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Sample records for r1 npp boreal

  1. Patterns of NPP, GPP, Respiration and NEP During Boreal Forest Succession

    SciTech Connect (OSTI)

    Goulden, Michael L.; McMillan, Andrew; Winston, Greg; Rocha, Adrian; Manies, Kristen; Harden, Jennifer W.; Bond-Lamberty, Benjamin

    2010-12-15

    We deployed a mesonet of year-round eddy covariance towers in boreal forest stands that last burned in ~1850, ~1930, 1964, 1981, 1989, 1998, and 2003 to understand how CO2 exchange changes during secondary succession.The strategy of using multiple methods, including biometry and micrometeorology, worked well. In particular, the three independent measures of NEP during succession gave similar results. A stratified and tiered approach to deploying eddy covariance systems that combines many lightweight and portable towers with a few permanent ones is likely to maximize the science return for a fixed investment. The existing conceptual models did a good job of capturing the dominant patterns of NPP, GPP, Respiration and NEP during succession. The initial loss of carbon following disturbance was neither as protracted nor large as predicted. This muted response reflects both the rapid regrowth of vegetation following fire and the prevalence of standing coarse woody debris following the fire, which is thought to decay slowly. In general, the patterns of forest recovery from disturbance should be expected to vary as a function of climate, ecosystem type and disturbance type. The NPP decline at the older stands appears related to increased Rauto rather than decreased GPP. The increase in Rauto in the older stands does not appear to be caused by accelerated maintenance respiration with increased biomass, and more likely involves increased allocation to fine root turnover, root metabolism, alternative forms of respiration, mycorrhizal relationships, or root exudates, possibly associated with progressive nutrient limitation. Several studies have now described a similar pattern of NEP following boreal fire, with 10-to-15 years of modest carbon loss followed by 50-to-100 years of modest carbon gain. This trend has been sufficiently replicated and evaluated using independent techniques that it can be used to quantify the likely effects of changes in boreal fire frequency and

  2. Boreal Renewable Energy Development | Open Energy Information

    Open Energy Info (EERE)

    Energy Development Jump to: navigation, search Name: Boreal Renewable Energy Development Place: Arlington, Massachusetts Region: Greater Boston Area Sector: Solar, Wind Year...

  3. Boreal Renewable Energy | Open Energy Information

    Open Energy Info (EERE)

    Energy Jump to: navigation, search Name: Boreal Renewable Energy Place: Acton, Massachusetts Zip: 1720 Sector: Hydro, Renewable Energy, Solar, Wind energy Product: Renewable Energy...

  4. Emission and transport of cesium-137 from boreal biomass burning...

    Office of Scientific and Technical Information (OSTI)

    from boreal biomass burning in the summer of 2010 Citation Details In-Document Search Title: Emission and transport of cesium-137 from boreal biomass burning in the summer ...

  5. Effects of warming on the structure and function of a boreal black spruce forest

    SciTech Connect (OSTI)

    Stith T.Gower

    2010-03-03

    A strong argument can be made that there is a greater need to study the effect of warming on boreal forests more than on any other terrestrial biome. Boreal forests, the second largest forest biome, are predicted to experience the greatest warming of any forest biome in the world, but a process-based understanding of how warming will affect the structure and function of this economically and ecologically important forest biome is lacking. The effects of warming on species composition, canopy structure and biogeochemical cycles are likely to be complex; elucidating the underlying mechanisms will require long-term whole-ecosystem manipulation to capture all the complex feedbacks (Shaver et al. 2000, Rustad et al. 2001, Stromgren 2001). The DOE Program for Ecosystem Research funded a three year project (2002-2005) to use replicated heated chambers on soil warming plots in northern Manitoba to examine the direct effects of whole-ecosystem warming. We are nearing completion of our first growing season of measurements (fall 2004). In spite of the unforeseen difficulty of installing the heating cable, our heating and irrigation systems worked extremely well, maintaining environmental conditions within 5-10% of the specified design 99% of the time. Preliminary data from these systems, all designed and built by our laboratory at the University of Wisconsin, support our overall hypothesis that warming will increase the carbon sink strength of upland boreal black spruce forests. I request an additional three years of funding to continue addressing the original objectives: (1) Examine the effect of warming on phenology of overstory, understory and bryophyte strata. Sap flux systems and dendrometer bands, monitored by data loggers, will be used to quantify changes in phenology and water use. (2) Quantify the effects of warming on nitrogen and water use by overstory, understory and bryophytes. (3) Compare effects of warming on autotrophic respiration and above- and belowground

  6. TCP Final Report: Measuring the Effects of Stand Age and Soil Drainage on Boreal Forest

    SciTech Connect (OSTI)

    Michael L. Goulden

    2007-05-02

    This was a 6-year research project in the Canadian boreal forest that focused on using field observations to understand how boreal forest carbon balance changes during recovery from catastrophic forest fire. The project began with two overarching goals: (1) to develop techniques that would all the year round operation of 7 eddy covariance sites in a harsh environment at a much lower cost than had previously been possible, and (2) to use these measurements to determine how carbon balance changes during secondary succession. The project ended in 2006, having accomplished its primary objectives. Key contributions to DOE during the study were: (1) Design, test, and demonstrate a lightweight, fully portable eddy flux system that exploits several economies of scale to allow AmeriFlux-quality measurements of CO{sub 2} exchange at many sites for a large reduction in cost (Goulden et al. 2006). (2) Added seven year-round sites to AmeriFlux, at a relatively low per site cost using the Eddy Covariance Mesonet approach (Goulden et al. 2006). These data are freely available on the AmeriFlux web site. (3) Tested and rejected the conventional wisdom that forests lose large amounts of carbon during the first decade after disturbance, then accumulate large amounts of carbon for {approx}several decades, and then return to steady state in old age. Rather, we found that boreal forests recovers quickly from fire and begins to accumulate carbon within {approx}5 years after disturbance. Additionally, we found no evidence that carbon accumulation declines in old stands (Goulden et al. 2006, Goulden et al. in prep). (4) Tested and rejected claims based on remote sensing observations (for example, Myneni et al 1996 using AVHRR) that regions of boreal forest have changed markedly in the last 20 years. Rather, we assembled a much richer data set than had been used in the past (eddy covariance observations, tree rings, biomass, NPP, AVHRR, and LandSat), which we used to establish that the

  7. 2210R1 ES&H Staff Assignments

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

    210 Appendix R1 Staff Assigned to ES&H Activities 1.0 Purpose This appendix provides information for current Environmental, Safety and Health (ES&H) related staff positions at Jefferson Lab. Other positions of responsibility are outlined on the various Division & Department's Organization Charts. * Section 2.0 - Contact Information for Hazard Issues * Section 3.0 - Contact Information for Responsible Positions * Section 4.0 - Councils and Committees * Section 5.0 - Division Safety

  8. Microsoft Word - DP_cover_and_front matter_R1_Draft_3.DOC | Department...

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

    R1Draft3.DOC Microsoft Word - DPcoverandfront matterR1Draft3.DOC PDF icon Microsoft Word - DPcoverandfront matterR1Draft3.DOC More Documents & Publications Microsoft ...

  9. Environmental Impact Assessment (EIA) Process of V1 NPP Decommissioning

    SciTech Connect (OSTI)

    Matejovic, Igor; Polak, Vincent

    2007-07-01

    Through the adoption of Governmental Resolution No. 801/99 the Slovak Republic undertook a commitment to shutdown units 1 and 2 of Jaslovske Bohunice V 1 NPP (WWER 230 reactor type) in 2006 and 2008 respectively. Therefore the more intensive preparation of a decommissioning documentation has been commenced. Namely, the VI NPP Conceptual Decommissioning Plan and subsequently the Environmental Impact Assessment Report of VI NPP Decommissioning were developed. Thus, the standard environmental impact assessment process was performed and the most suitable alternative of V1 NPP decommissioning was selected as a basis for development of further decommissioning documents. The status and main results of the environmental impact assessment process and EIA report are discussed in more detail in this paper. (authors)

  10. Microsoft Word - DOE-ID-INL-13-009 R1.docx

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

    ... R1 The atmospheric tracers sulfur ... such as plastic water bottles or other miscellaneous waste. ... Fuel would also be used in small portable generators where ...

  11. Lessons learnt from Ignalina NPP decommissioning project

    SciTech Connect (OSTI)

    NAISSE, Jean-Claude

    2007-07-01

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

  12. Microsoft Word - DOE-ID-INL-16-004 R1.docx

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

    of 4 CX Posting No.: DOE-ID-INL-16-004 R1 Original EC The proposed action would provide National & Homeland Security (N&HS) personnel with a new field station office near the ...

  13. Microsoft Word - DOE-ID-INL-14-042 R1.docx

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

    ... Laboratory Page 2 of 3 CX Posting No.: DOE-ID-INL-14-042 R1 Upgrade sub panel D (in ... radio bench Figure 2. Proposed SHARES Station Configuration at the SAF Building ...

  14. Microsoft Word - DOE-ID-INL-15-013 R1.docx

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

    R1 SECTION A. Project Title: Test Reactor Area (TRA)-774 Substation Equipment Upgrades ... Electricity for heat at the Advanced Test Reactor (ATR) heaters is fed from the substation ...

  15. Decreases in Soil Moisture and Organic Matter Quality Suppress Microbial Decomposition Following a Boreal Forest Fire

    SciTech Connect (OSTI)

    Holden, Sandra R.; Berhe, Asmeret A.; Treseder, Kathleen K.

    2015-08-01

    Climate warming is projected to increase the frequency and severity of wildfires in boreal forests, and increased wildfire activity may alter the large soil carbon (C) stocks in boreal forests. Changes in boreal soil C stocks that result from increased wildfire activity will be regulated in part by the response of microbial decomposition to fire, but post-fire changes in microbial decomposition are poorly understood. Here, we investigate the response of microbial decomposition to a boreal forest fire in interior Alaska and test the mechanisms that control post-fire changes in microbial decomposition. We used a reciprocal transplant between a recently burned boreal forest stand and a late successional boreal forest stand to test how post-fire changes in abiotic conditions, soil organic matter (SOM) composition, and soil microbial communities influence microbial decomposition. We found that SOM decomposing at the burned site lost 30.9% less mass over two years than SOM decomposing at the unburned site, indicating that post-fire changes in abiotic conditions suppress microbial decomposition. Our results suggest that moisture availability is one abiotic factor that constrains microbial decomposition in recently burned forests. In addition, we observed that burned SOM decomposed more slowly than unburned SOM, but the exact nature of SOM changes in the recently burned stand are unclear. Finally, we found no evidence that post-fire changes in soil microbial community composition significantly affect decomposition. Taken together, our study has demonstrated that boreal forest fires can suppress microbial decomposition due to post-fire changes in abiotic factors and the composition of SOM. Models that predict the consequences of increased wildfires for C storage in boreal forests may increase their predictive power by incorporating the observed negative response of microbial decomposition to boreal wildfires.

  16. Identifying the Proteins that Mediate the Ionizing Radiation Resistance of Deinococcus Radiodurans R1

    SciTech Connect (OSTI)

    Battista, John R

    2010-02-22

    The primary objectives of this proposal was to define the subset of proteins required for the ionizing radiation (IR) resistance of Deinococcus radiodurans R1, characterize the activities of those proteins, and apply what was learned to problems of interest to the Department of Energy.

  17. Preparation for Early Termination of Ignalina NPP Operation

    SciTech Connect (OSTI)

    Poskas, P.; Poskas, R.

    2003-02-26

    Seimas (Parliament of Lithuania) approved updated National Energy strategy where it is indicated that first Unit will be shutdown before the year 2005 and second Unit in 2009 if funding for decommissioning is available from EU and other donors. In accordance to Ignalina NPP Unit 1 Closure Law the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until year 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, o n the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned activities, licensing requirements for decommissioning, progress in preparation of the Final Decommissioning Plan is discussed.

  18. Integrating the Clearance in NPP Residual Material Management

    SciTech Connect (OSTI)

    Garcia-Bermejo, R.; Lamela, B.

