet, C.; Derreumaux, S.; Baumann, M.; Trompier, F.; Roch, P.; Clairand, I.; Brunet, G.; Gaudaire-Josset, S.; Chea, M.; Boisserie, G.

    2013-07-15

    Purpose: The use of small photon fields is now an established practice in stereotactic radiosurgery and radiotherapy. However, due to a lack of lateral electron equilibrium and high dose gradients, it is difficult to accurately measure the dosimetric quantities required for the commissioning of such systems. Moreover, there is still no metrological dosimetric reference for this kind of beam today. In this context, the first objective of this work was to determine and to compare small fields output factors (OF) measured with different types of active detectors and passive dosimeters for three types of facilities: a CyberKnife{sup Registered-Sign} system, a dedicated medical linear accelerator (Novalis) equipped with m3 microMLC and circular cones, and an adaptive medical linear accelerator (Clinac 2100) equipped with an additional m3 microMLC. The second one was to determine the k{sub Q{sub c{sub l{sub i{sub n,Q{sub m{sub s{sub r}{sup f{sub c}{sub l}{sub i}{sub n},f{sub m}{sub s}{sub r}}}}}}}}} correction factors introduced in a recently proposed small field dosimetry formalism for different active detectors.Methods: Small field sizes were defined either by microMLC down to 6 Multiplication-Sign 6 mm{sup 2} or by circular cones down to 4 mm in diameter. OF measurements were performed with several commercially available active detectors dedicated to measurements in small fields (high resolution diodes: IBA SFD, Sun Nuclear EDGE, PTW 60016, PTW 60017; ionizing chambers: PTW 31014 PinPoint chamber, PTW 31018 microLion liquid chamber, and PTW 60003 natural diamond). Two types of passive dosimeters were used: LiF microcubes and EBT2 radiochromic films.Results: Significant differences between the results obtained by several dosimetric systems were observed, particularly for the smallest field size for which the difference in the measured OF reaches more than 20%. For passive dosimeters, an excellent agreement was observed (better than 2%) between EBT2 and LiF microcubes for all OF measurements. Moreover, it has been shown that these passive dosimeters do not require correction factors and can then be used as reference dosimeters. Correction factors for the active detectors have then been determined from the mean experimental OF measured by the passive dosimeters.Conclusions: Four sets of correction factors needed to apply the new small field dosimetry formalism are provided for several active detectors. A protocol for small photon beams OF determination based on passive dosimeters measurements has been recently proposed to French radiotherapy treatment centers.

  13. NEET Enhanced Micro Pocket Fission Detector for High Temperature Reactors - FY15 Status Report

    SciTech Connect (OSTI)

    Unruh, Troy; McGregor, Douglas; Ugorowski, Phil; Reichenberger, Michael; Ito, Takashi

    2015-09-01

    A new project, that is a collaboration between the Idaho National Laboratory (INL), the Kansas State University (KSU), and the French Atomic Energy Agency, Commissariat à l'Énergie Atomique et aux Energies Alternatives, (CEA), has been initiated by the Nuclear Energy Enabling Technologies (NEET) Advanced Sensors and Instrumentation (ASI) program for developing and testing High Temperature Micro-Pocket Fission Detectors (HT MPFD), which are compact fission chambers capable of simultaneously measuring thermal neutron flux, fast neutron flux and temperature within a single package for temperatures up to 800 °C. The MPFD technology utilizes a small, multi-purpose, robust, in-core parallel plate fission chamber and thermocouple. As discussed within this report, the small size, variable sensitivity, and increased accuracy of the MPFD technology represent a revolutionary improvement over current methods used to support irradiations in US Material Test Reactors (MTRs). Previous research conducted through NEET ASI1-3 has shown that the MPFD technology could be made robust and was successfully tested in a reactor core. This new project will further the MPFD technology for higher temperature regimes and other reactor applications by developing a HT MPFD suitable for temperatures up to 800 °C. This report summarizes the research progress for year one of this three year project. Highlights from research accomplishments include: A joint collaboration was initiated between INL, KSU, and CEA. Note that CEA is participating at their own expense because of interest in this unique new sensor. An updated HT MPFD design was developed. New high temperature-compatible materials for HT MPFD construction were procured. Construction methods to support the new design were evaluated at INL. Laboratory evaluations of HT MPFD were initiated. Electrical contact and fissile material plating has been performed at KSU. Updated detector electronics are undergoing evaluations at KSU. A project meeting was held at KSU to discuss the roles and responsibilities between INL and KSU for development of the HT MPFDs. Provide input to various irradiation programs for installation of the MPFD technology in irradiation tests. As documented in this report, FY15 funding has allowed the project to meet year one planned accomplishments to develop a HT MPFD that offers US MTR users enhanced capabilities for real-time measurement of flux and temperature with a single detector. In addition, the accomplishments of this project have attracted funding from other Department of Energy Office of Nuclear Energy (DOE-NE) programs for additional applications. The work in those programs will build on current activities completed in this NEETASI HT MPFD project, but the MPFD will be specifically tailored to meet their program needs.

  14. Sharing Experiences within AREVA D and D Project Portfolio: Four Illustrations - 13049

    SciTech Connect (OSTI)

    Chabeuf, Jean-Michel; Varet, Thierry; AREVA Site Value Development Business Unit, La Hague Site

    2013-07-01

    Over the past ten years, AREVA has performed D and D operations on a wide range of nuclear sites, such as Marcoule and La Hague recycling plants, to Cadarache MOX fuel fabrication plant or Veurey and Annecy metallic Uranium machining plants. Each site is different from the other but some lessons can be shared through this D and D portfolio. In that respect, knowledge management is one of AREVA D and D Technical Department main missions. Four illustrations demonstrate the interest of knowledge share. Waste management is one of the key activities in D and D; It requires a specific characterization methodology, adapted logistics, and optimized waste channels, all of which have been developed over the years by AREVA teams on the site of Marcoule while they are rather new to La Hague, whose main activity remains fuel reprocessing despite the launch of UP2 400 D and D program. The transfer of know how has thus been organized over the past two years. Plasma cutting has been used extensively in Marcoule for years, while prohibited on the site of La Hague following questions raised about the risks associated wit Ruthenium sublimation. La Hague Technical Department has thus developed an experimental protocol to quantify and contain the Ruthenium risk, the result of which will then be applied to Marcoule where the Ruthenium issue has appeared in recent operations. Commissioning and operating fission products evaporators is a rather standard activity on UP2 800 and UP3, while the associated experience has been decreasing in Marcoule following final shutdown in 1998. When the French atomic Energy commission decided to build and operate a new evaporator to concentrate rinsing effluents prior to vitrification in 2009, AREVA La Hague operators were mobilized to test and commission the new equipment, and train local operators. Concrete scabbling is the final stage prior to the free release of a nuclear facility. In the context of Veurey and Annecy final cleanup and declassification, large scale concrete scabbling operations were conducted, and lead to the industrialization of the process and qualification of a new process, NiThrow{sup TM} scabbling technology, developed by AREVA. This experience has now been injected into La Hague D and D scenario and has allowed a significant gain in time and cost for scabbling operations. In short, the variety of experiences and sites under the responsibility of AREVA D and D teams present significant challenges, and yet provide a unique opportunity to innovate and qualify new tools and methods which can then be shared throughout the sites. (authors)

  15. NEET Micro-Pocket Fission Detector. Final Project report

    SciTech Connect (OSTI)

    Unruh, T.; Rempe, Joy; McGregor, Douglas; Ugorowski, Philip; Reichenberger, Michael; Ito, Takashi; Villard, J.-F.

    2014-09-01

    A collaboration between the Idaho National Laboratory (INL), the Kansas State University (KSU), and the French Alternative Energies and Atomic Energy Commission, Commissariat à l'Énergie Atomique et aux Energies Alternatives, (CEA), is funded by the Nuclear Energy Enabling Technologies (NEET) program to develop and test Micro-Pocket Fission Detectors (MPFDs), which are compact fission chambers capable of simultaneously measuring thermal neutron flux, fast neutron flux and temperature within a single package. When deployed, these sensors will significantly advance flux detection capabilities for irradiation tests in US Material Test Reactors (MTRs). Ultimately, evaluations may lead to a more compact, more accurate, and longer lifetime flux sensor for critical mock-ups, and high performance reactors, allowing several Department of Energy Office of Nuclear Energy (DOE-NE) programs to obtain higher accuracy/higher resolution data from irradiation tests of candidate new fuels and materials. Specifically, deployment of MPFDs will address several challenges faced in irradiations performed at MTRs: Current fission chamber technologies do not offer the ability to measure fast flux, thermal flux and temperature within a single compact probe; MPFDs offer this option. MPFD construction is very different than current fission chamber construction; the use of high temperature materials allow MPFDs to be specifically tailored to survive harsh conditions encountered in-core of high performance MTRs. The higher accuracy, high fidelity data available from the compact MPFD will significantly enhance efforts to validate new high-fidelity reactor physics codes and new multi-scale, multi-physics codes. MPFDs can be built with variable sensitivities to survive the lifetime of an experiment or fuel assembly in some MTRs, allowing for more efficient and cost effective power monitoring. The small size of the MPFDs allows multiple sensors to be deployed, offering the potential to accurately measure the flux and temperature profiles in the reactor. This report summarizes the status at the end of year two of this three year project. As documented in this report, all planned accomplishments for developing this unique new, compact, multipurpose sensor have been completed.

  16. Early Regulatory Engagement for Successful Site Remediation: the UK Experience - 13173

    SciTech Connect (OSTI)

    Maitland, R.P.; Senior, D.