    2008-01-15

    Previous Experiences in decommissioning projects are being used to optimize the residual material management in NPP, metallic scrap usually. The approach is based in the availability of a materials Clearance MARSSIM-based methodology developed and licensed in Spain. A typical project includes the integration of segregation, decontamination, clearance, quality control and quality assurance activities. The design is based in the clearance methodology features translating them into standard operational procedures. In terms of ecological taxes and final disposal costs, significant amounts of money could be saved with this type of approaches. The last clearance project managed a total amount of 405 tons scrap metal and a similar amount of other residual materials occupying a volume of 1500 m{sup 3}. After less than a year of field works 251 tons were finally recycled in a non-licensed smelting facility. The balance was disposed as LILW. In the planning phase the estimated cost savings were 4.5 Meuro. However, today a VLLW option is available in European countries so, the estimated cost savings are reduced to 1.2 Meuro. In conclusion: the application of materials clearance in NPP decommissioning lessons learnt to the NPP residual material management is an interesting management option. This practice is currently going on in Spanish NPP and, in a preliminary view, is consistent with the new MARSAME Draft. An interesting parameter is the cost of 1 m3 of recyclable scrap. The above estimates are very project specific because in the segregation process other residual materials were involved. If the effect of this other materials is removed the estimated Unit Cost were in this project around 1700 euro/m{sup 3}, this figure is clearly below the above VLLW disposal cost of 2600 euro. In a future project it appears feasible to descend to 839 euro/m{sup 3} and if it became routine values and is used in big Decommissioning projects, around 600 euro/m{sup 3} or below possibly could

  19. Historical trends and extremes in boreal Alaska river basins

    SciTech Connect (OSTI)

    Bennett, Katrina E.; Cannon, Alex J.; Hinzman, Larry

    2015-05-12

    Climate change will shift the frequency, intensity, duration and persistence of extreme hydroclimate events and have particularly disastrous consequences in vulnerable systems such as the warm permafrost-dominated Interior region of boreal Alaska. This work focuses on recent research results from nonparametric trends and nonstationary generalized extreme value (GEV) analyses at eight Interior Alaskan river basins for the past 50/60 years (1954/642013). Trends analysis of maximum and minimum streamflow indicates a strong (>+50%) and statistically significant increase in 11-day flow events during the late fall/winter and during the snowmelt period (late April/mid-May), followed by a significant decrease in the 11-day flow events during the post-snowmelt period (late May and into the summer). The AprilMayJune seasonal trends show significant decreases in maximum streamflow for snowmelt dominated systems (<50%) and glacially influenced basins (24% to 33%). Annual maximum streamflow trends indicate that most systems are experiencing declines, while minimum flow trends are largely increasing. Nonstationary GEV analysis identifies time-dependent changes in the distribution of spring extremes for snowmelt dominated and glacially dominated systems. Temperature in spring influences the glacial and high elevation snowmelt systems and winter precipitation drives changes in the snowmelt dominated basins. The Pacific Decadal Oscillation was associated with changes occurring in snowmelt dominated systems, and the Arctic Oscillation was linked to one lake dominated basin, with half of the basins exhibiting no change in response to climate variability. The paper indicates that broad scale studies examining trend and direction of change should employ multiple methods across various scales and consider regime dependent shifts to identify and understand changes in extreme streamflow within boreal forested watersheds of Alaska.

  20. Historical trends and extremes in boreal Alaska river basins

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

    Bennett, Katrina E.; Cannon, Alex J.; Hinzman, Larry

    2015-05-12

    Climate change will shift the frequency, intensity, duration and persistence of extreme hydroclimate events and have particularly disastrous consequences in vulnerable systems such as the warm permafrost-dominated Interior region of boreal Alaska. This work focuses on recent research results from nonparametric trends and nonstationary generalized extreme value (GEV) analyses at eight Interior Alaskan river basins for the past 50/60 years (1954/64–2013). Trends analysis of maximum and minimum streamflow indicates a strong (>+50%) and statistically significant increase in 11-day flow events during the late fall/winter and during the snowmelt period (late April/mid-May), followed by a significant decrease in the 11-day flowmore » events during the post-snowmelt period (late May and into the summer). The April–May–June seasonal trends show significant decreases in maximum streamflow for snowmelt dominated systems (<–50%) and glacially influenced basins (–24% to –33%). Annual maximum streamflow trends indicate that most systems are experiencing declines, while minimum flow trends are largely increasing. Nonstationary GEV analysis identifies time-dependent changes in the distribution of spring extremes for snowmelt dominated and glacially dominated systems. Temperature in spring influences the glacial and high elevation snowmelt systems and winter precipitation drives changes in the snowmelt dominated basins. The Pacific Decadal Oscillation was associated with changes occurring in snowmelt dominated systems, and the Arctic Oscillation was linked to one lake dominated basin, with half of the basins exhibiting no change in response to climate variability. The paper indicates that broad scale studies examining trend and direction of change should employ multiple methods across various scales and consider regime dependent shifts to identify and understand changes in extreme streamflow within boreal forested watersheds of Alaska.« less

  1. Historical trends and extremes in boreal Alaska river basins

    SciTech Connect (OSTI)

    Bennett, Katrina E.; Cannon, Alex J.; Hinzman, Larry

    2015-05-12

    Climate change will shift the frequency, intensity, duration and persistence of extreme hydroclimate events and have particularly disastrous consequences in vulnerable systems such as the warm permafrost-dominated Interior region of boreal Alaska. This work focuses on recent research results from nonparametric trends and nonstationary generalized extreme value (GEV) analyses at eight Interior Alaskan river basins for the past 50/60 years (1954/64–2013). Trends analysis of maximum and minimum streamflow indicates a strong (>+50%) and statistically significant increase in 11-day flow events during the late fall/winter and during the snowmelt period (late April/mid-May), followed by a significant decrease in the 11-day flow events during the post-snowmelt period (late May and into the summer). The April–May–June seasonal trends show significant decreases in maximum streamflow for snowmelt dominated systems (<–50%) and glacially influenced basins (–24% to –33%). Annual maximum streamflow trends indicate that most systems are experiencing declines, while minimum flow trends are largely increasing. Nonstationary GEV analysis identifies time-dependent changes in the distribution of spring extremes for snowmelt dominated and glacially dominated systems. Temperature in spring influences the glacial and high elevation snowmelt systems and winter precipitation drives changes in the snowmelt dominated basins. The Pacific Decadal Oscillation was associated with changes occurring in snowmelt dominated systems, and the Arctic Oscillation was linked to one lake dominated basin, with half of the basins exhibiting no change in response to climate variability. The paper indicates that broad scale studies examining trend and direction of change should employ multiple methods across various scales and consider regime dependent shifts to identify and understand changes in extreme streamflow within boreal forested watersheds of Alaska.

  2. On the influence of shrub height and expansion on boreal climate...

    Office of Scientific and Technical Information (OSTI)

    Title: On the influence of shrub height and expansion on boreal climate Authors: Bonfils, C ; Phillips, T ; Lawrence, D ; Cameron-Smith, P ; Riley, W ; Subin, Z Publication Date: ...

  3. Microsoft Word - DOE-ID-INL-16-049 R1.docx

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

    R1 SECTION A. Project Title: Materials and Fuels Complex Mobile Structure Decontamination and Decommissioning (D&D) and MFC Protected Area Intrusion Detection Upgrade SECTION B. Project Description and Purpose: The purpose of this revision is to capture project scope not included in the original Environmental Checklist (EC). Specifically, this revision adds the construction of three storm water dry wells to provide adequate storm water drainage for the site. Original EC: Security at Idaho

  4. Microsoft Word - DOE-ID-INL-16-050 R1.docx

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

    R1 SECTION A. Project Title: Advanced Test Reactor (ATR) Fuel Oil Leak Excavation and Cleanup SECTION B. Project Description and Purpose: The purpose of this revision is to expand the project scope to include asbestos disturbance and removal from the fuel line between Test Reactor Area (TRA)-627 and TRA-670. During excavation of the fuel line, asbestos containing insulation was discovered on the pipe. All other activities from the original Environmental Checklist (EC) remain the same, as

  5. DOE Acquisition Guide Chapter 16.2R1 (June 2014)

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

    Chapter 16.2R1 (June 2014) Performance Evaluation and Measurement Plans for Cost-Reimbursement, Non- Management and Operating Contracts [Reference: FAR 6, FAR 16, FAR 22, FAR 32, FAR 46, DEAR 915.404-4-72, DEAR 916.405-2, DEAR 970.1504-1, and Acquisition Guide Chapter 16.1] Overview The policy of the DOE is to maximize contractor performance and to align costs with performance through the use of performance-based management as a strategic contract management tool to plan for, manage, and

  6. Draft genome sequence of Raoultella terrigena R1Gly, a diazotrophic endophyte

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

    Schicklberger, M.; Shapiro, N.; Loqué, D.; Woyke, T.; Chakraborty, R.

    2015-06-11

    Raoultella terrigena R1Gly is a diazotrophic endophyte isolated from surface-sterilized roots of Nicotiana tabacum. The whole-genome sequence was obtained to investigate the endophytic characteristics of this organism at the genetic level, as well as to compare this strain with its close relatives. To our knowledge, this is the first genome obtained from the Raoultella terrigena species and only the third genome from the Raoultella genus, after Raoultella ornitholytic and Raoultella planticola. This genome will provide a foundation for further comparative genomic, metagenomic, and functional studies of this genus.

  7. Microsoft Word - DOE-ID-INL-16-031 R1.docx

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

    R1 SECTION A. Project Title: Install Energy Innovation Laboratory (EIL) (Idaho Falls [IF]-688) Entry Vestibule, Dock Area Staircase, and Door Canopies SECTION B. Project Description and Purpose: This revision of environmental checklist INL-16-031 is to capture additional project scope. Work would include adding canopies to doors on the south side of C-wing and the north and south sides of B-wing. These canopies would be located over the doors to shelter personnel from the weather and to reduce

  8. Microsoft Word - DOE-ID-INL-16-055 R1.docx

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

    5 R1 SECTION A. Project Title: Materials and Fuels Complex (MFC) Vault-Type Room SECTION B. Project Description and Purpose: The purpose of this revision to add the construction of a breezeway between the Irradiated Materials Characterization Laboratory (IMCL) and the vault type room (VTR). The breezeway will be constructed from concrete masonry unit (CMU) block. The breezeway will be approximately 6 ft. wide x 30 ft. long x 12 ft. high. An existing concrete walkway will be removed and a new

  9. FEASIBILITY AND EXPEDIENCE TO VITRIFY NPP OPERATIONAL WASTE

    SciTech Connect (OSTI)

    LIFANOV, F.A.; OJOVAN, M.I.; STEFANOVSKY, S.V.; BURCL, R.

    2003-02-27

    Operational radioactive waste is generated during routine operation of NPP. Process waste is mainly generated by treatment of water from reactor or ancillaries including spent fuel storage pools and some decontamination operations. Typical process wastes of pressurized water reactors (PWR or WWER) are borated water concentrates, whereas typical process wastes of boiling and RBMK type reactors are water concentrates with no boron content. NPP operational wastes are classified as low and intermediate level waste (LILW). NPP operational waste must be solidified in order to ensure safe conditions of storage and disposal. Currently the most promising solidification method for this waste is the vitrification technology. Vitrification of NPP operational waste is a relative new option being developed for last years. Nevertheless there is already accumulated operational experience on vitrifying low and intermediate level waste in Russian Federation at Moscow SIA ''Radon'' vitrification plant. This plant uses the most advanced type induction high frequency melters that facilitate the melting process and significantly reduce the generation of secondary waste and henceforth the overall cost. The plant was put into operation by the end of 1999. It has three operating cold crucible melters with the overall capacity up to 75 kg/h. The vitrification technology comprises a few stages, starting with evaporation of excess water from liquid radioactive waste, followed by batch preparation, glass melting, and ending with vitrified waste blocks and some relative small amounts of secondary waste. First of all since the original waste contain as main component water, this water is removed from waste through evaporation. Then the remaining salt concentrate is mixed with necessary technological additives, thus a glass-forming batch is formed. The batch is fed into melters where the glass melting occurs. From here there are two streams: one is the glass melt containing the most part of

  10. AmeriFlux CA-Gro Ontario - Groundhog River, Boreal Mixedwood Forest.

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    McCaughey, Harry [Queen's University

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-Gro Ontario - Groundhog River, Boreal Mixedwood Forest.. Site Description - Groundhog River (FCRN or CCP site "ON-OMW") is situated in a typical boreal mixedwood forest in northeastern Ontario (48.217 degrees north and 82.156 degrees west) about 80 km southwest of Timmins in Reeves Twp. near the Groundhog River. Rowe (1972) places the site in the Missinaibi-Cabonga Section of the Boreal Forest Region. In terms of ecoregion and ecozone, the site is in the Lake Timiskaming Lowlands of the Boreal Shield. The forest developed after high-grade logging in the 1930's. The average age in 2013 is estimated at beteen 75 and 80 years. The forest is dominated by five species characteristic of Ontario boreal mixedwoods: trembling aspen (Populus tremuloides Michx.), black spruce (Picea mariana (Mill.) B.S.P.), white spruce (Picea glauca (Moench.) Voss.), white birch (Betula papyrifera Marsh.), and balsam fir (Abies balsamea (L.) Mill.). The surficial geology is a lacustrine deposit of varved or massive clays, silts and silty sands. The soil is an orthic gleysol with a soil moisture regime classified as fresh to very fresh. Plonski (1974) rates it as a site class 1. The topography is simple and flat with an overall elevation of 340 m ASL.

  11. Draft genome sequence of Raoultella terrigena R1Gly, a diazotrophic endophyte

    SciTech Connect (OSTI)

    Schicklberger, M.; Shapiro, N.; Loqu, D.; Woyke, T.; Chakraborty, R.

    2015-06-11

    Raoultella terrigena R1Gly is a diazotrophic endophyte isolated from surface-sterilized roots of Nicotiana tabacum. The whole-genome sequence was obtained to investigate the endophytic characteristics of this organism at the genetic level, as well as to compare this strain with its close relatives. To our knowledge, this is the first genome obtained from the Raoultella terrigena species and only the third genome from the Raoultella genus, after Raoultella ornitholytic and Raoultella planticola. This genome will provide a foundation for further comparative genomic, metagenomic, and functional studies of this genus.

  12. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems

    SciTech Connect (OSTI)

    Sindelar, R.L.

    2001-02-22

    A research program to investigate the performance and potential for debris formation of Service Level I coating systems used in nuclear power plant containment is being performed at the Savannah River Technology Center. The research activities are aligned to address phenomena important to cause coating disbondment as identified by the Industry Coatings Expert Panel. The period of interest for performance covers the time from application of the coating through 40 years of service, followed by a medium-to-large break loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario. The interactive program elements are described in this report and the application of these elements to evaluate the performance of the specific coating system of Phenoline 305 epoxy-phenolic topcoat over Carbozinc 11 primer on a steel substrate. This system is one of the predominant coating systems present on steel substrates in NPP containment.

  13. South Ukraine NPP: Safety improvements through Plant Computer upgrade

    SciTech Connect (OSTI)

    Brenman, O.; Chernyshov, M. A.; Denning, R. S.; Kolesov, S. A.; Balakan, H. H.; Bilyk, B. I.; Kuznetsov, V. I.; Trosman, G.

    2006-07-01

    This paper summarizes some results of the Plant Computer upgrade at the Units 2 and 3 of South Ukraine Nuclear Power Plant (NPP). A Plant Computer, which is also called the Computer Information System (CIS), is one of the key safety-related systems at VVER-1000 nuclear plants. The main function of the CIS is information support for the plant operators during normal and emergency operational modes. Before this upgrade, South Ukraine NPP operated out-of-date and obsolete systems. This upgrade project wax founded by the U.S. DOE in the framework of the International Nuclear Safety Program (INSP). The most efficient way to improve the quality and reliability of information provided to the plant operator is to upgrade the Human-System Interface (HSI), which is the Upper Level (UL) CIS. The upgrade of the CIS data-acquisition system (DAS), which is the Lower Level (LL) CIS, would have less effect on the unit safety. Generally speaking, the lifetime of the LL CIS is much higher than one of the UL CIS. Unlike Plant Computers at the Western-designed plants, the functionality of the WER-1000 CISs includes a control function (Centralized Protection Testing) and a number of the plant equipment monitoring functions, for example, Protection and Interlock Monitoring and Turbo-Generator Temperature Monitoring. The new system is consistent with a historical migration of the format by which information is presented to the operator away from the traditional graphic displays, for example, Piping and Instrument Diagrams (P and ID's), toward Integral Data displays. The cognitive approach to information presentation is currently limited by some licensing issues, but is adapted to a greater degree with each new system. The paper provides some lessons learned on the management of the international team. (authors)

  14. Joint probability safety assessment for NPP defense infrastructure against extreme external natural hazards

    SciTech Connect (OSTI)

    Guilin, L.; Defu, L.; Huajun, L.; Fengqing, W.; Tao, Z.

    2012-07-01

    With the increasing tendency of natural hazards, the typhoon, hurricane and tropical Cyclone induced surge, wave, precipitation, flood and wind as extreme external loads menacing Nuclear Power Plants (NPP) in coastal and inland provinces of China. For all of planned, designed And constructed NPP the National Nuclear Safety Administration of China and IAEA recommended Probable Maximum Hurricane /Typhoon/(PMH/T), Probable Maximum Storm Surge (PMSS), Probable Maximum Flood (PMF), Design Basis Flood (DBF) as safety regulations for NPP defense infrastructures. This paper discusses the joint probability analysis of simultaneous occurrence typhoon induced extreme external hazards and compare with IAEA 2006-2009 recommended safety regulation design criteria for some NPP defense infrastructures along China coast. (authors)

  15. AmeriFlux CA-Qfo Quebec - Eastern Boreal, Mature Black Spruce

    SciTech Connect (OSTI)

    Margolis, Hank A.

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-Qfo Quebec - Eastern Boreal, Mature Black Spruce. Site Description - 49.69247° N / 74.34204° W, elevation of 387 mm, 90 - 100 yr old Black Spruce, Jack Pine, feather moss

  16. Cofrentes NPP activities on PSA and severe accident analysis

    SciTech Connect (OSTI)

    Suarez, J.; Borondo, L.; Garcia, P.J.

    1996-07-01

    Cofrentes NPP (CNPP) has developed a Level 1 PSA with the following scope: analysis of internal events, with the reactor initially operating at power, internal and external flooding risk analysis; internal fire risk analysis; reliability analysis of the containment heat removal and containment isolation systems. Level 1 CNPP-PSA results reveal that total core damage frequency in CNPP is less than other similar BWR/6 plants. The CNPP-PSA related activities and applications being carried out currently are: adjusting of MAAP 3.0B, revision 10, on VAX and PC; acquisition of MAAP 4; development of Level1/Level2-PSA interface; seismic site categorization for the IPEEE; prioritization of motor operated valves related to GL-89/10, complementary analysis for exemption to some 10CFR50 App. J requirements; Q-List grading; reliability-centered maintenance; maintenance rule support; on-line maintenance support, off-line risk-monitor development, PSA applicability to the 10CFR50 App. R requirements, analysis of the frequency of mis-oriented fuel bundle event, etc. About severe accident management, CNPP, as part of the Spanish-BWROG, is currently analyzing the generic products of the US-BWROG AMG in order to generate their specific ones. Also, in this group BWR, the development of tools to simulate accident scenarios beyond core damage will be studied and a training process oriented to warrant the optimum use of new EOP/AMG in accident scenarios will be implemented.

  17. SIMULATE-3 plant-site applications at Cofrentes NPP

    SciTech Connect (OSTI)

    Molina, D. ); Crespo, A. )

    1992-01-01

    Cofrentes nuclear power plant (NPP) is a General Electric boiling water reactor-6 reactor located in Spain and currently operating on cycle 7. Since 1989, several SIMULATE-3-based plant-site applications have been used to define target control rod patterns and for maneuver predictions. The actual calculational method involves the SIMULATE-3 code running on the main computer of the utility (IBERDROLA) at Madrid. Access from the plant site is provided through personal computers and communication devices. The general performance of the method is satisfactory, but experience has shown that several improvements could be made: using workstations to avoid dependence on the remote host computer, providing color graphic displays for input-output, and introducing an adaptive capability that would allow feedback with in-core instrumentation measurements. Future hardware configuration is being studied by IBERDROLA, while the other two improvements are under development by UITESA. Data management will be carried out by the PISCIS tool, a graphic interface based on X-Windows, which is being extended with additional color screens. Adaptive capability will be provided by the SIMULATE-3 adaptive system discussed in this paper. It is intended to be installed at Cofrentes on-line with the actual process computer.

  18. Modification of the Decontamination Facility at the Kruemmel NPP - 13451

    SciTech Connect (OSTI)

    Klute, Stefan; Kupke, Peter

    2013-07-01

    In February 2009, Siempelkamp Nukleartechnik GmbH was awarded the contract for the design, manufacture, delivery and construction of a new Decontamination Facility in the controlled area for Kruemmel NPP. The new decontamination equipment has been installed according to the state of art of Kruemmel NPP. The existing space required the following modification, retrofitting and reconstruction works: - Demounting of the existing installation: to create space for the new facility it was necessary to dismantle the old facility. The concrete walls and ceilings were cut into sizes of no more than 400 kg for ease of handling. This enabled decontamination so largest possible amount could be released for recycling. All steel parts were cut into sizes fitting for iron-barred boxes, respecting the requirement to render the parts decontaminable and releasable. - Reconstructing a decontamination facility: Reconstruction of a decontamination box with separate air lock as access area for the decontamination of components and assemblies was conducted using pressurized air with abrasives (glass beads or steel shots). The walls were equipped with sound protection, the inner walls were welded gap-free to prevent the emergence of interstices and were equipped with changeable wear and tear curtains. Abrasive processing unit positioned underneath the dry blasting box adjacent to the two discharge hoppers. A switch has been installed for the separation of the glass beads and the steel shot. The glass beads are directed into a 200 l drum for the disposal. The steel shot was cleaned using a separator. The cleaned steel shot was routed via transportation devices to the storage container, making it available for further blasting operations. A decontamination box with separate air lock as access area for the decontamination of components and assemblies using high pressure water technology was provided by new construction. Water pressures between 160 bar and 800 bar can be selected. The inner

  19. ARM - Field Campaign - ARM Radiosondes for NPOESS/NPP Validation - ENA

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

    govCampaignsARM Radiosondes for NPOESS/NPP Validation - ENA Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : ARM Radiosondes for NPOESS/NPP Validation - ENA 2015.02.01 - 2017.12.31 Lead Scientist : Lori Borg For data sets, see below. Abstract This is a satellite validation project involving the use of satellite overpass coincident radiosonde launches. This is analogous to previous IOPs performed for AIRS on the NASA Aqua platform and

  20. ARM - Field Campaign - ARM Radiosondes for NPOESS/NPP Validation - SGP

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

    govCampaignsARM Radiosondes for NPOESS/NPP Validation - SGP Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : ARM Radiosondes for NPOESS/NPP Validation - SGP 2012.07.09 - 2017.12.31 Lead Scientist : Lori Borg For data sets, see below. Abstract This is a satellite validation project involving the use of satellite overpass coincident radiosonde launches. This is analogous to previous IOPs performed for AIRS on the NASA Aqua platform and

  1. ARM - Field Campaign - ARM Radiosondes for NPOESS/NPP Validation - TWP

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

    govCampaignsARM Radiosondes for NPOESS/NPP Validation - TWP ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : ARM Radiosondes for NPOESS/NPP Validation - TWP 2012.07.09 - 2014.12.31 Lead Scientist : David Tobin For data sets, see below. Abstract This was a satellite validation project involving the use of satellite overpass coincident radiosonde launches. This was analogous to previous IOPs performed for

  2. ELECTROCHEMICAL CORROSION STUDIES FOR TANK 241-AN-107 CORE 309 SEGMENTS 21R1 & 21R2

    SciTech Connect (OSTI)

    DUNCAN JB

    2007-11-13

    Liquid waste in tank 241-AN-107 is below Technical Safety Requirements Administrative Control 5.16 (AC 5.16) limits. Electrochemical corrosion testing was performed on Core 309, Segments 21R1 and 21R2, to provide information on the conductivity and corrosive tendencies of the tank saltcake and interstitial liquid. This report describes data obtained under the execution of RPP-PLAN-29001, 'Electrochemical Corrosion Studies for Tank 241-AN-107 Core 309, Segments 21R1 and 21R2'. Analytical results are presented that show supernatant was within the limits while the interstitial liquid remained below the limits for the analytical cores. Applicable AC 5.16 chemistry control limits for AN-107 are presented.