    2013-07-01

    The Office for Nuclear Regulation (ONR) is an independent safety, security and transport regulator of the UK nuclear industry. ONR regulates all civil nuclear reactor power stations, fuel manufacture, enrichment, spent fuel reprocessing, most defence sites and installations that store and process legacy spent fuel and radioactive waste. The responsibility for funding and strategic direction of decommissioning and radioactive waste management of state owned legacy sites has rested solely with the Nuclear Decommissioning Authority (NDA) since 2005. A key component of NDA's mandate was to encourage new strategic approaches and innovation to dealing with the UK's waste legacy and which deliver value-for-money to the UK taxpayer. ONR, as an agency of the Health and Safety Executive, is entirely independent of NDA and regulates all prescribed activities on NDA's sites. NDA's competition of site management and closure contracts has attracted significant international interest and the formation of consortia comprised of major British, US, French and Swedish organizations bidding for those contracts. The prominence of US organizations in each of those consortia reflects the scale and breadth of existing waste management and D and D projects in the US. This paper will articulate, in broad terms, the challenges faced by international organizations seeking to employ 'off-the-shelf' technology and D and D techniques, successfully employed elsewhere, into the UK regulatory context. The predominantly 'goal-setting' regulatory framework in the UK does not generally prescribe a minimum standard to which a licensee must adhere. The legal onus on licensees in the UK is to demonstrate, whatever technology is selected, that in its applications, risks are reduced 'So Far As Is Reasonably Practicable' or 'SFAIRP'. By the nature of its role, ONR adopts a conservative approach to regulation; however ONR also recognises that in the decommissioning (and ultimately the site closure) domain, it is often necessary to consider and support novel approaches to achieve the nationally desired end-state. Crucial to successful and compliant operation in this regulatory environment is early and sustained engagement of the contractor with the regulator. There must be a 'no-surprises' culture to engender regulatory confidence early in a project. The paper considers some of the challenges facing international prime and lower tier contractors when undertaking D and D contracts in the UK, and emphasizes the importance of constructive and transparent dialogue with all regulators to sustain confidence at all stages of a major decommissioning project. The paper will also articulate ONR's strategy to increase collaboration with the US Department of Energy in light of increasing UK-US synergy in the area of waste management and to benchmark respective regulatory approaches. (authors)

  17. Qualification of JEFF3.1.1 library for high conversion reactor calculations using the ERASME/R experiment

    SciTech Connect (OSTI)

    Vidal, J. F.; Noguere, G.; Peneliau, Y.; Santamarina, A.

    2012-07-01

    With its low CO{sub 2} production, Nuclear Energy appears to be an efficient solution to the global warming due to green-house effect. However, current LWR reactors are poor uranium users and, pending the development of Fast Neutron Reactors, alternative concepts of PWR with higher conversion ratio (HCPWR) are being studied again at CEA, first studies dating from the middle 80's. In these French designs, low moderation ratio has been performed by tightening the lattice pitch, achieving a conversion ratio of 0.8-0.9 with a MOX fuel coming from PWR UOX recycling. Theses HCPWRs are characterized by a harder neutron spectrum and the calculation uncertainties on the fundamental neutronics parameters are increased by a factor 3 regarding a standard PWR lattice, due to the major contribution of the Plutonium isotopes and of the epithermal energy range to the reaction rates. In order to reduce these uncertainties, a 3-year experimental validation program called ERASME has been performed by CEA from 1984 to 1986 in the EOLE reactor. Monte Carlo analysis of the ERASME/R experiments with the Monte Carlo code TRIPOLI4 allowed the qualification of the recommended JEFF.3.1.1 library for major neutronics parameters. K{sub eff} of the MOX under-moderated lattice is over-predicted by 440 {+-} 830 pcm (2{sigma}); the conversion ratio, indicator of the good use of uranium, is also slightly over-predicted: 2 % {+-} 4 % (2{sigma}) and the same for B4C absorber rods worth and soluble boron worth, over-predicted by 2 %, both in the 2 standard deviations range. The radial fission maps of heterogeneities (water-holes, B4C and fertile rods) are well reproduced: maximal (C-E)/E dispersion is 1.3 %, maximal power peak error is 2.7 %. The void reactivity worth is the only parameter poorly calculated with an overprediction of +12.4% {+-} 1.5%. ERASME/R analysis of MOX reactivity, void effect and spectral indexes will contribute to the reevaluation of {sup 241}Am and Plutonium isotopes nuclear data for the next library JEFF3.2. (authors)

  18. Non-local equilibrium two-phase flow model with phase change in porous media and its application to reflooding of a severely damaged reactor core

    SciTech Connect (OSTI)

    Bachrata, A.; Fichot, F.; Quintard, M.; Repetto, G.; Fleurot, J.

    2012-05-15

    A generalized non local-equilibrium, three-equation model was developed for the macroscopic description of two-phase flow heat and mass transfer in porous media subjected to phase change. Six pore-scale closure problems were proposed to determine all the effective transport coefficients for representative unit cells. An improved model is presented in this paper with the perspective of application to intense boiling phenomena. The objective of this paper is to present application of this model to the simulation of reflooding of severely damaged nuclear reactor cores. In case of accident at a nuclear power plant, water sources may not be available for a long period of time and the core heats up due to the residual power. Any attempt to inject water during core degradation can lead to quenching and further fragmentation of the core material. The fragmentation of fuel rods and melting of reactor core materials may result in the formation of a {sup d}ebris bed{sup .} The typical particle size in a debris bed might reach few millimeters (characteristic length-scale: 1 to 5 mm), which corresponds to a high permeability porous medium. The proposed two-phase flow model is implemented in the ICARECATHARE code, developed by IRSN to study severe accident scenarios in pressurized water reactors. Currently, the French IRSN has set up two experimental facilities to study debris bed reflooding, PEARL and PRELUDE, with the objective to validate safety models. The PRELUDE program studies the complex two phase flow of water and steam in a porous medium (diameter 180 mm, height 200 mm), initially heated to a high temperature (400 deg. C or 700 deg. C). The series of PRELUDE experiments achieved in 2010 constitute a significant complement to the database of high temperature bottom reflood experimental data. They provide relevant data to understand the progression of the quench front and the intensity of heat transfer. Modeling accurately these experiments required improvements to the reflooding model, especially in terms of the existence of various saturation regimes. The improved two-phase flow model shows a good agreement with PRELUDE experimental results.

  19. Drain Tank Information for Developing Design Basis of the Preliminary Design - R00

    SciTech Connect (OSTI)

    Ferrada, Juan J [ORNL

    2011-01-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  20. Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)

    SciTech Connect (OSTI)

    John D. Bess; J. Blair Briggs

    2010-06-01

    The March 2010 edition of the International Reactor Physics Experiment Evaluation Project (IRPhEP) Handbook includes additional benchmark data that can be implemented in the validation of data and methods for Generation IV (GEN-IV) reactor designs. Evaluations supporting sodium-cooled fast reactor (SFR) efforts include the initial isothermal tests of the Fast Flux Test Facility (FFTF) at the Hanford Site, the Zero Power Physics Reactor (ZPPR) 10B and 10C experiments at the Idaho National Laboratory (INL), and the burn-up reactivity coefficient of Japan’s JOYO reactor. An assessment of Russia’s BFS-61 assemblies at the Institute of Physics and Power Engineering (IPPE) provides additional information for lead-cooled fast reactor (LFR) systems. Benchmarks in support of the very high temperature reactor (VHTR) project include evaluations of the HTR-PROTEUS experiments performed at the Paul Scherrer Institut (PSI) in Switzerland and the start-up core physics tests of Japan’s High Temperature Engineering Test Reactor. The critical configuration of the Power Burst Facility (PBF) at the INL which used ternary ceramic fuel, U(18)O2-CaO-ZrO2, is of interest for fuel cycle research and development (FCR&D) and has some similarities to “inert-matrix” fuels that are of interest in GEN-IV advanced reactor design. Two additional evaluations were revised to include additional evaluated experimental data, in support of light water reactor (LWR) and heavy water reactor (HWR) research; these include reactor physics experiments at Brazil’s IPEN/MB-01 Research Reactor Facility and the French High Flux Reactor (RHF), respectively. The IRPhEP Handbook now includes data from 45 experimental series (representing 24 reactor facilities) and represents contributions from 15 countries. These experimental measurements represent large investments of infrastructure, experience, and cost that have been evaluated and preserved as benchmarks for the validation of methods and collection of data in support of current and future reactor design and development.

  1. Carbon dioxide, hydrographic, and chemical data obtained in the Central South Pacific Ocean (WOCE sections P17S and P16S) during the tunes-2-expedition of the R/V Thomas Washington, July--August 1991

    SciTech Connect (OSTI)

    1991-12-31

    This data documentation discusses the procedures and methods used to measure total carbon dioxide (TCO{sub 2}), discrete partial pressure of TCO{sub 2} (pCO{sub 2}), and total alkalinity (TALK), during the Research Vessel (R/V) Thomas Washington TUNES Leg 2 Expedition in the central South Pacific Ocean. Conducted as part of the World Ocean Circulation Experiment (WOCE), the cruise began in Papeete, Tahiti, French Polynesia, on July 16, 1991, and returned to Papeete on August 25, 1991. WOCE Meridional Sections P17S along 135{degrees} W and P16S along 150{degrees} W were completed during the 40-day expedition. A total of 97 hydrographic stations were occupied. Hydrographic and chemical measurements made along WOCE Sections P17S and P16S included pressure, temperature, salinity, and oxygen measured by conductivity, temperature and depth sensor; bottle salinity; oxygen; phosphate; nitrate; nitrite; silicate; CFC-12; CFC- 11; TCO{sub 2}; TALK; and pCO{sub 2} measured at 20{degrees}C. The TCO{sub 2} concentration in 1000 seawater samples was determined with a coulometric analysis system, the pCO{sub 2} in 940 water samples was determined with an equilibrator/gas chromatograph system, while the TALK concentration in 139 samples was determined on shore at the laboratory of C. Goyet of Woods Hole Oceanographic Institution with an alkalinity titration system. In addition, 156 coulometric measurements for the Certified Reference Material (Batch {number_sign}6) were made and yielded a mean value of 2303.2 {plus_minus} 1.5 {mu}mol/kg. This mean value agrees within a standard deviation of the 2304.6 {plus_minus} 1.6 {mu}mol/kg (N=9) value determined with the manometer of C. D. Keeling at Scripps Institution of Oceanography (SIO). Replicate samples from 11 Niskin bottles at 4 stations were also collected for later shore-based reference analyses of TCO{sub 2} and TALK by vacuum extraction and manometry in the laboratory of C. D. Keeling of SIO.