  3. Evaluation of Radiation Impacts of Spent Nuclear Fuel Storage (SNFS-2) of Chernobyl NPP - 13495

    SciTech Connect (OSTI)

    Paskevych, Sergiy; Batiy, Valiriy; Sizov, Andriy; Schmieman, Eric

    2013-07-01

    Radiation effects are estimated for the operation of a new dry storage facility for spent nuclear fuel (SNFS-2) of Chernobyl NPP RBMK reactors. It is shown that radiation exposure during normal operation, design and beyond design basis accidents are minor and meet the criteria for safe use of radiation and nuclear facilities in Ukraine. (authors)

  4. Chernobyl NPP: Completion of LRW Treatment Plant and LRW Management on Site - 12568

    SciTech Connect (OSTI)

    Fedorov, Denis; Adamovich, Dmitry [SIA 'RADON', Moscow (Russian Federation); Klimenko, I.; Taranenko, L. [IVL Engineering, Kiev (Ukraine)

    2012-07-01

    Since a beginning of ChNPP operation, and after a tragedy in 1986, a few thousands m3 of LRW have been collected in a storage tanks. In 2004 ChNPP started the new project on creation of LRW treatment plant (LRWTP) financed from EBRD fund. But it was stopped in 2008 because of financial and contract problems. In 2010 SIA RADON jointly with Ukrainian partners has won a tender on completion of LRWTP, in particular I and C system. The purpose of LRTP is to process liquid rad-wastes from SSE 'Chernobyl NPP' site and those liquids stored in the LRWS and SLRWS tanks as well as the would-be wastes after ChNPP Power Units 1, 2 and 3 decommissioning. The LRTP design lifetime - 20 years. Currently, the LRTP is getting ready to perform the following activities: 1. retrieval of waste from tanks stored at ChNPP LWS using waste retrieval system with existing equipment involved; 2. transfer of retrieved waste into LRTP reception tanks with partial use of existing transfer pipelines; 3. laboratory chemical and radiochemical analysis of reception tanks contest to define the full spectrum of characteristics before processing, to acknowledge the necessity of preliminary processing and to select end product recipe; 4. preliminary processing of the waste to meet the requirements for further stages of the process; 5. shrinkage (concentrating) of preliminary processed waste; 6. solidification of preliminary processed waste with concrete to make a solid-state (end product) and load of concrete compound into 200-l drums; 7. curing of end product drums in LRTP curing hall; 8. radiologic monitoring of end product drums and their loading into special overpacks; 9. overpack radiological monitoring; 10. send for disposal (ICSRM Lot 3); The current technical decisions allow to control and return to ChNPP of process media and supporting systems outputs until they satisfy the following quality norms: salt content: < 100 g/l; pH: 1 - 11; anionic surface-active agent: < 25 mg/l; oil dissipated in the

  5. ON THE INSTABILITY OF TROPICAL WESTERN PACIFIC WARM POOL DURING THE BOREAL WINTER AND SPRING

    SciTech Connect (OSTI)

    BARR-KUMARAKULASINGHE,S.A.

    1998-03-23

    A source of instability in the western Pacific warm pool is shown to be due to sea surface elevation variations caused by changes in the zonal sea-surface temperature (SST) gradient and the changes in the Pacific Ocean basin length in relation to the warm pool latitudinal location. The variation of the sea-surface elevation is measured by using the thermocline depth response calculated from a two-layer ocean. The warm pool is shown to be barely at equilibrium during the boreal late winter and early spring by comparing the measured thermocline at 110{degree}W, 0{degree}E with the calculated thermocline depth. Based on this analysis, a failure or reversal of the climatological zonal winds are apparently not a necessary precursor for the instability of the warm pool and initiation of a warm event. A warm event can be initiated by an increase in the size of the warm pool and/or an increase in zonal SST differences during the boreal/winter spring. This mechanism could be an alternate mechanism for El-Nino Southern Oscillation (ENSO) dynamics to that postulated by Bjeknes (1969).

  6. SIGN-R1 and complement factors are involved in the systemic clearance of radiation-induced apoptotic cells in whole-body irradiated mice

    SciTech Connect (OSTI)

    Park, Jin-Yeon; Loh, SoHee; Cho, Eun-hee; Choi, Hyeong-Jwa; Na, Tae-Young; Nemeno, Judee Grace E.; Lee, Jeong Ik; Yoon, Taek Joon; Choi, In-Soo; Lee, Minyoung; Lee, Jae-Seon; Kang, Young-Sun

    2015-08-07

    Although SIGN-R1-mediated complement activation pathway has been shown to enhance the systemic clearance of apoptotic cells, the role of SIGN-R1 in the clearance of radiation-induced apoptotic cells has not been characterized and was investigated in this study. Our data indicated that whole-body γ-irradiation of mice increased caspase-3{sup +} apoptotic lymphocyte numbers in secondary lymphoid organs. Following γ-irradiation, SIGN-R1 and complements (C4 and C3) were simultaneously increased only in the mice spleen tissue among the assessed tissues. In particular, C3 was exclusively activated in the spleen. The delayed clearance of apoptotic cells was markedly prevalent in the spleen and liver of SIGN-R1 KO mice, followed by a significant increase of CD11b{sup +} cells. These results indicate that SIGN-R1 and complement factors play an important role in the systemic clearance of radiation-induced apoptotic innate immune cells to maintain tissue homeostasis after γ-irradiation. - Highlights: • Splenic SIGN-R1{sup +} macrophages are activated after γ-irradiation. • C3 and C4 levels increased and C3 was activated in the spleen after γ-irradiation. • SIGN-R1 mediated the systemic clearance of radiation-induced apoptotic cells in spleen and liver.

  7. Composition of carbonaceous smoke particles from prescribed burning of a Canadian boreal forest: 1. Organic aerosol characterization by gas chromatography

    SciTech Connect (OSTI)

    Mazurek, M.A.; Laterza, C.; Newman, L.; Daum, P.; Cofer, W.R. III; Levine, J.S.; Winstead, E.L.

    1995-06-01

    In this study we examine the molecular organic constituents (C8 to C40 lipid compounds) collected as smoke particles from a Canadian boreal forest prescribed burn. Of special interest are (1) the molecular identity of polar organic aerosols, and (2) the amount of polar organic matter relative to the total mass of aerosol particulate carbon. Organic extracts of smoke aerosol particles show complex distributions of the lipid compounds when analyzed by capillary gas chromatography/mass spectrometry. The molecular constituents present as smoke aerosol are grouped into non-polar (hydrocarbons) and polar {minus}2 oxygen atoms) subtractions. The dominant chemical species found in the boreal forest smoke aerosol are unaltered resin compounds (C20 terpenes) which are abundant in unburned conifer wood, plus thermally altered wood lignins and other polar aromatic hydrocarbons. Our results show that smoke aerosols contain molecular tracers which are related to the biofuel consumed. These smoke tracers can be related structurally back to the consumed softwood and hardwood vegetation. In addition, combustion of boreal forest materials produces smoke aerosol particles that are both oxygen-rich and chemically complex, yielding a carbonaceous aerosol matrix that is enriched in polar substances. As a consequence, emissions of carbonaceous smoke particles from large-scale combustion of boreal forest land may have a disproportionate effect on regional atmospheric chemistry and on cloud microphysical processes.

  8. LOCA feasibility study of Almaraz NPP 110% power up-rate

    SciTech Connect (OSTI)

    Orive, Raul; Gallego, Ines; Garcia, Pablo; Concejal, Alberto; Martinez-Murillo, Juan-Carlos

    2006-07-01

    Knowledge about accidents and fuel response in extreme conditions has progressed in parallel with the simulation tools development and consequently results are today highly satisfactory. This fact allows nuclear power plants (NPP) to carry out optimization processes of its operation and yield improvements due to the development of new methodologies and tools. Power up-rates open a demand in areas like the analyses of Loss Of Coolant Accidents (LOCA's), which impact on plant design may limit the maximum operation power in a nuclear power plant. TRAC-PF1 is a thermal-hydraulic calculation code that allows the complete treatment of two-phase flows in balance, combining a three dimensional vessel, that simulates in detail the accident phenomena, with one dimensional components. TRAC-PF1 code capacities in the reproduction of experiments, transients and accidents have been widely proved. IBERINCO has modified the original code to develop a conservative model applicable to a 3-loop Westinghouse NPP. These circumstances have allowed Almaraz NPP to get deeper in the study of the plant behaviour during a LOCA, after a hypothetical Power Up-rate. The scope of the study includes the development of the plant model and the reproduction of several accidents with loss of coolant. These accidents have been simulated with the improved option and the conservative version of the modified code (TRAC-PF1/IBER). The limiting case at the current power is analyzed in 110% Power Up-rate conditions and different sensitivity studies are performed, focused in impact of axial power distribution, discharge coefficients and emergency core cooling system availability. These studies allow to verify the effectiveness of Almaraz NPP safety systems in LOCA scenarios to guarantee the required safety margins. (authors)

  9. Principles on Radiological Characterization of the Unit 1 at Ignalina NPP for Decommissioning Purposes

    SciTech Connect (OSTI)

    Poskas, P.; Zujus, R.; Drumstas, G.; Poskas, R.; Simonis, V.

    2008-07-01

    There is only one nuclear power plant in Lithuania - Ignalina NPP (INPP). The INPP operated two similar units with installed capacity of 1500 MW(each). They were commissioned in 12/1983 and 08/1987, and the original design lifetime was projected out to 2010 and 2015 respectively. But the first Unit of Ignalina NPP was shutdown December 31, 2004, and second Unit will be closed down before 2010 taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. Implementation of dismantling activities requires detailed knowledge of the radiological situation at the Unit 1. General Programme of Radiological Survey for Ignalina NPP Unit 1 based on NUREG-1575 was prepared in 2005- 2006 by Consortium led by Lithuanian Energy Institute and approved by Regulatory Bodies. It includes such main steps as historical site assessment, scoping, characterization, remedial actions/decontamination support surveys and final status surveys. General Programme of Radiological Survey defines content and principles of the surveys, and preliminary survey considerations, including identification of the contaminants, establishment of the free release levels, principles on areas classification depending on contamination potential, identification of the final survey units, criteria for selection survey instrumentation, techniques and methods etc. So, in the paper information on these principles and the content of the different stages in General Programme of Radiological Survey is presented. (authors)

  10. AmeriFlux CA-Qcu Quebec - Eastern Boreal, Black Spruce/Jack Pine Cutover

    SciTech Connect (OSTI)

    Margolis, Hank A.

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-Qcu Quebec - Eastern Boreal, Black Spruce/Jack Pine Cutover. Site Description - The ground is gently rolling with a weak slope (<5%). In mesic areas (designated as well to moderately well drained areas, according to the Canadian System of Soil Classification (Agriculture Canada Expert Committee on Soil Survey, 1983)), the soil is a ferro-humic to humic podzol covered by an organic layer having an average depth of 26 cm (Fig. 1). In humid areas, the soil is organic (imperfectly to poorly drained) with an average organic layer of 125 cm. Mesic areas accounted for approximately 75% of the total surface area of the footprint and humid areas accounted for 25%. Full-time continuous measurements eneded in 2011. Intermittent measurements are on-going as resources permit.

  11. AmeriFlux CA-SF3 Saskatchewan - Western Boreal, forest burned in 1998.

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Amiro, Brian [University of Manitoba; Canadian Forest Service

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-SF3 Saskatchewan - Western Boreal, forest burned in 1998.. Site Description - The 1998 burn site (F98) was in the east part of Prince Albert National Park, Saskatchewan, in the Waskesiu Fire, ignited by lightning that burned about 1700 ha in July 1998. The pre-fire forest consisted of jack pine and black spruce stands, with some intermixed aspen. The fire was severe, consuming much of the top layer of organic soil and killing all trees. In 2001, much of the regenerating vegetation consisted of aspen saplings about 1 m tall and shorter jack pine and black spruce seedlings. An overstory of dead, leafless jack pine trees dominated at a height of 18 m. Sparse grass and herbs, such as fireweed (Epilobium angustifolium L.) covered the ground. There were a large number of fallen dead trees, mostly perched above the ground and not decomposing quickly.

  12. The resilience and functional role of moss in boreal and arctic ecosystems

    SciTech Connect (OSTI)

    Turetsky, Merritt; Bond-Lamberty, Benjamin; Euskirchen, Eugenie S.; Talbot, Julie; Frolking, Steve; McGuire, A. David; Tuittila, Eeva-Stiina

    2012-08-24

    Mosses in boreal and arctic ecosystems are ubiquitous components of plant communities, represent an important component of plant diversity, and strongly influence the cycling of water, nutrients, energy and carbon. Here we use a literature review and synthesis as well as model simulations to explore the role of moss in ecological stability and resilience. Our literature review of moss community responses to disturbance showed all possible responses (increases, decreases, no change) within most disturbance categories in boreal and arctic regions. Our modeling simulations suggest that loss of moss within northern plant communities will reduce soil carbon accumulation primarily by influencing decomposition rates and soil nitrogen availability. While two models (HPM and STM-TEM) showed a significant effect of moss removal, results from the Biome-BGC and DVM-TEM models suggest that northern, moss-rich ecosystems would need to experience extreme perturbation before mosses were eliminated. We highlight a number of issues that have not been adequately explored in moss communities, such as functional redundancy and singularity, relationships between response and effect traits, phenotypical plasticity in traits, and whether the effects of moss on ecosystem processes scale with local abundance. We also suggest that as more models explore issues related to ecological resilience, issues related to both parameter and conceptual uncertainty should be addressed: are the models more limited by uncertainty in the parameterization of the processes included or by what is not represented in the model at all? It seems clear from our review that mosses need to be incorporated into models as one or more plant functional types, but more empirical work is needed to determine how to best aggregate species.