  2. AREVA NP next generation fresh UO{sub 2} fuel assembly shipping cask: SCALE - CRISTAL comparisons lead to safety criticality confidence

    SciTech Connect (OSTI)

    Doucet, M.; Landrieu, M.; Montgomery, R.; O' Donnell, B.

    2007-07-01

    AREVA NP as a worldwide PWR fuel provider has to have a fleet of fresh UO{sub 2} shipping casks being agreed within a lot of countries including USA, France, Germany, Belgium, Sweden, China, and South Africa - and to accommodate foreseen EPR Nuclear Power Plants fuel buildings. To reach this target the AREVA NP Fuel Sector decided to develop an up-to-date shipping cask (so called MAP project) gathering experience feedback of the today fleet and an improved safety allowing the design to comply with international regulations (NRC and IAEA) and local Safety Authorities. Based on pre design features a safety case was set up to highlight safety margins. Criticality hypothetical accidental assumptions were defined: - Preferential flooding; - Fuel rod lattice pitch expansion for full length of fuel assemblies; - Neutron absorber penalty; -... Well known computer codes, American SCALE package and French CRISTAL package, were used to check configurations reactivity and to ensure that both codes lead to coherent results. Basic spectral calculations are based on similar algorithms with specific microscopic cross sections ENDF/BV for SCALE and JEF2.2 for CRISTAL. The main differences between the two packages is on one hand SCALE's three dimensional fuel assembly geometry is described by a pin by pin model while an homogenized fuel assembly description is used by CRISTAL and on the other hand SCALE is working with either 44 or 238 neutron energy groups while CRISTAL is with a 172 neutron energy groups. Those two computer packages rely on a wide validation process helping defining uncertainties as required by regulations in force. The shipping cask with two fuel assemblies is designed to maximize fuel isolation inside a cask and with neighboring ones even for large array configuration cases. Proven industrial products are used: - Boral{sup TM} as neutron absorber; - High density polyethylene (HDPE) or Nylon as neutron moderator; - Foam as thermal and mechanical protection. The cask is designed to handle the complete AREVA NP fuel assembly types from the 14x14 to the 18x18 design with a {sup 235}U enrichment up to 5.0% enriched natural uranium (ENU) and enriched reprocessed uranium (ERU). After a brief presentation of the computer codes and the description of the shipping cask, calculation results and comparisons between SCALE and CRISTAL will be discussed. (authors)

  3. MELCOR 1.8.5 modeling aspects of fission product release, transport and deposition an assessment with recommendations.

    SciTech Connect (OSTI)

    Gauntt, Randall O.

    2010-04-01

    The Phebus and VERCORS data have played an important role in contemporary understanding and modeling of fission product release and transport from damaged light water reactor fuel. The data from these test programs have allowed improvement of MELCOR modeling of release and transport processes for both low enrichment uranium fuel as well as high burnup and mixed oxide (MOX) fuels. This paper discusses the synthesis of these findings in the MELCOR severe accident code. Based on recent assessments of MELCOR 1.8.5 fission product release modeling against the Phebus FPT-1 test and on observations from the ISP-46 exercise, modifications to the default MELCOR 1.8.5 release models are recommended. The assessments identified an alternative set of Booth diffusion parameters recommended by ORNL (ORNL-Booth), which produced significantly improved release predictions for cesium and other fission product groups. Some adjustments to the scaling factors in the ORNL-Booth model were made for selected fission product groups, including UO{sub 2}, Mo and Ru in order to obtain better comparisons with the FPT-1 data. The adjusted model, referred to as 'Modified ORNL-Booth,' was subsequently compared to original ORNL VI fission product release experiments and to more recently performed French VERCORS tests, and the comparisons was as favorable or better than the original CORSOR-M MELCOR default release model. These modified ORNL-Booth parameters, input to MELCOR 1.8.5 as 'sensitivity coefficients' (i.e. user input that over-rides the code defaults) are recommended for the interim period until improved release models can be implemented into MELCOR. For the case of ruthenium release in air-oxidizing conditions, some additional modifications to the Ru class vapor pressure are recommended based on estimates of the RuO{sub 2} vapor pressure over mildly hyperstoichiometric UO{sub 2}. The increased vapor pressure for this class significantly increases the net transport of Ru from the fuel to the gas stream. A formal model is needed. Deposition patterns in the Phebus FPT-1 circuit were also significantly improved by using the modified ORNL-Booth parameters, where retention of lower volatile Cs{sub 2}MoO{sub 4} is now predicted in the heated exit regions of the FPT-1 test, bringing down depositions in the FPT-1 steam generator tube to be in closer alignment with the experimental data. This improvement in 'RCS' deposition behavior preserves the overall correct release of cesium to the containment that was observed even with the default CORSOR-M model. Not correctly treated however is the release and transport of Ag to the FPT-1 containment. A model for Ag release from control rods is presently not available in MELCOR. Lack of this model is thought to be responsible for the underprediction by a factor of two of the total aerosol mass to the FPT-1 containment. It is suggested that this underprediction of airborne mass led to an underprediction of the aerosol agglomeration rate. Underprediction of the agglomeration rate leads to low predictions of the aerosol particle size in comparison to experimentally measured ones. Small particle size leads low predictions of the gravitational settling rate relative to the experimental data. This error, however, is a conservative one in that too-low settling rate would result in a larger source term to the environment. Implementation of an interim Ag release model is currently under study. In the course of this assessment, a review of MELCOR release models was performed and led to the identification of several areas for future improvements to MELCOR. These include upgrading the Booth release model to account for changes in local oxidizing/reducing conditions and including a fuel oxidation model to accommodate effects of fuel stoichiometry. Models such as implemented in the French ELSA code and described by Lewis are considered appropriate for MELCOR. A model for ruthenium release under air oxidizing conditions is also needed and should be included as part of a fuel oxidation model since fuel stoichiometry is a fundamen

  4. COSMO 09

    SciTech Connect (OSTI)

    2009-09-07

    This year's edition of the annual Cosmo International Conference on Particle Physics and Cosmology -- Cosmo09 -- will be hosted by the CERN Theory Group from Monday September 7 till Friday September 11, 2009. The conference will take place at CERN, Geneva (Switzerland). The Cosmo series is one of the major venues of interaction between cosmologists and particle physicists. In the exciting LHC era, the Conference will be devoted to the modern interfaces between Fundamental and Phenomenological Particle Physics and Physical Cosmology and Astronomy. The Conference will be followed by the CERN TH Institute "Particle Cosmology" which will take place from Monday September 14 till Friday September 18, 2009. The CERN-TH Institutes are visitor programs intended to bring together scientists with similar interests and to promote scientific collaborations. If you wish to participate, please register on the Institute web page. Link to last editions: COSMO 07 (U. of Sussex), COSMO 08 (U. of Wisconsin) List of plenary speakers: Gianfranco Bertone, Pierre Binetruy, Francois Bouchet, Juerg Diemand, Jonathan Feng, Gregory Gabadadze, Francis Halzen, Steen Hannestad, Will Kinney, Johannes Knapp, Hiranya Peiris, Will Percival, Syksy Rasanen, Alexandre Refregier, Pierre Salati, Roman Scoccimarro, Michael Schubnell, Christian Spiering, Neil Spooner, Andrew Tolley, Matteo Viel. The plenary program is available on-line. Select "Preliminary programme" in the left menu and click on each plenary session to see details. Parallel sessions: Inflation, convenor: Andrew Liddle Dark matter, convenor: Marco Cirelli Dark energy and modified gravity, convenor: Kazuya Koyama CMB, LSS and cosmological parameters/models, convenor: Licia Verde String cosmology, convenor: Jim Cline Baryogenesis and leptogenesis, convenor: Mariano Quiros The submission of talk proposals is closed by now. The parallel session program is available on-line. Select "Preliminary programme" in the left menu and click on each parallel session title to see details. Posters. Participants willing to present a poster will be offered the opportunity to hang it in the hall, next to the main auditorium. The poster application is closed by now. The poster list is available on-line. Registration. On-line registration is open from January 16 till August 31 (click on the link in the left menu). There will be no registration fees. [Thanks to the generosity of EU's network "UniverseNet", we have some limited funds available for supporting the visit of a few young scientists who could not attend otherwise. The application for funding is closed by now. All applicants have already been informed of the success of their application.] Accomodation. Participants are expected to arrange their accomodation by themselves: some rooms with shower, wc and washbasin have been blocked in the CERN hostel for the conference (price: 58CHF/night). Unfortunately, all these rooms have already been booked. You can book a hotel in Geneva or in the area surrounding CERN using this list. If you book a hotel on the French side, be sure to have a passport or a visa valid also in France. All participants are expected to be in possession of a passport or a visa valid in Swizerland (if relevant), and to be covered by their own health insurance during their visit. Sponsors. This conference is receiving support from the European Community's Marie Curie Research and Training Network UniverseNet.