  13. C/2013 R1 (Lovejoy) at IR wavelengths and the variability of CO abundances among Oort Cloud comets

    SciTech Connect (OSTI)

    Paganini, L.; Mumma, M. J.; Villanueva, G. L.; Bonev, B. P.; DiSanti, M. A.; Keane, J. V.; Meech, K. J.; Blake, G. A.; Gibb, E. L.

    2014-08-20

    We report production rates, rotational temperatures, and related parameters for gases in C/2013 R1 (Lovejoy) using the Near InfraRed SPECtrometer at the Keck Observatory, on six UT dates spanning heliocentric distances (R{sub h} ) that decreased from 1.35 AU to 1.16 AU (pre-perihelion). We quantified nine gaseous species (H{sub 2}O, OH*, CO, CH{sub 4}, HCN, C{sub 2}H{sub 6}, CH{sub 3}OH, NH{sub 3}, and NH{sub 2}) and obtained upper limits for two others (C{sub 2}H{sub 2} and H{sub 2}CO). Compared with organics-normal comets, our results reveal highly enriched CO, (at most) slightly enriched CH{sub 3}OH, C{sub 2}H{sub 6}, and HCN, and CH{sub 4} consistent with {sup n}ormal{sup ,} yet depleted, NH{sub 3}, C{sub 2}H{sub 2}, and H{sub 2}CO. Rotational temperatures increased from ?50 K to ?70 K with decreasing R{sub h} , following a power law in R{sub h} of 2.0 0.2, while the water production rate increased from 1.0 to 3.9 10{sup 28} molecules s{sup 1}, following a power law in R{sub h} of 4.7 0.9. The ortho-para ratio for H{sub 2}O was 3.01 0.49, corresponding to spin temperatures (T {sub spin}) ? 29 K (at the 1? level). The observed spatial profiles for these emissions showed complex structures, possibly tied to nucleus rotation, although the cadence of our observations limits any definitive conclusions. The retrieved CO abundance in Lovejoy is more than twice the median value for comets in our IR survey, suggesting this comet is enriched in CO. We discuss the enriched value for CO in comet C/2013 R1 in terms of the variability of CO among Oort Cloud comets.

  14. OVERVIEW ON BNL ASSESSMENT OF SEISMIC ANALYSIS METHODS FOR DEEPLY EMBEDDED NPP STRUCTURES.

    SciTech Connect (OSTI)

    XU,J.; COSTANTINO, C.; HOFMAYER, C.; GRAVES, H.

    2007-04-01

    A study was performed by Brookhaven National Laboratory (BNL) under the sponsorship of the U. S. Nuclear Regulatory Commission (USNRC), to determine the applicability of established soil-structure interaction analysis methods and computer programs to deeply embedded and/or buried (DEB) nuclear power plant (NPP) structures. This paper provides an overview of the BNL study including a description and discussions of analyses performed to assess relative performance of various SSI analysis methods typically applied to NPP structures, as well as the importance of interface modeling for DEB structures. There are four main elements contained in the BNL study: (1) Review and evaluation of existing seismic design practice, (2) Assessment of simplified vs. detailed methods for SSI in-structure response spectrum analysis of DEB structures, (3) Assessment of methods for computing seismic induced earth pressures on DEB structures, and (4) Development of the criteria for benchmark problems which could be used for validating computer programs for computing seismic responses of DEB NPP structures. The BNL study concluded that the equivalent linear SSI methods, including both simplified and detailed approaches, can be extended to DEB structures and produce acceptable SSI response calculations, provided that the SSI response induced by the ground motion is very much within the linear regime or the non-linear effect is not anticipated to control the SSI response parameters. The BNL study also revealed that the response calculation is sensitive to the modeling assumptions made for the soil/structure interface and application of a particular material model for the soil.

  15. Development of a new methodology for stability analysis in BWR NPP

    SciTech Connect (OSTI)

    Garcia-Fenoll, M.; Abarca, A.; Barrachina, T.; Miro, R.; Verdu, G.

    2012-07-01

    In this work, a new methodology to reproduce power oscillations in BWR NPP is presented. This methodology comprises the modal analysis techniques, the signal analysis techniques and the simulation with the coupled code RELAP5/PARCSv2.7. Macroscopic cross sections are obtained by using the SIMTAB methodology, which is fed up with CASMO-4/SIMULATE-3 data. The input files for the neutronic and thermohydraulic codes are obtained automatically and the thermalhydraulic-to-neutronic representation (mapping) used is based on the fundamental, first and second harmonics shapes of the reactor power, calculated with the VALKIN code (developed in UPV). This mapping was chosen in order not to condition the oscillation pattern. To introduce power oscillations in the simulation a new capability in the coupled code, for generate density perturbations (both for the whole core and for chosen axial levels) according with the power modes shapes, has been implemented. The purpose of the methodology is to reproduce the driving mechanism of the out of phase oscillations appeared in BWR type reactors. In this work, the methodology is applied to the Record 9 point, collected in the NEA benchmark of Ringhals 1 NPP. A set of different perturbations are induced in the first active axial level and the LPRM signals resulting are analyzed. (authors)

  16. Interannual Modulation of Subtropical Atlantic Boreal Summer Dust Variability by ENSO

    SciTech Connect (OSTI)

    DeFlorio, Mike; Goodwin, Ian D.; Cayan, Dan; Miller, Arthur J.; Ghan, Steven J.; Pierce, David; Russell, Lynn M.; Singh, Balwinder

    2016-01-01

    Dust variability in the climate system has been studied for several decades, yet there remains an incomplete understanding of the dynamical mechanisms controlling interannual and decadal variations in dust transport. The sparseness of multi-year observational datasets has limited our understanding of the relationship between climate variations and atmospheric dust. We use available observations and a century-length fully coupled Community Earth System Model (CESM) simulation to show that the El Niño- Southern Oscillation (ENSO) exerts a control on North African dust transport during boreal summer. In CESM, this relationship is stronger over the dusty tropical North Atlantic than near Barbados, one of the few sites having a multi-decadal observed record. During strong La Niña summers in CESM, a statistically significant increase in lower tropospheric easterly wind is associated with an increase in North African dust transport over the Atlantic. Barbados dust and Pacific SST variability are only weakly correlated in both observations and CESM, suggesting that other processes are controlling the crossbasin variability of dust. We also use our CESM simulation to show that the relationship between downstream North African dust transport and ENSO fluctuates on multidecadal timescales and may be modulated by the North Atlantic Oscillation (NAO). Our findings indicate that existing observations of dust over the tropical North Atlantic are not extensive enough to completely describe the variability of dust and dust transport, and demonstrate the importance of global models to supplement and interpret observational records.

  17. Boreal winter MJO teleconnection in the Community Atmosphere Model version 5 with the Unified Convection parameterization

    SciTech Connect (OSTI)

    Yoo, Changhyun; Park, Sungsu; Kim, Daehyun; Yoon, Jin-Ho; Kim, Hye-Mi

    2015-10-15

    The Madden-Julian Oscillation (MJO), the dominant mode of tropical intraseasonal variability, influences weather and climate in the extratropics through atmospheric teleconnection. In this study, two simulations using the Community Atmosphere Model version 5 (CAM5) - one with the default shallow and deep convection schemes and the other with the Unified Convection scheme (UNICON) - are employed to examine the impacts of cumulus parameterizations on the simulation of the boreal wintertime MJO teleconnection in the Northern Hemisphere. We demonstrate that the UNICON substantially improves the MJO teleconnection. When the UNICON is employed, the simulated circulation anomalies associated with the MJO better resemble the observed counterpart, compared to the simulation with the default convection schemes. Quantitatively, the pattern correlation for the 300-hPa geopotential height anomalies between the simulations and observation increases from 0.07 for the default schemes to 0.54 for the UNICON. These circulation anomalies associated with the MJO further help to enhance the surface air temperature and precipitation anomalies over North America, although room for improvement is still evident. Initial value calculations suggest that the realistic MJO teleconnection with the UNICON is not attributed to the changes in the background wind, but primarily to the improved tropical convective heating associated with the MJO.

  18. Preparation and properties of (R)-(-)-1-azabicyclo(2. 2. 2)oct-3-yl- (R)-(+)-alpha-hydroxy-alpha-(4-( sup 125 I)iodophenyl)-alpha-phenyl acetate and (R)-(-)-1-azabicyclo(2. 2. 2)oct-3-yl-(S)-(-)-alpha-hydroxy-alpha- (4-( sup 125 I)iodophenyl)-alpha-phenyl acetate as potential radiopharmaceuticals

    SciTech Connect (OSTI)

    Cohen, V.I.; Rzeszotarski, W.J.; Gibson, R.E.; Fan, L.H.; Reba, R.C. )

    1989-10-01

    rac-4-Nitrobenzilic acid was synthesized and resolved with quinidine and quinine to give the corresponding (R)- and (S)-salts. The resolved diastereomeric salts were converted to (R)- and (S)-4-nitrobenzilic acids and subsequent esterification gave their corresponding ethyl esters. Transesterification with (R)-(-)-3-quinuclidinol afforded (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(R)-(+)-alpha-hydroxy-alpha- (4-nitrophenyl)-alpha-phenyl acetate and (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(S)-(-)-alpha-hydroxy- alpha-(4-nitrophenyl)-alpha-phenyl acetate. After hydrogenation, the (R,R)- and (R,S)-amines were converted to the respective triazene derivatives. The triazene derivatives reacted with sodium ({sup 125}I)iodide to give (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(R)-(+)- alpha-hydroxy-alpha-(4-({sup 125}I)iodophenyl)-alpha-phenyl acetate and (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(S)-(-)-alpha-hydroxy- alpha-(4-(125I)iodophenyl)-alpha-phenyl acetate. The evaluation of their affinities to muscarinic acetylcholine receptors (MAcChR) shows that (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(S)-(-)-alpha-hydroxy-alpha-(4- ({sup 125}I)iodophenyl)-alpha-phenyl acetate exhibits an affinity for the MAcChR from corpus striatum that is approximately threefold lower than that of (R)-(-)-1-azabicyclo(2.2.2)oct-3-yl-(R)-(+)-alpha-hydroxy-alpha-(4- ({sup 125}I)iodophenyl)-alpha-phenyl acetate.

  19. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect (OSTI)

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M.; Michal, V.; Vargovcik, L.

    2012-07-01

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of

  20. Design enhancement in BWR feedwater control system: Experience feedback from Kuosheng NPP

    SciTech Connect (OSTI)

    Chen, C. C.

    2006-07-01

    Though feedwater control system is used only for normal operation of the plant, it belongs to the category cited by SRP chapter 7.7 that has the potential to affect the performance of critical safety functions. Kousheng has been commercial operation for more than 20 years. Because of equipment aging problem and difficulties in getting spare parts, feedwater control system needs upgrade. Unit II feedwater control system was upgraded to modern digital control system in EOC-17 and Unit I was upgraded in EOC-18. Before the implementation of the project, Taipower has accumulated various experiences from previous digital control system retrofits in Chin-Shan, Kousheng and Maanshan NPP. A task force lead by author is formed to assist Kousheng. This paper shares the experience of Kousheng retrofit project. (authors)

  1. Failure Forewarning in NPP Equipment NERI2000-109 Final Project Report

    SciTech Connect (OSTI)

    Hively, LM

    2004-03-26

    The objective of this project is forewarning of machine failures in critical equipment at next-generation nuclear power plants (NPP). Test data were provided by two collaborating institutions: Duke Engineering and Services (first project year), and the Pennsylvania State University (Applied Research Laboratory) during the second and third project years. New nonlinear methods were developed and applied successfully to extract forewarning trends from process-indicative, time-serial data for timely, condition-based maintenance. Anticipation of failures in critical equipment at next-generation NPP will improve the scheduling of maintenance activities to minimize safety concerns, unscheduled non-productive downtime, and collateral damage due to unexpected failures. This approach provides significant economic benefit, and is expected to improve public acceptance of nuclear power. The approach is a multi-tiered, model-independent, and data-driven analysis that uses ORNL's novel nonlinear method to extract forewarning of machine failures from appropriate data. The first tier of the analysis provides a robust choice for the process-indicative data. The second tier rejects data of inadequate quality. The third tier removes signal artifacts that would otherwise confound the analysis, while retaining the relevant nonlinear dynamics. The fourth tier converts the artifact-filtered time-serial data into a geometric representation, that is then transformed to a discrete distribution function (DF). This method allows for noisy, finite-length datasets. The fifth tier obtains dissimilarity measures (DM) between the nominal-state DF and subsequent test-state DFs. Forewarning of a machine failure is indicated by several successive occurrences of the DM above a threshold, or by a statistically significant trend in the DM. This paradigm yields robust nonlinear signatures of degradation and its progression, allowing earlier and more accurate detection of the machine failure.