  5. Cold Crucible Induction Melter (CCIM) Demonstration Using a Representative Savannah River Site Sludge Simulant On the Large-Size Pilot Platform at the CEA-Marcoule

    SciTech Connect (OSTI)

    Girold, C.; Delaunay, M.; Dussossoy, J.L.; Lacombe, J. [CEA Marcoule, CEA/DEN/DTCD/SCDV, 30 (France); Marra, S.; Peeler, D.; Herman, C.; Smith, M.; Edwards, R.; Barnes, A.; Stone, M. [Savannah River National Laboratory (SRNL), Washington Savannah River Company, Savannah River Site, Aiken, SC (United States); Iverson, D. [Liquid Waste Operations, Washington Savannah River Company (WSRC), Aiken, SC (United States); Do Quang, R. [AREVA NC, Tour AREVA, 92 - Paris La Defense (France); Tchemitcheff, E. [AREVA Federal Services LLC, Richland Office, Richland, WA (United States); Veyer, C. [Consultant, 59 - Saint Waast la Vallee (France)

    2008-07-01

    The cold-crucible induction melter technology (CCIM) is considered worldwide for industrial implementation to overcome the current limits of high level waste vitrification technologies and to answer future challenges such as: new or difficult sludge compositions, need for improving waste loading, need for high temperatures, and corrosive effluents. More particularly, this technology is being considered for implementation at the US DOE Savannah River site to increase the rate of waste processing while reducing the number of HLW canisters to be produced through increased waste loading and improved waste throughput. A collaborative program involving AREVA, CEA (French Atomic Energy Commission), SRNL (Savannah River National Laboratory) and WSRC (Washington Savannah River Company) has thus been initiated in 2007 to demonstrate vitrification with waste loadings on the order of 50% (versus the current DWPF waste loading of about 35%) with a PUREX-type waste composition (high Fe{sub 2}O{sub 3} composition), and to perform two pilot-scale runs on the large size platform equipped with a 650 mm diameter CCIM at the CEA Marcoule. The objectives of the demonstrations were 1) to show the feasibility of processing a representative SRS sludge surrogate using continuous slurry feeding, 2) to produce a glass that would meet the acceptance specifications with an increased waste loading when compared to what is presently achieved at the DWPF, and 3) achieve improved waste throughputs. This presentation describes the platform and the very encouraging results obtained from the demonstration performed at temperatures, specific throughputs and waste loadings that overcome current DWPF limits. Results from the initial exploratory run and second demonstration run include 1) production of a glass product that achieved the targeted glass composition that was more durable than the standard Environmental Assessment (EA) glass, 2) successful slurry feeding of the CCIM, and 3) promising waste processing rates (at 1250 deg. C and 1300 deg. C melt pool temperature) that could result in processing of the Savannah River HLW faster than could be currently achieved with the existing Joule Heated melter in DWPF. In conclusion, this joint effort conducted by CEA, AREVA, SRNL and WSRC led to very encouraging results, demonstrating waste throughputs 44 % that of the DWPF ceramic melter throughput in a 650 mm CCIM melter for the same waste type with a Sludge Batch 3 PUREX-type waste feed flux of 150 L/h/m{sup 2} demonstrated at 1250 deg. C. The very high waste loading (above 52%) allows reducing the amount of glass to be produced by about 27% to treat the same amount of waste when compared to previous DWPF operation for this specific type of feed, since 27 % less glass is needed to immobilize the same amount of waste. It was also demonstrated, for this type of feed, an unusual behavior with regard to nepheline formation, which would require further evaluation for future applications. The product from the baseline demonstration run, with a waste loading of at least 52%, displayed a very good quality. Stabilized operation close to the maximum throughput was demonstrated. Cesium volatility was apparently between 7 and 12 % (based on glass analysis); however this value is only preliminary. This demonstration also allowed the CEA to better understand the SRS slurry feed behavior and to propose adaptations to the platform for any future demonstrations using this type of feed. Finally, use of a large diameter CCIM ({approx}1 meter) may allow faster processing of the SRS HLW than can be achieved with the current DWPF melter. (authors)

  6. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect (OSTI)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

  7. A Cultural Resources Inventory and Historical Evaluation of the Smoky Atmospheric Nuclear Test, Areas 8, 9, and 10, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Jones, Robert C.; King, Maureen L.; Beck, Colleen M.; Falvey, Lauren W.; Menocal, Tatianna M.

    2014-09-01

    This report presents the results of a National Historic Preservation Act Section 106 cultural resources inventory and historical evaluation of the 1957 Smoky atmospheric test location on the Nevada National Security Site (NNSS). The Desert Research Institute (DRI) was tasked to conduct a cultural resources study of the Smoky test area as a result of a proposed undertaking by the Department of Energy Environmental Management. This undertaking involves investigating Corrective Action Unit (CAU) 550 for potential contaminants of concern as delineated in a Corrective Action Investigation Plan. CAU 550 is an area that spatially overlaps portions of the Smoky test location. Smoky, T-2c, was a 44 kt atmospheric nuclear test detonated at 5:30 am on August 31, 1957, on top of a 213.4 m (700 ft) 200 ton tower (T-2c) in Area 8 of the NNSS. Smoky was a weapons related test of the Plumbbob series (number 19) and part of the Department of Defense Exercise Desert Rock VII and VIII. The cultural resources effort involved the development of a historic context based on archival documents and engineering records, the inventory of the cultural resources in the Smoky test area and an associated military trench location in Areas 9 and 10, and an evaluation of the National Register eligibility of the cultural resources. The inventory of the Smoky test area resulted in the identification of structures, features, and artifacts related to the physical development of the test location and the post-test remains. The Smoky test area was designated historic district D104 and coincides with a historic archaeological site recorded as 26NY14794 and the military trenches designed for troop observation, site 26NY14795. Sites 26NY14794 and 26NY14795 are spatially discrete with the trenches located 4.3 km (2.7 mi) southeast of the Smoky ground zero. As a result, historic district D104 is discontiguous and in total it covers 151.4 hectares (374 acres). The Smoky test location, recorded as historic district D104 and historic sites 26NY14794 and 26NY14795, is the best preserved post-shot atmospheric nuclear tower test at the NNSS and possibly in the world. It is of local, national, and international importance due to nuclear testing’s pivotal role in the Cold War between the United States and the former Soviet Union. The district and sites are linked to the historic theme of atmospheric nuclear testing. D104 retains aspects of the engineering plan and design for the Smoky tower, instrument stations used to measure test effects, German and French personnel shelters, and military trenches. A total of 33 structures contribute to the significance of D104. Artifacts and features provide significant post-test information. Historic district D104 (discontiguous) and historic site 26NY14794 (the Smoky test area) are eligible for listing on the NRHP under Criteria A, B, C, and D. The historic site 26NY14795 (the Smoky military trenches) is eligible for listing under Criteria A, C, and D. Several items have been identified for removal by the CAU 550 investigation. However, none of them is associated with the Smoky atmospheric test, but with later activities in the area. The military trenches are not part of CAU 550 and no actions are planned there. A proposed closure of the Smoky test area with restrictions will limit access and contribute to the preservation of the cultural resources. It is recommended that the Smoky historic district and sites be included in the NNSS cultural resources monitoring program.

  8. ATRC Neutron Detector Testing Quick Look Report

    SciTech Connect (OSTI)

    Troy C. Unruh; Benjamin M. Chase; Joy L. Rempe

    2013-08-01

    As part of the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) program, a joint Idaho State University (ISU) / French Alternative Energies and Atomic Energy Commission (CEA) / Idaho National Laboratory (INL) project was initiated in FY-10 to investigate the feasibility of using neutron sensors to provide online measurements of the neutron flux and fission reaction rate in the ATR Critical Facility (ATRC). A second objective was to provide initial neutron spectrum and flux distribution information for physics modeling and code validation using neutron activation based techniques in ATRC as well as ATR during depressurized operations. Detailed activation spectrometry measurements were made in the flux traps and in selected fuel elements, along with standard fission rate distribution measurements at selected core locations. These measurements provide additional calibration data for the real-time sensors of interest as well as provide benchmark neutronics data that will be useful for the ATR Life Extension Program (LEP) Computational Methods and V&V Upgrade project. As part of this effort, techniques developed by Prof. George Imel will be applied by Idaho State University (ISU) for assessing the performance of various flux detectors to develop detailed procedures for initial and follow-on calibrations of these sensors. In addition to comparing data obtained from each type of detector, calculations will be performed to assess the performance of and reduce uncertainties in flux detection sensors and compare data obtained from these sensors with existing integral methods employed at the ATRC. The neutron detectors required for this project were provided to team participants at no cost. Activation detectors (foils and wires) from an existing, well-characterized INL inventory were employed. Furthermore, as part of an on-going ATR NSUF international cooperation, the CEA sent INL three miniature fission chambers (one for detecting fast flux and two for detecting thermal flux) with associated electronics for assessment. In addition, Prof. Imel, ISU, has access to an inventory of Self-Powered Neutron Detectors (SPNDs) with a range of response times as well as Back-to-Back (BTB) fission chambers from prior research he conducted at the Transient REActor Test Facility (TREAT) facility and Neutron RADiography (NRAD) reactors. Finally, SPNDs from the National Atomic Energy Commission of Argentina (CNEA) were provided in connection with the INL effort to upgrade ATR computational methods and V&V protocols that are underway as part of the ATR LEP. Work during fiscal year 2010 (FY10) focussed on design and construction of Experiment Guide Tubes (EGTs) for positioning the flux detectors in the ATRC N-16 locations as well as obtaining ATRC staff concurrence for the detector evaluations. Initial evaluations with CEA researchers were also started in FY10 but were cut short due to reactor reliability issues. Reactor availability issues caused experimental work to be delayed during FY11/12. In FY13, work resumed; and evaluations were completed. The objective of this "Quick Look" report is to summarize experimental activities performed from April 4, 2013 through May 16, 2013.

  9. COSMO 09

    ScienceCinema (OSTI)

    None

    2011-10-06

    This year's edition of the annual Cosmo International Conference on Particle Physics and Cosmology -- Cosmo09 -- will be hosted by the CERN Theory Group from Monday September 7 till Friday September 11, 2009. The conference will take place at CERN, Geneva (Switzerland). The Cosmo series is one of the major venues of interaction between cosmologists and particle physicists. In the exciting LHC era, the Conference will be devoted to the modern interfaces between Fundamental and Phenomenological Particle Physics and Physical Cosmology and Astronomy. The Conference will be followed by the CERN TH Institute "Particle Cosmology" which will take place from Monday September 14 till Friday September 18, 2009. The CERN-TH Institutes are visitor programs intended to bring together scientists with similar interests and to promote scientific collaborations. If you wish to participate, please register on the Institute web page. Link to last editions: COSMO 07 (U. of Sussex), COSMO 08 (U. of Wisconsin) List of plenary speakers: Gianfranco Bertone, Pierre Binetruy, Francois Bouchet, Juerg Diemand, Jonathan Feng, Gregory Gabadadze, Francis Halzen, Steen Hannestad, Will Kinney, Johannes Knapp, Hiranya Peiris, Will Percival, Syksy Rasanen, Alexandre Refregier, Pierre Salati, Roman Scoccimarro, Michael Schubnell, Christian Spiering, Neil Spooner, Andrew Tolley, Matteo Viel. The plenary program is available on-line. Select "Preliminary programme" in the left menu and click on each plenary session to see details. Parallel sessions: Inflation, convenor: Andrew Liddle Dark matter, convenor: Marco Cirelli Dark energy and modified gravity, convenor: Kazuya Koyama CMB, LSS and cosmological parameters/models, convenor: Licia Verde String cosmology, convenor: Jim Cline Baryogenesis and leptogenesis, convenor: Mariano Quiros The submission of talk proposals is closed by now. The parallel session program is available on-line. Select "Preliminary programme" in the left menu and click on each parallel session title to see details. Posters. Participants willing to present a poster will be offered the opportunity to hang it in the hall, next to the main auditorium. The poster application is closed by now. The poster list is available on-line. Registration. On-line registration is open from January 16 till August 31 (click on the link in the left menu). There will be no registration fees. [Thanks to the generosity of EU's network "UniverseNet", we have some limited funds available for supporting the visit of a few young scientists who could not attend otherwise. The application for funding is closed by now. All applicants have already been informed of the success of their application.] Accomodation. Participants are expected to arrange their accomodation by themselves: some rooms with shower, wc and washbasin have been blocked in the CERN hostel for the conference (price: 58CHF/night). Unfortunately, all these rooms have already been booked. You can book a hotel in Geneva or in the area surrounding CERN using this list. If you book a hotel on the French side, be sure to have a passport or a visa valid also in France. All participants are expected to be in possession of a passport or a visa valid in Swizerland (if relevant), and to be covered by their own health insurance during their visit. Sponsors. This conference is receiving support from the European Community's Marie Curie Research and Training Network UniverseNet.