  2. Assessment of boreal forest historical C dynamics in Yukon River Basin: relative roles of warming and fire regime change

    SciTech Connect (OSTI)

    Yuan, Fengming [ORNL; Yi, Shuhua [Cold and Arid Regions Environmental and Engineering Research Institute, CAS; McGuire, A. David [University of Alaska; Johnson, Kristopher D [University of Alaska, Fairbanks; Liang, Jingjing [University of Alaska, Fairbanks; Harden, Jennifer [USGS, Menlo Park, CA; Kasischke, Eric S. [University of Maryland, College Park; Kurz, Werner [Canadian Forest Service

    2012-01-01

    Carbon (C) dynamics of boreal forest ecosystems have substantial implications for efforts to mitigate the rise of atmospheric CO2 and may be substantially influenced by warming and changing wildfire regimes. In this study we applied a large-scale ecosystem model that included dynamics of organic soil horizons and soil organic matter characteristics of multiple pools to assess forest C stock changes of the Yukon River Basin (YRB) in Alaska, USA, and Canada from 1960 through 2006, a period characterized by substantial climate warming and increases in wildfire. The model was calibrated for major forests with data from long-term research sites and evaluated using a forest inventory database. The regional assessment indicates that forest vegetation C storage increased by 46 Tg C, but that total soil C storage did not change appreciably during this period. However, further analysis suggests that C has been continuously lost from the mineral soil horizon since warming began in the 1970s, but has increased in the amorphous organic soil horizon. Based on a factorial experiment, soil C stocks would have increased by 158 Tg C if the YRB had not undergone warming and changes in fire regime. The analysis also identified that warming and changes in fire regime were approximately equivalent in their effects on soil C storage, and interactions between these two suggests that the loss of organic horizon thickness associated with increases in wildfire made deeper soil C stocks more vulnerable to loss via decomposition. Subbasin analyses indicate that C stock changes were primarily sensitive to the fraction of burned forest area within each subbasin and that boreal forest ecosystems in the YRB are currently transitioning from being sinks to sources at ;0.7% annual area burned. We conclude that it is important for international mitigation efforts focused on controlling atmospheric CO2 to consider how climate warming and changes in fire regime may concurrently affect the CO2 sink

  3. Reactivity-worth estimates of the OSMOSE samples in the MINERVE reactor R1-MOX, R2-UO2 and MORGANE/R configurations.

    SciTech Connect (OSTI)

    Zhong, Z.; Klann, R. T.; Nuclear Engineering Division

    2007-08-03

    An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R2-UO2 and MORGANE/R core configuration were completed. The calculation model was generated using the lattice physics code DRAGON. In addition, an initial comparison of calculated values to experimental measurements was performed based on preliminary results for the R1-MOX configuration.

  4. The Management of the Radioactive Waste Generated by Cernavoda NPP, Romania, an Example of International Cooperation - 13449

    SciTech Connect (OSTI)

    Barariu, Gheorghe

    2013-07-01

    The design criteria and constraints for the development of the management strategy for radioactive waste generated from operating and decommissioning of CANDU Nuclear Units from Cernavoda NPP in Romania, present many specific aspects. The main characteristics of CANDU type waste are its high concentrations of tritium and radiocarbon. Also, the existing management strategy for radioactive waste at Cernavoda NPP provides no treatment or conditioning for radioactive waste disposal. These characteristics embodied a challenging effort, in order to select a proper strategy for radioactive waste management at present, when Romania is an EU member and a signatory country of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The helping of advanced countries in radioactive waste management, directly or into the frame of the international organizations, like IAEA, become solve the aforementioned challenges at adequate level. (authors)

  5. Comparison of Candidate Sites for installation of Landfill facility at Ignalina NPP Site Using Fuzzy Logic Approach

    SciTech Connect (OSTI)

    Poskas, P.; Kilda, R.; Poskas, G.

    2008-07-01

    There is only one nuclear power plant in Lithuania - Ignalina NPP (Nuclear Power Plant). Two similar units with installed capacity of 1500 MW (each) were commissioned in 1983 and 1987 respectively. But the first Unit of Ignalina NPP was finally shutdown December 31, 2004, and second Unit is planned to be shutdown before 2010. Operational radioactive waste of different activities is generated at Ignalina NPP. After closure of INPP a waste from decommissioning should be managed also. According to Lithuanian regulatory requirements (1) the waste depending on the activity must be managed in different ways. In compliance with this Regulation very low-level radioactive waste (VLLW) could be disposed of in a Landfill facility. In such case very simple engineered barriers are required. A cap on the top of the repository is necessary from long-term safety point of view. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components: the site, the disposal facility and the waste form. The basic objective of the siting process is to select a suitable site for disposal and demonstrate that this site has characteristics which provide adequate isolation of radionuclides from the biosphere for desired periods of time. The methodology and results on evaluation and comparison of two candidate sites intended for construction of Landfill facility at Ignalina NPP site are presented in the paper. Criteria for comparison are based on the IAEA (International Atomic Energy Agency) recommendations (2). Modeling of the radionuclide releases has been performed using ISAM (Improving of Safety Assessment Methodologies for Near Surface Disposal facilities) methodology (3). For generalization of the information and elaboration of the recommendations Fuzzy Logic approach was used (4). (authors)

  6. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    SciTech Connect (OSTI)

    Takeshita, K.; Takahashi, H.; Jinbo, Y.; Ishido, A.

    2013-07-01

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  7. Commissioning and Operation of a Robotic Arm for Waste Retrieval at Trawsfynydd NPP, North Wales - 12091

    SciTech Connect (OSTI)

    Smith, Alan L.; Cabrera, David L.

    2012-07-01

    Trawsfynydd is one of the UK's first generation Magnox nuclear power plants. It started operation in 1965 and ceased generation in 1991. Before the site can enter the 'care and maintenance' phase a number of wet and dry waste stores around the site must be emptied and their contents made safe. Wet wastes include sludges and resins produced during the operating life of the NPP. The sludges and resins are stored in a number of different tanks that vary significantly in terms of size, shape, internal features and access. A dexterous long reach manipulator arm has been designed and built to facilitate tank clearance. Commissioning of the arm was carried out in parallel with Factory Acceptance Testing (FAT) at the manufacturer's site in Colorado, USA. In addition to basic functional testing this work included a full range of task based testing to ensure that the arm, tools, control system and support equipment were thoroughly exercised in representative conditions. Trawsfynydd is one of the lead sites in the UK's program for nuclear plant decommissioning. As such the lessons learned, both in terms of technology and process, will be applicable across the remainder of the fleet. (authors)

  8. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Net primary productivity (NPP) modeling can help to improve the understanding of the ecosystem, and therefore, improve ecological efficiency. The boreal ecosystem productivity ...

  9. Estimation of net primary productivity using a process-based...

    Office of Scientific and Technical Information (OSTI)

    Net primary productivity (NPP) modeling can help to improve the understanding of the ecosystem, and therefore, improve ecological efficiency. The boreal ecosystem productivity ...

  10. doeid11129r1.pdf

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

    ... 200 million dry tons annually to the nation's energy supply, primarily from wood residues. ... The pellets are also less combustible because Figure 4.1. Current bale technology is not ...

  11. 06 Run R1.xls

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

    3-2006 Run Shutdown Maintenance / AP Injector / SPEAR Startup Spear Down University Holidays AP 28 AP 28 MA AP 15 22 11 13 Conf 12 User 1 5 4 3 2 28 31 30 29 20 18 17 27 26 25 19 21 AP 20 16 11 14 AP 7 8 8 15 16 13 AP 12 11 14 MA 1 6 AP 1 16 MA 6 8 9 2 9 12 MA AP 21 25 26 24 23 22 20 Dwn 4pm 24 26 29 28 27 27 28 29 30 2 4 3 10 3 8 9 26 27 23 24 25 3 MA 7 3 3 4 1 1 2 4 2 1 1 9 6 11 7 8 10 9 8 13 14 3 4 3 2 4 6 8 21 5 15 12 17 18 14 16 13 9 10 11 5 MA 15 14 5 11 12 10 AP 6 AP 10 MA 13 1 6 7 4 29

  12. Application of the leak-before-break concept to the primary circuit piping of the Leningrad NPP

    SciTech Connect (OSTI)

    Eperin, A.P.; Zakharzhevsky, Yu.O.; Arzhaev, A.I.

    1997-04-01

    A two-year Finnish-Russian cooperation program has been initiated in 1995 to demonstrate the applicability of the leak-before-break concept (LBB) to the primary circuit piping of the Leningrad NPP. The program includes J-R curve testing of authentic pipe materials at full operating temperature, screening and computational LBB analyses complying with the USNRC Standard Review Plan 3.6.3, and exchange of LBB-related information with emphasis on NDE. Domestic computer codes are mainly used, and all tests and analyses are independently carried out by each party. The results are believed to apply generally to RBMK type plants of the first generation.

  13. Involvement of aldolase A in X-ray resistance of human HeLa and UV{sup r}-1 cells

    SciTech Connect (OSTI)

    Lu, Jun; Suzuki, Toshikazu Satoh, Mamoru; Chen, Shiping; Tomonaga, Takeshi; Nomura, Fumio; Suzuki, Nobuo

    2008-05-09

    To find novel proteins involved in radio-resistance of human cells, we searched for nuclear proteins, whose expression levels alter after X-ray irradiation in HeLa cells, using agarose fluorescent two-dimensional differential gel electrophoresis following mass spectrometry. We identified 6 proteins, whose levels were increased in nuclei 24 h after irradiation at 5 Gy, including aldolase A. Nuclear aldolase A levels increased twofold after the irradiation, however, total aldolase A levels did not change. When the expression of aldolase A was suppressed by its specific siRNA, sensitization of the suppressed cells to X-ray-induced cell death was observed. In addition, UV{sup r}-1 cells with higher aldolase A expression exhibited lower sensitivity to X-ray-induced cell death than the parental RSa cells with lower aldolase A expression. These results suggest that aldolase A may play a role in the radio-response of human cells, probably in nuclei, in addition to its glycolytic role in the cytosol.

  14. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

    SciTech Connect (OSTI)

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  15. NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

    SciTech Connect (OSTI)

    Manan, J. A. N. Abd Mostafa, N. A.; Salim, M. F.

    2015-04-29

    The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national and international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders’ interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear

  16. Assessment of Hard-to-Detect Radionuclide Levels in Decommissioning Waste From the Bohunice NPP-A1, Slovakia, for Clearance and Disposal Purposes

    SciTech Connect (OSTI)

    Slavik, O.; Moravek, J.; Stubna, M.

    2002-02-26

    For assessments of hard-to-detect radionuclides (HD-RN) contents in various type of radwastes at the NPP-A1, available empirical data referenced to 137Cs (actinides, 90Sr, 99Tc, 63Ni, 14C) and the theoretical assessment for the remaining HD-RN using calculated RN inventory and a simple model with effective relative (137Cs) spent fuel release fractions was applied. The analytical data of extended radiochemical analysis for the existing available operational radwaste forms have been reviewed for this purpose. 137Cs, 90Sr and 241Am were set up as release markers for partial spent fuel release groups of HD-RNs within which the total fractions of HD-RN released to the operational radwastes were assumed to be constant. It was shown by the assessment carried out that 137Cs and HD-RNs 129I, 99Tc, and partly 79Se and 14C are the main contributors to the disposal dose limit for the radioactive concentrate at NPP A-1. In the case of the radioactive sludge from the operational radwaste system the role of predominant dose contributors belongs to actinides 239,240Pu and 241Am. In the case of clearance of radioactive material from the NPP-A1 site, only the reference radionuclide, 137Cs was predicted to be the most dominant dose contributor. In all of these cases the estimated contributions of other hard-to-detect radionuclides to respective disposal or release dose limit are lower by 2 and more orders of magnitude. As a lesson learned, the most attention is proposed to focus on the control and measurement of the critical HD-RNs indicated by the assessment. For the control of less important HD-RNs, the developed release coefficient method is sufficient to be applied.

  17. Lysine N[superscript zeta]-Decarboxylation Switch and Activation of the [beta]-Lactam Sensor Domain of BlaR1 Protein of Methicillin-resistant Staphylococcus aureus

    SciTech Connect (OSTI)

    Borbulevych, Oleg; Kumarasiri, Malika; Wilson, Brian; Llarrull1, Leticia I.; Lee, Mijoon; Hesek, Dusan; Shi, Qicun; Peng, Jeffrey; Baker, Brian M.; Mobashery, Shahriar

    2012-10-29

    The integral membrane protein BlaR1 of methicillin-resistant Staphylococcus aureus senses the presence of {beta}-lactam antibiotics in the milieu and transduces the information to the cytoplasm, where the biochemical events that unleash induction of antibiotic resistance mechanisms take place. We report herein by two-dimensional and three-dimensional NMR experiments of the sensor domain of BlaR1 in solution and by determination of an x-ray structure for the apo protein that Lys-392 of the antibiotic-binding site is posttranslationally modified by N{sup {zeta}}-carboxylation. Additional crystallographic and NMR data reveal that on acylation of Ser-389 by antibiotics, Lys-392 experiences N{sup {zeta}}-decarboxylation. This unique process, termed the lysine N{sup {zeta}}-decarboxylation switch, arrests the sensor domain in the activated ('on') state, necessary for signal transduction and all the subsequent biochemical processes. We present structural information on how this receptor activation process takes place, imparting longevity to the antibiotic-receptor complex that is needed for the induction of the antibiotic-resistant phenotype in methicillin-resistant S. aureus.

  18. jz502253r 1..7

    Office of Scientific and Technical Information (OSTI)

    ... Pure Resonant Auger -Normal Auger Kinetic Energy (eV) Figure 4. Auger spectra for a neat ... and resonant (spectator + participator, green dashed line) components at 398 eV. (c) ...

  19. ENG-RCAL-028-r1.PDF

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

    for the Shipment of Unirradiated Uranium Preparer: J. L. Boles Date 53100 ... of the transportation of unirradiated uranium in the form of metallic billets, UO 3 ...

  20. Application of 'Six Sigma{sup TM}' and 'Design of Experiment' for Cementation - Recipe Development for Evaporator Concentrate for NPP Ling AO, Phase II (China) - 12555

    SciTech Connect (OSTI)

    Fehrmann, Henning [Westinghouse Electric Germany GmbH (Germany); Perdue, Robert [Westinghouse Electric Company (United States)

    2012-07-01

    Cementation of radioactive waste is a common technology. The waste is mixed with cement and water and forms a stable, solid block. The physical properties like compression strength or low leach ability depends strongly on the cement recipe. Due to the fact that this waste cement mixture has to fulfill special requirements, a recipe development is necessary. The Six Sigma{sup TM}' DMAIC methodology, together with the Design of experiment (DoE) approach, was employed to optimize the process of a recipe development for cementation at the Ling Ao nuclear power plant (NPP) in China. The DMAIC offers a structured, systematical and traceable process to derive test parameters. The DoE test plans and statistical analysis is efficient regarding the amount of test runs and the benefit gain by getting a transfer function. A transfer function enables simulation which is useful to optimize the later process and being responsive to changes. The DoE method was successfully applied for developing a cementation recipe for both evaporator concentrate and resin waste in the plant. The key input parameters were determined, evaluated and the control of these parameters were included into the design. The applied Six Sigma{sup TM} tools can help to organize the thinking during the engineering process. Data are organized and clearly presented. Various variables can be limited to the most important ones. The Six Sigma{sup TM} tools help to make the thinking and decision process trace able. The tools can help to make data driven decisions (e.g. C and E Matrix). But the tools are not the only golden way. Results from scoring tools like the C and E Matrix need close review before using them. The DoE is an effective tool for generating test plans. DoE can be used with a small number of tests runs, but gives a valuable result from an engineering perspective in terms of a transfer function. The DoE prediction results, however, are only valid in the tested area. So a careful selection of input

  1. DOE_OR_21548_283_R_1.pdf

    Office of Legacy Management (LM)

  2. Microsoft Word - V-ESR-G-00003_R1.doc

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

    ESR-G-00003 Revision 1 Waste Removal Technology Baseline: Technology Development Description T. B. Caldwell 15 June 2011 Savannah River Remediation, LLC Closure Project Engineering Aiken, SC 29808 Prepared for the U.S. Department of Energy under Contract No. DE-AC09-09SR22505 Waste Removal Technology Baseline: V-ESR-G-00003 Technology Development Description Revision 1 15 June 2011 Page 3 of 50 TABLE OF CONTENTS LIST OF FIGURES

  3. Microsoft Word - 2015 Tech Exchange Biosketches R1

    Office of Environmental Management (EM)

    ... (economic) analysis, options analysis, statistics, probability, elicitation, earth ... problems, work in a collaborative environment on interesting problems that call for ...

  4. DOE_OR_21548_702_R_1.pdf

    Office of Legacy Management (LM)

  5. DOE_OR_21548_765_R_1.pdf

    Office of Legacy Management (LM)

  6. DOE_OR_21548_789_R_1.pdf

    Office of Legacy Management (LM)

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    Office of Legacy Management (LM)

  8. Microsoft Word - TWCB meeting minutes Aug12r1 web

    Office of Environmental Management (EM)

    (TWCB) Meeting Minutes, August 1-2, 2012 F. Lockhart, TWCB Staff Coordinator, 202-731-5659 Page 1 of 5 The first Tank Waste Corporate Board (TWCB) meeting since the Office of ...

  9. Microsoft PowerPoint - TWCB Summary Aug12r1

    Office of Environmental Management (EM)

    Summary Tank Waste Corporate Board Summary www.em.doe.gov 1 Tank Waste Corporate Board Summary Tank Waste Corporate Board Summary Ken Picha, Deputy Assistant Secretary Office of...

  10. Microsoft Word - DOE-ID-INL-13-006 R1-(INL-13-019 R1-redline...

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

    Two circuits of three-phase distribution lines will be ... to approximately pole 40E on the 138kV transmission line. ... non-road engines (small electrical generators), but are ...

  11. Microsoft Word - DOE-ID-INL-11-005 R1 _INL-11-037 R1_.doc

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

    ... This is in accordance with the methods specified in the Rules for the Control of Air Pollution in Idaho (IDAPA 58.01.01.650-651). Steps taken to control fugitive dust at the INL ...

  12. Radioecologycal study of {sup 239/240}Pu in Bangka Island and Muria Peninsula: Determination of {sup 239/240}Pu in marine sediment and seawater as part of baseline data collecting for sitting of candidates of first Indonesia NPP

    SciTech Connect (OSTI)

    Suseno, Heny; Wisnubroto, Djarot S.

    2014-03-24

    Radioisotope Pu-239/240 are alpha emitting nuclides important indicators of radioactive contamination of the marine environment. Global fallout is the main source of plutonium in the marine environment. There are very limited study on {sup 239/240}Pu in Indonesia coastal environments. The data of this radioisotopes is needed for baseline data of nuclear power plant (NPP) site candidates both in Bangka Island and Muria Peninsula. Bottom sediments play an important role in radioecological studies of the marine environment because a large proportion of radioactive substances entering the sea is adsorbed over time onto suspended particulate matter and deposited in sediments. Plutonium is particle reactive and deposited in marine sediment. Radioisotope {sup 239/240}Pu was determinated by alpha spectrometry after radiochemical procedure that was performed in both water and marine sediment from Bangka Island and Muria Peninsula. The sediment baseline of concentration {sup 239/240}Pu in Bangka Island and Muria Peninsula were range from 0.013 to 0.021 Bq.kg{sup ?1} and 0.018 to 0.024 Bq.kg{sup ?1} respectively. The water baseline concentration this isotope were range from 2.73 to 4.05 mBq.m{sup ?3} and 2.98 to 4.50 mBq.m{sup ?3}.

  13. Interannual Modulation of Subtropical Atlantic Boreal Summer...

    Office of Scientific and Technical Information (OSTI)

    Resource Relation: Journal Name: Climate Dynamics; Journal Volume: 46; Journal Issue: 1 Publisher: Springer-Verlag Research Org: Pacific Northwest National Laboratory (PNNL), ...

  14. Decommissioning Project of Bohunice A1 NPP

    SciTech Connect (OSTI)

    Stubna, M.; Pekar, A.; Moravek, J.; Spirko, M.

    2002-02-26

    The first (pilot) nuclear power plant A1 in the Slovak Republic, situated on Jaslovske Bohunice site (60 km from Bratislava) with the capacity of 143 MWel, was commissioned in 1972 and was running with interruptions till 1977. A KS 150 reactor (HWGCR) with natural uranium as fuel, D2O as moderator and gaseous CO2 as coolant was installed in the A1 plant. Outlet steam from primary reactor coolant system with the temperature of 410 C was led to 6 modules of steam generators and from there to turbine generators. Refueling was carried out on-line at plant full power. The first serious incident associated with refueling occurred in 1976 when a locking mechanism at a fuel assembly failed. The core was not damaged during that incident and following a reconstruction of the damaged technology channel, the plant continued in operation. However, serious problems were occurring with the integrity of steam generators (CO2 gas on primary side, water and steam on secondary side) when the plant had to be shut down frequently due to failures and subsequent repairs. The second serious accident occurred in 1977 when a fuel assembly was overheated with a subsequent release of D2O into gas cooling circuit due to a human failure in the course of replacement of a fuel assembly. Subsequent rapid increase in humidity of the primary system resulted in damages of fuel elements in the core and the primary system was contaminated by fission products. In-reactor structures had been damaged, too. Activity had penetrated also into certain parts of the secondary system via leaking steam generators. Radiation situation in the course of both events on the plant site and around it had been below the level of limits specified. Based on a technical and economical justification of the demanding character of equipment repairs for the restoration of plant operation, and also due to a decision made not to continue with further construction of gas cooled reactors in Czechoslovakia, a decision was made in 1977 to terminate plant operation. The decision on the A1 plant decommissioning was issued in 1979.

  15. Microsoft Word - 2014-1-1 RCA Qtr 1 Metrics Attachment_R1

    Energy Savers [EERE]

    ContractProject Management Performance Metric FY 2014 Target FY 2014 Projected FY 2014 ... ContractProject Management Performance Metrics FY 2014 Target FY 2014 1 th Qtr Actual ...

  16. Microsoft Word - SWPF-15-DI-001_R1_Construction Turnover to C...

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

    Construction Turnover to Testing and Commissioning Oversight SWPF-15-DI-001, Rev. 1 September, 2015 SWPF-15-DI-001 Revision 1 Page 3 of 29 REV A Internal Review by DOE Construction ...

  17. OSMOSE program : statistical review of oscillation measurements in the MINERVE reactor R1-UO2 configuration.

    SciTech Connect (OSTI)

    Stoven, G.; Klann, R.; Zhong, Z.; Nuclear Engineering Division

    2007-08-28

    The OSMOSE program is a collaboration on reactor physics experiments between the United States Department of Energy and the France Commissariat Energie Atomique. At the working level, it is a collaborative effort between the Argonne National Laboratory and the CEA Cadarache Research Center. The objective of this program is to measure very accurate integral reaction rates in representative spectra for the actinides important to future nuclear system designs, and to provide the experimental data for improving the basic nuclear data files. The main outcome of the OSMOSE measurement program will be an experimental database of reactivity-worth measurements in different neutron spectra for the heavy nuclides. This database can then be used as a benchmark to verify and validate reactor analysis codes. The OSMOSE program (Oscillation in Minerve of isotopes in Eupraxic Spectra) aims at improving neutronic predictions of advanced nuclear fuels through oscillation measurements in the MINERVE facility on samples containing the following separated actinides: {sup 232}Th, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 243}Am, {sup 244}Cm, and {sup 245}Cm. The first part of this report provides an overview of the experimental protocol and the typical processing of a series of experimental results which is currently performed at CEA-Cadarache. In the second part of the report, improvements to this technique are presented, as well as the program that was created to process oscillation measurement results from the MINERVE facility in the future.