  10. Geological Repository Layout for Radioactive High Level Long Lived Waste in Argilite

    SciTech Connect (OSTI)

    Gaussen, J.L.

    2006-07-01

    In the framework of the 1991 French radioactive waste act, ANDRA has studied the feasibility of a geological repository in the argillite layer of the Bure site for high-level long-lived waste. This presentation is focused on the underground facilities that constitute the specific component of this project. The preliminary underground layout, which has been elaborated, is based on four categories of data: - the waste characteristics and inventory; - the geological properties of the host argillite; - the long term performance objectives of the repository; - the specifications in term of operation and reversibility. The underground facilities consist of two types of works: the access works (shafts and drifts) and the disposal cells. The function of the access works is to permit the implementation of two concurrent activities: the nuclear operations (transfer and emplacement of the disposal packages into the disposal cells) and the construction of the next disposal cells. The design of the drifts network which matches up to this function is also influenced by two other specifications: the minimisation of the drift dimensions in order to limit their influence on the integrity of the geological formation and the necessity of a safe ventilation in case of fire. The resulting layout is a network of 4 parallel drifts (2 of them being dedicated to the operation, the other two being dedicated to the construction activities). The average diameter of these access drifts is 7 meters. 4 shafts ensure the link between the surface and the underground. The most important function of the disposal cells is to contribute to the long-term performance of the repository. In this regard, the thermal and geotechnical considerations play an important role. The B wastes (intermediate level wastes) are not (or not very) exothermic. Consequently, the design of their disposal cells result mainly from geotechnical considerations. The disposal packages (made of concrete) are piled up in big cavities the diameter of which is about 10 meters and the length of which is about 250 meters. On the other hand, the design of the C waste disposal cells (vitrified waste) is mainly derived from their thermal power (about 500 W after a 60 year period of interim storage). The disposal cell is a tunnel the diameter of which is about 0,70 m and the length of which is about 40 m. The number of the disposal packages (made of steel) per cell, the spacing between two adjacent canisters within a given cell and the spacing between two adjacent cells are adjusted to limit the peak of temperature in the host formation at 100 deg. C. The disposal cells are also characterized by favourable design factors that would facilitate the potential retrieval of the wastes. The whole underground layout would represent a surface area of several km{sup 2}. (authors)

  11. Neutronics qualification of the Jules Horowitz reactor fuel by interpretation of the VALMONT experimental program - Transposition of the uncertainties on the reactivity of JHR with JEF2.2 and JEFF3.1.1

    SciTech Connect (OSTI)

    Leray, O.; Hudelot, J. P.; Antony, M.; Doederlein, C.; Santamarina, A.; Bernard, D.; Vaglio-Gaudard, C.

    2011-07-01

    The new European material testing Jules Horowitz Reactor (JHR), currently under construction in Cadarache center (CEA France), will use LEU (20% enrichment in {sup 235}U) fuels (U{sub 3}Si{sub 2} for the start up and UMoAl in the future) which are quite different from the industrial oxide fuel, for which an extensive neutronics qualification database has been established. The HORUS3D/N neutronics calculation scheme, used for the design and safety studies of the JHR, is being developed within the framework of a rigorous verification-validation-qualification methodology. In this framework, the experimental VALMONT (Validation of Aluminium Molybdenum uranium fuel for Neutronics) program has been performed in the MINERVE facility of CEA Cadarache (France), in order to qualify the capability of HORUS3D/N to accurately calculate the reactivity of the JHR reactor. The MINERVE facility using the oscillation technique provides accurate measurements of reactivity effect of samples. The VALMONT program includes oscillations of samples of UAl{sub x}/Al and UMo/Al with enrichments ranging from 0.2% to 20% and Uranium densities from 2.2 to 8 g/cm{sup 3}. The geometry of the samples and the pitch of the experimental lattice ensure maximum representativeness with the neutron spectrum expected for JHR. By comparing the effect of the sample with the one of a known fuel specimen, the reactivity effect can be measured in absolute terms and be compared to computational results. Special attention was paid to the rigorous determination and reduction of the experimental uncertainties. The calculational analysis of the VALMONT results was performed with the French deterministic code APOLLO2. A comparison of the impact of the different calculation methods, data libraries and energy meshes that were tested is presented. The interpretation of the VALMONT experimental program allowed the qualification of JHR fuel UMoAl8 (with an enrichment of 19.75% {sup 235}U) by the Minerve-dedicated interpretation tool: PIMS. The effect of energy meshes and evaluations put forward the JEFF3.1.1/SHEM scheme that leads to a better calculation of the reactivity effect of VALMONT samples. Then, in order to quantify the impact of the uncertainties linked to the basic nuclear data, their propagation from the cross section measurement to the final computational result was analysed in a rigorous way by using a nuclear data re-estimation method based on Gauss-Newton iterations. This study concludes that the prior uncertainties due to nuclear data (uranium, aluminium, beryllium and water) on the reactivity of the Begin Of Cycle (BOC) for the JHR core reach 1217 pcm at 2{sigma}. Now, the uppermost uncertainty on the JHR reactivity is due to aluminium. (authors)

  12. REMORA 3: The first instrumented fuel experiment with on-line gas composition measurement by acoustic sensor

    SciTech Connect (OSTI)

    Lambert, T.; Muller, E.; Federici, E.; Rosenkrantz, E.; Ferrandis, J. Y.; Tiratay, X.; Silva, V.; Machard, D.; Trillon, G.

    2011-07-01

    With the aim to improve the knowledge of nuclear fuel behaviour, the development of advanced instrumentation used during in-pile experiments in Material Testing Reactor (MTR) is necessary. To obtain data on high Burn-Up MOX fuel performance under transient operating conditions, especially in order to differentiate between the kinetics of fission gas and helium releases and to acquire data on the degradation of the fuel conductivity, a highly instrumented in-pile experiment called REMORA 3 has been conducted by CEA and IES (Southern Electronic Inst. - CNRS - Montpellier 2 Univ.). A rodlet extracted from a fuel rod base irradiated for five cycles in a French EDF commercial PWR has been re-instrumented with a fuel centerline thermocouple, a pressure transducer and an advanced acoustic sensor. This latter, patented by CEA and IES, is 1 used in addition to pressure measurement to determine the composition of the gases located in the free volume and the molar fractions of fission gas and helium. This instrumented fuel rodlet has been re-irradiated in a specific rig, GRIFFONOS, located in the periphery of the OSIRIS experimental reactor core at CEA Saclay. First of all, an important design stage and test phases have been performed before the irradiation in order to optimize the response and the accuracy of the sensors: - To control the influence of the temperature on the acoustic sensor behaviour, a thermal mock-up has been built. - To determine the temperature of the gas located in the acoustic cavity as a function of the coolant temperature, and the average temperature of the gases located in the rodlet free volume as a function of the linear heat rate, thermal calculations have been achieved. The former temperature is necessary to calculate the molar fractions of the gases and the latter is used to calculate the total amount of released gas from the internal rod pressure measurements. - At the end of the instrumented rod manufacturing, specific internal free volume and pressure measurements have been carried out. Preliminary calculations of the REMORA 3 experiments have been performed from these measurements, with the aim to determine free volume evolution as a function of linear heat rate history. - A tracer gas has been added to the filling gas in order to optimize the accuracy of the helium balance at the time of the post irradiation examination. The two phases of the REMORA 3 irradiation have been achieved at the end of 2010 in the OSIRIS reactor. Slight acoustic signal degradation, observed during the test under high neutron and gamma flux, has led to an efficiency optimization of the signal processing. The instrumentation ran smoothly and allowed to reach all the experimental objectives. After non destructive examination performed in the Osiris reactor pool, typically gamma spectrometry and neutron radiography, the instrumented rod and the device have been disassembled. Then the instrumented rod has been transported to the LECA facility in Cadarache Centre for post irradiation examination. The internal pressure and volume of the rodlet as well as precise gas composition measurements will be known after puncturing step performed in a hot cell of this facility. That will allow us to qualify the in-pile measurements and to finalize the data which will be used for the validation of the fuel behaviour computer codes. (authors)

  13. Sub-crop geologic map of pre-Tertiary rocks in the Yucca Flat and northern Frenchman Flat areas, Nevada Test Site, southern Nevada

    SciTech Connect (OSTI)

    Cole, J.C.; Harris, A.G.; Wahl, R.R.

    1997-10-02

    This map displays interpreted structural and stratigraphic relations among the Paleozoic and older rocks of the Nevada Test Site region beneath the Miocene volcanic rocks and younger alluvium in the Yucca Flat and northern Frenchman Flat basins. These interpretations are based on a comprehensive examination and review of data for more than 77 drillholes that penetrated part of the pre-Tertiary basement beneath these post-middle Miocene structural basins. Biostratigraphic data from conodont fossils were newly obtained for 31 of these holes, and a thorough review of all prior microfossil paleontologic data is incorporated in the analysis. Subsurface relationships are interpreted in light of a revised regional geologic framework synthesized from detailed geologic mapping in the ranges surrounding Yucca Flat, from comprehensive stratigraphic studies in the region, and from additional detailed field studies on and around the Nevada Test Site. All available data indicate the subsurface geology of Yucca Flat is considerably more complicated than previous interpretations have suggested. The western part of the basin, in particular, is underlain by relics of the eastward-vergent Belted Range thrust system that are folded back toward the west and thrust by local, west-vergent contractional structures of the CP thrust system. Field evidence from the ranges surrounding the north end of Yucca Flat indicate that two significant strike-slip faults track southward beneath the post-middle Miocene basin fill, but their subsurface traces cannot be closely defined from the available evidence. In contrast, the eastern part of the Yucca Flat basin is interpreted to be underlain by a fairly simple north-trending, broad syncline in the pre-Tertiary units. Far fewer data are available for the northern Frenchman Flat basin, but regional analysis indicates the pre-Tertiary structure there should also be relatively simple and not affected by thrusting. This new interpretation has implications for ground water flow through pre-Tertiary rocks beneath the Yucca Flat and northern Frenchman Flat areas, and has consequences for ground water modeling and model validation. Our data indicate that the Mississippian Chainman Shale is not laterally extensive confining unit in the western part of the basin because it is folded back onto itself by the convergent structures of the Belted Range and CP thrust systems. Early and Middle Paleozoic limestone and dolomite are present beneath most of both basins and, regardless of structural complications, are interpreted to form a laterally continuous and extensive carbonate aquifer. Structural culmination that marks the French Peak accommodation zone along the topographic divide between the two basins provides a lateral pathway through highly fractured rock between the volcanic aquifers of Yucca Flat and the regional carbonate aquifer. This pathway may accelerate the migration of ground-water contaminants introduced by underground nuclear testing toward discharge areas beyond the Nevada Test Site boundaries. Predictive three-dimensional models of hydrostratigraphic units and ground-water flow in the pre-Tertiary rocks of subsurface Yucca Flat are likely to be unrealistic due to the extreme structural complexities. The interpretation of hydrologic and geochemical data obtained from monitoring wells will be difficult to extrapolate through the flow system until more is known about the continuity of hydrostratigraphic units. 1 plate

  14. Cleanup of Nuclear Licensed Facility 57

    SciTech Connect (OSTI)

    Jeanjacques, Michel; Bremond, Marie Pierre; Marchand, Carole; Poyau, Cecile; Viallefont, Cecile; Gautier, Laurent; Masure, Frederic

    2008-01-15

    This summary describes the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. The French atomic energy commission's center at Fontenay aux Roses (CEA-FAR) was created in 1946 to house pile ZOE. Laboratories for fuel cycle research were installed in existing buildings at the site. Work was later concentrated on spent fuel reprocessing, in a pilot workshop referred to as the 'Usine Pu'. In the early sixties, after the dismantling of these first generation facilities, a radiochemistry laboratory dedicated to research and development work on reprocessing was constructed, designated Building 18. During the same decade, more buildings were added: Building 54, storehouses and offices, Building 91, a hall and laboratories for chemical engineering research on natural and depleted uranium. Together, these three building constitute NLF 57. Building 18 architecture featured four similar modules. Each module had three levels: a sub-level consisting of technical galleries and rooms for the liquid effluent tanks, a ground floor and roof space in which the ventilation was installed. Offices, change rooms, four laboratories and a hall were situated on the ground floor. The shielded lines were installed in the laboratories and the halls. Construction of the building took place between 1959 and 1962, and its commissioning began in 1961. The research and development programs performed in NLF 57 related to studies of the reprocessing of spent fuel, including dry methods and the Purex process, techniques for the treatment of waste (vitrification, alpha waste decontamination, etc.) as well as studies and production of transuranic elements for industry and research. In addition to this work, the necessary methods of analysis for monitoring it were also developed. The research and development program finally ended on 30 June 1995. The NLF 57 cleanup program was intended to reduce the nuclear and conventional hazards and minimize the quantities of HLW and MLW during the subsequent dismantling work. To facilitate the organization of the cleanup work, it was divided into categories by type: - treatment and removal of nuclear material, - removal of radioactive sources, - treatment and removal of aqueous liquid waste, - treatment and removal of organic effluents, - treatment and removal of solid waste, - pumping out of the PETRUS tank, - flushing and decontamination of the tanks, - cleanup of Buildings 18 and 91/54. To estimate the cost of the operations and to monitor the progress of the work, an indicator system was put in place based on work units representative of the operation. The values of the work units were periodically updated on the basis of experience feedback. The cleanup progress is now 92% complete (06/12/31): - treatment and removal of nuclear material: 100%, - removal of radioactive sources: 100%, - treatment and removal of aqueous liquid waste: 64%, - treatment and removal of organic effluents: 87%, - treatment and removal of solid waste: 99%, - pumping out of the PETRUS tank: 69%, - flushing and decontamination of tank: 75%, - section cleaning of Buildings 18 and 91/: 90%. The DRSN/SAFAR is the delegated Project Owner for cleanup and dismantling operations. It is also the prime contractor for the cleanup and dismantling operations. SAFAR itself is responsible for operations relating to the CEA activity and those with technical risks (Removal of nuclear materials, Removal of radioactive sources, Pumping out plutonium and transuranic contaminated solvent and Flushing and decontamination of tanks and pipes). All other operations are sub-contracted to specialist companies. The NLF57 cleanup program as executed is capable of attaining activity levels compatible with a future dismantling operation using known and mastered techniques and producing a

  15. RADIOACTIVE WASTE MANAGEMENT IN THE USSR: A REVIEW OF UNCLASSIFIED SOURCES, 1963-1990

    SciTech Connect (OSTI)

    Bradley, D. J.; Schneider, K. J.

    1990-03-01

    The Soviet Union operates a vast and growing radioactive waste management system. Detailed information on this system is rare and a general overall picture only emerges after a review of a great deal of literature. Poor waste management practices and slow implementation of environmental restoration activities have caused a great deal of national concern. The release of information on the cause and extent of an accident involving high-level waste at the Kyshtym production reactor site in 1957, as well as other contamination at the site, serve to highlight past Soviet waste management practices. As a result, the area of waste management is now receiving greater emphasis, and more public disclosures. Little is known about Soviet waste management practices related to uranium mining, conversion, and fuel fabrication processes. However, releases of radioactive material to the environment from uranium mining and milling operations, such as from mill tailings piles, are causing public concern. Official Soviet policy calls for a closed fuel cycle, with reprocessing of power reactor fuel that has been cooled for five years. For power reactors, only VVER-440 reactor fuel has been reprocessed in any significant amount, and a decision on the disposition of RBMK reactor fuel has been postponed indefinitely. Soviet reprocessing efforts are falling behind schedule; thus longer storage times for spent fuel will be required, primarily at multiple reactor stations. Information on reprocessing in the Soviet Union has been severely limited until 1989, when two reprocessing sites were acknowledged by the Soviets. A 400-metric ton (MT) per year reprocessing facility, located at Kyshtym, has been operational since 1949 for reprocessing production reactor fuel. This facility is reported to have been reprocessing VVER-440 and naval reactor fuel since 1978, with about 2000 MT of VVER-440 fuel being reprocessed by July 1989. A second facility, located near Krasnoyarsk and having a 1500 MT per year capacity as the first of several modules, was about 30% completed by July 1989. The completion of this plant was subsequently "indefinitely postponed." The initial reprocessing scheme at the Kyshtym site used sodium uranyl acetate precipitation from fuel dissolved in nitric acid solutions. The basic method~ ology now appears to be based on the conventional PUREX process. Dry reprocessing on a pilot or laboratory scale has been under way in Dimitrovgrad since 1984, and a larger unit is now being built, according to the French CEA. Perhaps significantly, much research is being done on partitioning high-level waste into element fractions. The Soviets appear to have the technology to remove radioactive noble gases released during reprocessing operations; however, there are no indications of its implementation. Millions of curies of liquid low- and intermediate-level wastes have been disposed of by well injection into underground areas where they were supposedly contained by watertight rock strata. Some gaseous wastes were also disposed of by well injection. This practice is not referred to in recent literature and thus may not be widely used today. Rather, it appears that these waste streams are now first treated to reduce volume, and then solidified using bitumen or concrete. These solidified liquid wastes from Soviet nuclear power reactor operations, along with solid wastes, are disposed of in shallow-land burial sites located at most large power reactor stations. In addition, 35 shallow-land burial sites have been alluded to by the Soviets for disposal of industrial, medical, and research low-level wastes as well as ionization sources. Research on tritium-bearing and other gaseous wastes is mentioned, as well as a waste minimization program aimed at reducing the volume of waste streams by 30%. The Soviets have announced that their high-level waste management plan is to 1) store liquid wastes for 3-5 years; 2) incorporate the waste into glass (at a final glass volume of 100-150 liters/MT of fuel reprocessed); 3) set it aside in air-cooled storage

  16. Technical Data to Justify Full Burnup Credit in Criticality Safety Licensing Analysis

    SciTech Connect (OSTI)

    Enercon Services, Inc.

    2011-03-14

    Enercon Services, Inc. (ENERCON) was requested under Task Order No.2 to identify scientific and technical data needed to benchmark and justify Full Burnup Credit, which adds 16 fission products and 4 minor actinides1 to Actinide-Only burnup credit. The historical perspective for Full Burnup Credit is discussed, and interviews of organizations participating in burnup credit activities are summarized as a basis for identifying additional data needs and making recommendation. Input from burnup credit participants representing two segments of the commercial nuclear industry is provided. First, the Electric Power Research Institute (EPRI) has been very active in the development of Full Burnup Credit, representing the interests of nuclear utilities in achieving capacity gains for storage and transport casks. EPRI and its utility customers are interested in a swift resolution of the validation issues that are delaying the implementation of Full Burnup Credit [EPRI 2010b]. Second, used nuclear fuel storage and transportation Cask Vendors favor improving burnup credit beyond Actinide-Only burnup credit, although their discussion of specific burnup credit achievements and data needs was limited citing business sensitive and technical proprietary concerns. While Cask Vendor proprietary items are not specifically identified in this report, the needs of all nuclear industry participants are reflected in the conclusions and recommendations of this report. In addition, Oak Ridge National Laboratory (ORNL) and Sandia National Laboratory (SNL) were interviewed for their input into additional data needs to achieve Full Burnup Credit. ORNL was very open to discussions of Full Burnup Credit, with several telecoms and a visit by ENERCON to ORNL. For many years, ORNL has provided extensive support to the NRC regarding burnup credit in all of its forms. Discussions with ORNL focused on potential resolutions to the validation issues for the use of fission products. SNL was helpful in ENERCON's understanding of the difficult issues related to obtaining and analyzing additional cross section test data to support Full Burnup Credit. A PIRT (Phenomena Identification and Ranking Table) analysis was performed by ENERCON to evaluate the costs and benefits of acquiring different types of nuclear data in support of Full Burnup Credit. A PIRT exercise is a formal expert elicitation process with the final output being the ranking tables. The PIRT analysis (Table 7-4: Results of PIRT Evaluation) showed that the acquisition of additional Actinide-Only experimental data, although beneficial, was associated with high cost and is not necessarily needed. The conclusion was that the existing Radiochemical Assay (RCA) data plus the French Haut Taux de Combustion (HTC)2 and handbook Laboratory Critical Experiment (LCE) data provide adequate benchmark validation for Actinide-Only Burnup Credit. The PIRT analysis indicated that the costs and schedule to obtain sufficient additional experimental data to support the addition of 16 fission products to Actinide-Only Burnup Credit to produce Full Burnup Credit are quite substantial. ENERCON estimates the cost to be $50M to $100M with a schedule of five or more years. The PIRT analysis highlights another option for fission product burnup credit, which is the application of computer-based uncertainty analyses (S/U - Sensitivity/Uncertainty methodologies), confirmed by the limited experimental data that is already available. S/U analyses essentially transform cross section uncertainty information contained in the cross section libraries into a reactivity bias and uncertainty. Recent work by ORNL and EPRI has shown that a methodology to support Full Burnup Credit is possible using a combination of traditional RCA and LCE validation plus S/U validation for fission product isotopics and cross sections. Further, the most recent cross section data (ENDF/B-VII) can be incorporated into the burnup credit codes at a reasonable cost compared to the acquisition of equivalent experimental data. ENERCON concludes that even with the costs of code data library updating, the use of S/U analysis methodologies could be accomplished on a shorter schedule and a lower cost than the gathering of sufficient experimental data. ENERCON estimates of the costs of an updated S/U computer code and data suite are $5M to $10M with a schedule of two to three years. Recent ORNL analyses using the S/U analysis method show that the bias and uncertainty values for fission product cross sections are smaller than previously expected. This result is confirmed by a similar EPRI approach using different data and computer codes. ENERCON also found that some issues regarding the implementation of burnup credit appear to have been successfully resolved especially the axial burnup profile issue and the depletion parameter issue. These issues were resolved through data gathering activities at the Yucca Mountain Project and ORNL.

  17. Worksheet

    U.S. Energy Information Administration (EIA) Indexed Site

    UTILITY_ID","UTILITY_NAME","TRANSLINE_NO","TERMINAL_LOC_FROM","TERMINAL_LOC_TO","PERCENT_OWNED","LINE_LENGTH","LINE_TYPE","VOLTAGE_TYPE","VOLTAGE_OPERATING","VOLTAGE_DESIGN","CONDUCTOR_SIZE","CONDUCTOR_MAT_TYPE","CONDUCTOR_CONFIG","CIRCUIT_PERSTRUCT_PRES","CIRCUIT_PERSTRUCT_ULT","POLE_TOWER_TYPE","RATED_CAPACITY","LAND_LANDRIGHT_COSTS","POLE_TOWER_FIXTURE_COSTS","CONDUCTOR_DEVICE_COSTS","CONSTRUCTION_ETC_COSTS","TOTAL_LINE_COSTS","IN_SERVICE_DATE" 2003,1015,"Austin City of",1,"Northland","Magnesium Plant",100,4.11,"OH","AC",138,138,795,"ACSR Drake/ACSS Rail","Single",1,2,"Steel & Wood Poles",215,0,17500,8000,19500,45000,"application/vnd.ms-excel" 2003,1015,"Austin City of",2,"Grove","Met Center",100,3.1,"OH","AC",138,138,795,"ASCR Drake","Double",1,1,"Steel Pole",430,0,30000,10000,35000,75000,"application/vnd.ms-excel" 2003,1015,"Austin City of",3,"Dessau","Daffin Gin",100,6.01,"OH","AC",138,138,795,"ASCR Drake","Single",1,1,"Steel Pole",215,0,60000,15000,40000,115000,"application/vnd.ms-excel" 2003,1015,"Austin City of",4,"Burleson","AMD",100,2.2,"OH","AC",138,138,795,"ACR Drake","Double",2,2,"Steel Pole",430,0,75000,55000,120000,250000,"application/vnd.ms-excel" 2003,1015,"Austin City of",5,"Bergstrom","Kingsberry",100,4.2,"OH","AC",138,138,795,"ASCR Drake/AAAC","Single",1,2,"Steel & Wood Poles",215,0,75000,35000,340000,450000,"application/vnd.ms-excel" 2003,1015,"Austin City of",6,"Mcneil","Magnesium Plant",100,3.24,"OH","AC",138,138,795,"ACSR Drake","Double",1,2,"Steel Pole & Steel Tower",430,0,380000,76000,644000,1100000,"application/vnd.ms-excel" 2003,1015,"Austin City of",7,"Summit","Magnesium Plant",100,2.18,"OH","AC",138,138,795,"ACSR Drake","Double",1,2,"Steel Pole & Steel Tower",430,0,265000,125000,410000,800000,"application/vnd.ms-excel" 2003,1307,"Basin Electric Power Coop",1,"Rapid City","New Underwood",65,18.55,"OH","AC",230,230,1272,"ACSR","Single",1,1,"Single Pole, Steel",460,0,0,0,5300000,5300000,"application/vnd.ms-excel" 2003,1586,"Bentonville City of",1,"AEP/SWEPCO","City Substation F",100,1,"OH","AC",161,161,477,"ACSR","Single",1,1,"Wood and Steel Single Pole",199,18000,81522,28082,214516,342120,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",1,"Coppell","Lewisville",100,7.03,"OH","AC",138,138,1033,"ACSR","Double",1,1,"Concrete/Steel Single Pole",485,17577.55,2527717,537265.96,956475.39,4039035.9,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",2,"Boyd","Newark",100,1.8,"OH","AC",138,138,795,"ACSR","Single",2,2,"Concrete/Steel Single Pole",215,133929.08,538282.3,131112.75,246577.6,1049901.73,"application/vnd.ms-excel" 2003,2172,"Brazos Electric Power Coop",3,"Cedar Hill","Sardis",100,5.1,"OH","AC",138,138,795,"ACSR","Single",1,1,"Concrete Si ngle Ploe",215,24515.26,652910.22,246676.96,560582.43,1484684.87,"application/vnd.ms-excel" 2003,5580,"East Kentucky Power Coop Inc",1,"Jamestown Tap","Jamestown Tap",100,0.47,"OH","AC",161,161,556.5,"ACSR","Single",1,1,"Wood Single Pole",292,43326,160508,68789,0,272623,"application/vnd.ms-excel" 2003,5580,"East Kentucky Power Coop Inc",2,"Pulaski Co. Tap","Pulaski Co. Tap",100,5.88,"OH","AC",161,161,795,"ACSR","Single",1,1,"Wood H-Frame Structure",367,494183,1092462,468198,0,2054843,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",1,"Shoal Creek","Spout Spring",100,10.83,"OH","AC",230,230,1351,"ACSR","Single",1,1,"Concrete, Single Pole & Steel",602,1277945,1685271,444690,6047603,9455509,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",2,"Dresden","Yellowdirt",100,9.5,"OH","AC",230,230,795,"ACSR","Double",1,1,"Concrete, Single Pole",866,870826,772876,375515,3649376,5668593,"application/vnd.ms-excel" 2003,7197,"Georgia Transmission Corp",3,"East Moultrie","West Valdosta",100,38.46,"OH","AC",230,230,1622,"ACSR","Single",1,1,"Concrete, Single Pole",596,1191168,2829632,1476802,10279078,15776680,"application/vnd.ms-excel" 2003,7490,"Grand River Dam Authority",1,"Cowskin","Grove PSO",100,4.5,"OH","AC",138,138,795,"ACSR","Single/Twisted",1,1,"Wood Pole",223,287671,135402,156769,880890,1460732,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",1,"BASTROP","AUSTIN",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,9155828,155817297,37044659,47228709,249246493,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",2,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",3,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",4,"BASTROP","AUSTROP",100,0.32,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",5,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",6,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",7,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",8,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",9,"CANYON","SAN MARCOS/LOCKHART",100,0.31,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",10,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",11,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",12,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",13,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",14,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",15,"CICO","HELOTES",100,4,"OH","AC",138,138,795,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",16,"LOCKHART","DUMP HILL",100,1.6,"OH","AC",138,138,795,"ACSR","Single",1,1,"Concrete Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",17,"HILL POWER STATION","NUECES BAY",100,17.3,"OH","AC",138,138,795,"ACSR","Double",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",18,"NORTH OAK PARK","LON HILL",100,14.9,"OH","AC",138,138,795,"ACSR","Double",1,1,"Wood Pole",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",19,"STATE HIGHTWAY 80",,100,0.38,"OH","AC",138,138,211.5,"ACSR","Single",1,1,"Wood H-Frame Structure",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",20,"STATE HIGHWAY 80",,100,0.38,"OH","AC",138,138,211.5,"ACSR","Single",1,1,"Wood H-Frame Structure",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",21,"STERLING/MITCHELL LINE","TWINN BUTTES",100,135.08,"OH","AC",345,345,1590,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",22,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",23,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",24,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",25,"VERDE CREEK","KERRVILLE STADIUM",100,0.1,"OH","AC",138,138,336,"ACSR","Double",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",26,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",27,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",28,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",29,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",30,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,11269,"Lower Colorado River Authority",31,"ZORN","MCCARTY LANE",100,4.2,"OH","AC",138,138,1433.6,"ACSR","Single",1,1,"Steel Tower",,0,0,0,0,0,"application/vnd.ms-excel" 2003,15143,"Platte River Power Authority",1,"Rawhide","Timberline West",100,31.63,"OH","AC",230,230,954,"ACSR","Single",2,2,"Steel/Tower & Pole",378,5553,1928767,2385430,251850,4571600,"application/vnd.ms-excel" 2003,15159,"Plymouth City of",1,"Mullet River Sub","Sub # 1",100,0.8,"OH","AC",138,138,336.4,"ACSR","SINGLE",1,1,"Steel Double Pole",33,0,0,0,1492139,1492139,"application/vnd.ms-excel" 2003,16534,"Sacramento Municipal Util Dist",1,"Natomas","Elverta",100,4.3,"OH","AC",230,230,954,"Aluminum","Single",1,1,"Steel Tower",316,0,0,0,0,0,"application/vnd.ms-excel" 2003,17543,"South Carolina Pub Serv Auth",1,"Rainey - Anderson (Duke) #1","Rainey - Anderson (Duke) #1",100,9.51,"OH","AC",230,230,1272,"ACSR","Double",2,2,"Steel / Tower",956,840152,1230361,1207282,22364,3300159,"application/vnd.ms-excel" 2003,17543,"South Carolina Pub Serv Auth",2,"Rainey - Anderson (Duke) #2","Rainey - Anderson (Duke) #2",100,9.51,"OH","AC",230,230,1272,"ACSR","Double",2,2,"Steel / Tower",956,840152,1230361,1207282,22364,3300159,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",1,"West Ringgold","Center Point",100,7.94,"OH","AC",115,230,954,"ASCR","Single",1,2,"Steel Tower",,2086252,5658529,1502763,3053959,12301503,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",2,"NE Johnson City--Erwin 161kV T","Jonesborough 161 kV SS",100,0.28,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,11050,191917,894933,714987,1812887,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",3,"Elizabethton","Pandara-Shouns",100,15.12,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,282232,1797686,537733,2057572,4675223,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",4,"Sullivan","Blountville",100,0.63,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,547521,1134556,788061,1224067,3694205,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",5,"Pin Hook","Structure E 104A (NES)",100,1.74,"OH","DC",161,161,2034.5,"ASCR","Single",1,2,"Steel Tower",,179775,881877,641976,270782,1974410,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",6,"Dug Gap 115 kV SS","Center Point 230 kV SS",100,4.49,"OH","AC",115,230,954,"ASCR","Single",2,2,"Steel Tower",,3939251,3451555,545558,1026021,8962385,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",7,"Chickamauga-Ridgedale","Hawthorne 161 kV SS",100,2.82,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,87206,533582,342640,584799,1548227,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",8,"Ft. Loudoun-Elza 161 kV TL","Spallation Neutron Source 161",100,3.92,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,2972,639541,373150,469765,1485428,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",9,"Leake","Sebastapol SW STA 161 kV",100,0.77,"OH","AC",161,161,636,"ASCR","Single",2,2,"Steel Tower",,36158,236368,103374,167311,543211,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",10,"Sebasatpol 161 kV Switching St","Five Point 161 kV Substation",100,0.13,"OH","AC",161,230,954,"ASCR","Single",1,1,"Steel Tower",,917304,1772761,931352,1477668,5099085,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",11,"Structure 170A","Structure 174",100,0.73,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,0,445863,79638,194574,720075,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",12,"Ramer-Hickory Valley 161 kV TL","Middleton 46 kV SS",100,6.81,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,566805,1162854,447607,787813,2965079,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",13,"Lowndes-Miller","Valley View",100,0.46,"OH","AC",500,500,954,"ASCR","Triple",1,2,"Steel Tower",,0,688737,255237,341129,1285103,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",14,"Sweetwater 161 kV SS","Madisonville 161 kV SS",100,8.95,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Tower",,1066219,1474937,466681,797814,3805651,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",15,"East Point 500 kV SS","Hanceville 161 kV TL",100,11.25,"OH","AC",161,161,1351.5,"ASCR","Single",1,2,"Steel Tower",,1416513,1442382,606534,1427424,4892853,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",16,"W Cookeville-Crossville 161 kV","W. Crossville SS",100,4.37,"OH","AC",161,161,954,"ASCR","Single",1,2,"Steel Tower",,267463,1112667,651963,964407,2996500,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",17,"East Shelbyville-Unionville","Deason 161 kV SS",100,5.09,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,1071199,931797,430714,320721,2754431,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",18,"Kentucky Hydro","Barkley Hydro",100,2,"OH","AC",161,161,2034.5,"ACSR","Single",1,1,"Steel Tower",,2845,406947,90111,155401,655304,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",19,"MEC Sw Station","Trinity Substation",100,2.9,"OH","AC",161,161,954,"ACSS","Single",2,2,"Steel Tower",,0,604526,474640,608702,1687868,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",20,"Hickory Valley Selmer 161 kV T","North Selmer 161 kV SS",100,4.88,"OH","AC",161,161,636,"ASCR","Single",1,1,"Steel Tower",,357578,632244,368993,899046,2257861,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",21,"Trinity","Morgan Energy Center",100,2.98,"OH","AC",161,161,1590,"ASCR","Single",2,2,"Steel Tower",,7155,647789,386671,513831,1555446,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",22,"MEC","Finley",100,0.61,"OH","AC",161,161,954,"ASCR","Single",1,2,"Steel Tower",,9879,303540,156165,181613,651197,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",23,"Pickwick-South Jackson","Magic Valley",100,1.38,"OH","AC",161,161,954,"ASCR","Single",1,1,"Steel Pole",,78377,284367,113237,237716,713697,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",24,"Wolf Creek-Choctaw 500 kV TL","Reliant French Camp Gener Plt",100,0.11,"OH","AC",500,500,954,"ASCR","Triple",1,2,"Steel Tower",,0,863770,411493,891161,2166424,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",25,"Widows Creek Ft. Payne 161 kV","Flat Rock 161 kV SS",100,2.05,"OH","AC",161,161,397.5,"ASCR","Single",1,1,"Steel Tower",,130460,443384,182965,410228,1167037,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",26,"Volunteer-Cherokee HP 161 kV T","Oakland 161 kV SS",100,0.5,"OH","AC",161,161,1351,"ASCR","Single",1,2,"Steel Tower",,0,159020,71787,133784,364591,"application/vnd.ms-excel" 2003,18642,"Tennessee Valley Authority",27,"Cordell-Hull-Carthage 161 kV","South Carthage 161 kV SS",100,1.68,"OH","AC",161,161,636,"ASCR","Single",1,2,"Steel Tower",,0,209664,102390,256537,568591,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",1,"Arco","Sprectrum",100,5.89,"OH","AC",138,138,336.4,"ACSR","Single",1,1,"Wood Pole",91,37547.56,399750.8,416067.16,0,853365.52,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",2,"Hazel Dell Jct","Hazel Dell",100,3.12,"OH","AC",138,138,795,"ACSR","Single",1,1,"Wood Pole",158,72967.09,417464.37,285659.16,0,776090.62,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",3,"Red River","Tenaska Kiowa Sw",100,75.75,"OH","AC",345,345,795,"ACSR","Single",1,1,"Combination Pole",158,0,0,0,47569327.23,47569327.23,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",4,"Washita Sw","Blue Canyon",100,23.96,"OH","AC",138,138,1590,"ACSR","Single",1,1,"Wood Pole",239,0,0,0,5092171.22,5092171.22,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",5,"Limestone Jct","Limestone",100,0.5,"OH","AC",138,138,336.4,"ACSR","Single",1,1,"Wood Pole",91,25673.08,159253.08,77468.07,0,262394.23,"application/vnd.ms-excel" 2003,20447,"Western Farmers Elec Coop Inc",6,"OGE Sunset Jct","Sunset Corner",100,0.15,"OH","AC",161,161,336.4,"ACSR","Singel",1,1,"Wood Pole",91,0,29315.87,35224.01,0,64539.88,"application/vnd.ms-excel" 2003,27000,"Western Area Power Admin",1,"Shiprock","Four Corners",100,8.2,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",2,"Coolidge","Sundance 1 and 2",100,9.8,"OH","AC",230,230,954,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",3,"Structure 96/4","O/Banion 1",100,38,"OH","AC",230,230,,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",4,"Mead","Market Place",100,12.9,"OH","AC",525,525,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",5,"Bears Ears","Craig",100,1,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",6,"Glen Canyon Pumping Plant","Glen Canyon SW Yard",100,1,"OH","AC",345,345,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",7,"Baker","Bowman",22.96,53.96,"OH","AC",230,230,954,"ASCR",,1,1,"Wood H",,0,0,0,0,0 2003,27000,"Western Area Power Admin",8,"Basin Tap #2","Washburn",100,2.23,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",9,"Craig","Rifle",100,96,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",10,"Garrison","Basin Tap #1",100,20.97,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",11,"Everta","Roseville",100,13.3,"OH","AC",230,230,,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",12,"Griffith","McConnico",100,8,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",13,"McConnico","Peacock",100,29.4,"OH","AC",230,230,795,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",14,"Liberty","Buckeye",100,6.7,"OH","AC",230,230,1272,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",15,"Liberty","Parker",100,118.7,"OH","AC",230,230,1272,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",16,"Liberty","Estrella",100,10.8,"OH","AC",230,230,954,"ASCR",,2,2,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",17,"Liberty","Lone Batte",100,38.2,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",18,"Lone Butte","Sundance",100,38.4,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",19,"New Waddell","West Wing",100,10.1,"OH","AC",230,230,954,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",20,"South Point","Topock #1",100,6.46,"OH","AC",230,230,1590,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0 2003,27000,"Western Area Power Admin",21,"South Point","Topock #2",100,6.34,"OH","AC",230,230,1590,"ASCR",,1,1,"Steel Lattice",,0,0,0,0,0