  18. Microsoft Word - EM SSAB Application September 2013 Update_FillableR.1

    Office of Environmental Management (EM)

    Message from Dave Geiser Environmental justice (EJ) is the fair treatment and meaningful involvement of all people regardless of race, color, national origin, or income with respect to the development, implementation, and enforcement of environmental laws, regulations, and policies. On February 11, 1994, President Clinton issued Executive Order (EO) 12898, Federal Actions to Address Environmental Justice in Minority Populations and Low-Income Populations, and he tasked each federal agency to

  19. Microsoft Word - SWPF-15-DI-001_R1_Construction Turnover to C&T Oversight

    Office of Environmental Management (EM)

    April 6, 2015 1 SAFETY SYSTEM OVERSIGHT ANNUAL AWARD PROGRAM OBJECTIVE The Safety System Oversight (SSO) Annual Award is a special award designed to recognize superior or exemplary service by an employee who has performed SSO functions. This special award program has been established in accordance with the requirements of Department of Energy (DOE) Order 331.1C, Employee Performance Management and Recognition Program. SAFETY SYSTEM OVERSIGHT ANNUAL AWARD The SSO Annual Award recipient is

  20. Photovoltaic Array Field Characterization Report. University of Toledo R1 Arrays

    SciTech Connect (OSTI)

    Silverman, Timothy J.; McNutt, Peter; Wohlgemuth, John

    2015-09-01

    We inspected two 6.2 kW systems of CdTe modules that had been deployed for approximately eight years. The report summarizes the findings, lists the observed defects and links one of these defects to a significant loss in performance in some modules.

  1. Microsoft Word - Final Draft FY-13 LWRS IPP R1 Clean Angie KAM...

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

    means the prudent use of resources - in this case, our nation's commercial nuclear power plants. Sustainability is defined as the ability to maintain safe and economic...

  2. Microsoft Word - DOE-ID-INL-16-012 R1.docx

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

    Approximately 150,000 sq. ft. of asphalt will be removed, the road base will be re-graded to ... Field Representative and the Cultural Resource Management Office as soon as possible. ...

  3. Microsoft PowerPoint - SRSCRO_Forum_01_27_2011R1.ppt [Compatibility Mode]

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

    SRS Overview Making the world a safer place Doug Dearolph Manager, NNSA Savannah River Site Office SRSCRO Forum January 2012 2 NNSA Mission Areas Defense Nuclear Nonproliferation Defense Programs Naval Reactors Maintain a safe, secure, and reliable nuclear weapons stockpile to help ensure the security of the U.S. and its allies, deter aggression, and support international stability Detect, prevent, and reverse the proliferation of weapons of mass destruction, and promote international nuclear

  4. Microsoft Word - DOE-ID-INL-13-004 R1.doc

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

    proposes to install glove boxes, laboratory equipment and laboratory hoods in the east ... (including, but not limited to, laboratory equipment, electronic hardware, ...

  5. Microsoft Word - CBU-PIT-2004-00010_R1.doc

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

    CBU-PIT-2004-00010 REVISION: 0 12/17/04 KEYWORDS Tank Closure, Tank 17, Tank 20, Modeling, Errata, Closure Module, General Closure Plan, Waste Characterization Report RETENTION: PERMANENT CLASSIFICATION: U Does not contain UCNI Tanks 17 and 20 Closure Errata B. A. Martin December 17, 2004 Westinghouse Savannah River Company Closure Business Unit Planning Integration & Technology Department Aiken, SC 29808 ________________________________________________________________________ Prepared for

  6. Microsoft Word - DOE-ID-INL-14-020 R1.docx

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

    and CFA-624 are currently using pressurized steam coils to provide heat to both buildings. ... Boiler USTs do not have to meet 40 CFR 280 requirements, including Subpart G closure ...

  7. Summary of Investigations on Technical Feasibility of Direct Disposal of Dual-Purpose Canisters R1

    Office of Energy Efficiency and Renewable Energy (EERE)

    This study has evaluated the technical feasibility of direct disposal in a geologic repository, of commercial spent nuclear fuel (SNF) in dual-purpose canisters (DPCs) of existing designs.  The...

  8. Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14) R1

    Office of Energy Efficiency and Renewable Energy (EERE)

    Results continue to support the earlier conclusion that direct disposal of DPCs is technically feasible, at least for some DPCs, and for some disposal concepts (geologic host media). Much of the...

  9. Microsoft Word - DP_cover_and_front matter_R1_Draft_3.DOC

    Energy Savers [EERE]

    ... ES-13 1-1 The Former Nuclear Fuel Reprocessing Plant and ... 1-22 2-1 Spent Fuel Reprocessing Diagram (PUREX ... The seams connecting the geomembrane panels would be ...

  10. Microsoft Word - DOE-ID-INL-16-006 R1.docx

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

    revision is to 1) update the Project Description with corrections to the program name changes, 2) to add in- town Research and Development (R&D) facilities, and 3) to ...

  11. Microsoft Word - 2014-5-27 RCA Qtr 2 Metrics Attachment_R1

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

    Second Quarter Overall Root Cause Analysis (RCA)Corrective Action Plan (CAP) Performance Metrics 1 ContractProject Management Performance Metric FY 2014 Target FY 2014 Projected ...

  12. Microsoft Word - SRR-CWDA-2011-00054_R1.doc

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

    Comment Response Matrix SRR-CWDA-2011-00054 for NRC Staff Comments on the Draft Basis for Section 3116 Revision 1 Determination and Associated Performance Assessment for the June 2011 F-Tank Farm at the Savannah River Site E Page 2 of 388 REVISION SUMMARY REV. # DESCRIPTION DATE OF ISSUE 0 Initial issue 5/2011 1 Updated reference document information in the responses to RAI-MEP-1 through RAI-MEP-6, CC- MEP-2, and in the reference list, for the following reference documents: DOE/SRS-WD-2011-001

  13. Microsoft Word - SRR-CWDA-2012-00026_R1_Text.doc

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

    ... A leak detection probe can be placed in the chamber through ... inches thick, in addition to the expected corrosion film. ...equipment damage) 34 Ultrasound with Oxalic Acid ...

  14. Microsoft Word - SRR-CWDA-2012-00045_R1.docx

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

    Section 3116(a). DOESRS-WD-2010-001 On October 27, 2011, NRC issued its Technical Evaluation Report for F-Area Tank Farm Facility, Savannah River Site, South Carolina. ...

  15. 272-AW_Bldg_Renovation_Mod1_CX-00017 r1.pdf

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

  16. LLNL Data Disk Evaluation Report and Information Gathering Document #449.R1.3

    SciTech Connect (OSTI)

    BeLue, A.

    2015-09-29

    This is a report on Data Storage Disk Evaluation and characterization. The purpose of this memo is to capture new recipients due to some recent characterization issues with the Hammer Mill process. The Data Storage Disk Evaluation report was generated utilizing data acquired during 2009 and 2010 from submitted storage media.

  17. Viability of Existing INL Facilities for Dry Storage Cask Handling R1

    Broader source: Energy.gov [DOE]

    This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks in support of the U.S. Department of Energy's plan for confirmatory dry storage project for high burnup fuel.

  18. Assessment of boreal forest historical C dynamics in Yukon River...

    Office of Scientific and Technical Information (OSTI)

    this study we applied a large-scale ecosystem model that included dynamics of organic soil horizons and soil organic matter characteristics of multiple pools to assess forest C...

  19. Packaging, Transportation and Recycling of NPP Condenser Modules - 12262

    SciTech Connect (OSTI)

    Polley, G.M.

    2012-07-01

    Perma-Fix was awarded contract from Energy Northwest for the packaging, transportation and disposition of the condenser modules, water boxes and miscellaneous metal, combustibles and water generated during the 2011 condenser replacement outage at the Columbia Generating Station. The work scope was to package the water boxes and condenser modules as they were removed from the facility and transfer them to the Perma-Fix Northwest facility for processing, recycle of metals and disposition. The condenser components were oversized and overweight (the condenser modules weighed ∼102,058 kg [225,000 lb]) which required special equipment for loading and transport. Additional debris waste was packaged in inter-modals and IP-1 boxes for transport. A waste management plan was developed to minimize the generation of virtually any waste requiring landfill disposal. The Perma-Fix Northwest facility was modified to accommodate the ∼15 m [50-ft] long condenser modules and equipment was designed and manufactured to complete the disassembly, decontamination and release survey. The condenser modules are currently undergoing processing for free release to a local metal recycler. Over three millions pounds of metal will be recycled and over 95% of the waste generated during this outage will not require land disposal. There were several elements of this project that needed to be addressed during the preparation for this outage and the subsequent packaging, transportation and processing. - Staffing the project to support 24/7 generation of large components and other wastes. - The design and manufacture of the soft-sided shipping containers for the condenser modules that measured ∼15 m X 4 m X 3 m [50 ft X 13 ft X 10 ft] and weighed ∼102,058 kg [225,000 lbs] - Developing a methodology for loading the modules into the shipping containers. - Obtaining a transport vehicle for the modules. - Designing and modifying the processing facility. - Movement of the modules at the processing facility. If any of these issues were not adequately resolved prior to the start of the outage, costly delays would result and the re-start of the power plant could be impacted. The main focus of this project was to find successful methods for keeping this material out of the landfills and preserving the natural resources. In addition, this operation provided a significant cost savings to the public utility by minimizing landfill disposal. The onsite portion of the project has been completed without impact to the overall outage schedule. By the date of presentation, the majority of the waste from the condenser replacement project will have been processed and recycled. The goals for this project included helping Energy Northwest maintain the outage schedule, package and characterize waste compliantly, perform transportation activities in compliance with 49CFR (Ref-1), and minimize the waste disposal volume. During this condenser replacement project, over three millions pounds of waste was generated, packaged, characterized and transported without injury or incident. It is anticipated that 95% of the waste generated during this project will not require landfill disposal. All of the waste is scheduled to be processed, decontaminated and recycled by June of 2012. (authors)

  20. New Generation Dresden NPP Demineralizer Vault Cleanup Project

    SciTech Connect (OSTI)

    Denton, M.S.; CET, Ph.D.; Forrester, K.; Azar, M.

    2008-07-01

    Electro-coagulation (EC) is a technique that facilitates rapid destabilization and flocculation of colloidal suspensions to cause the suspended solids to separate from slurry phase. It is generally accepted that coagulation is brought about primarily by the reduction of the net surface charge to a point where the colloidal particles, previously stabilized by electrostatic repulsion, can approach closely enough for van der Waals forces to hold them together and allow aggregation. In the EC process, the coagulant is generated in situ by electrolytic oxidation of an appropriate anode material (aluminum in this case). In this process, charged ionic species, metals or otherwise, and suspended solids are removed from wastewater by allowing them to interact with an ion having opposite charge, or with floc of metallic hydroxides generated electrochemically within the effluent. Typically, no supplementary organic polymer coagulant addition is required. Thus, electro-coagulation (EC) was found to be an attractive treatment option to rapidly destabilize the colloidal particulate phase, allowing more facile particulate removal by decantation and/or coarse filtration. However, the liquid medium must have some conductivity (> 100 {mu}mho is preferred), in order to allow effective electrical coupling with the EC electrodes. A very small amount of aluminum or sodium sulfate salts can be added to the feed slurry, adjusting the water quality parameters to a conductivity of >100 {mu}mho and a pH value near 6.0-7.0. The EC-treated vault slurry had a pH value near 6.5 (within the pH range for minimal solubility of amphoteric aluminum hydroxide). In contrast to untreated wastewater, the agglomerated particles in the EC-treated aliquot could be filtered relatively rapidly, yielding a clear filtrate, indicating that the flocs that have been formed are now > 20- {mu}m in size, are pumpable (high shear strength), and filterable/dewaterable with ease (low water content). Final waste volumes also show that the actual volumetric fraction of solids produced are relatively small. In order to estimate the amount of material (Al or Fe depending on the electrode material) added by the EC process, a rough rule of thumb has been found to be {approx}15 ppm per amp-minute. It was found with most wastewaters that Cs seeding (if that step is required) added {approx} 100 ppm Cs Seed and 10-15 ppm/amp minute additional floc from the electrodes. In a typical BWR wastewater case, where the TSS represented {<=} 0.15 wt% ({approx}1500 ppm). At 1.5 amp-min., the Al (III) added by the EC process would be {approx} 20 ppm, or {approx} 60 ppm as Al(OH){sub 3}. It was found the relatively low floc [{approx} 40 ppm as dried Al(OH){sub 3}] worked quite well for the high colloid level present ({approx}1500 ppm), and would be even more enhanced with the use of recycle. Even at that relatively low treatment dose, the colloidal TSS in the wastewater was effectively flocculated to yield agglomerates that were easily filtered and dewatered. Another rule of thumb is that, empirically, TDS (in mg/l) is typically {approx}0.5 X conductivity (in umho/cm). For instance, a conductivity reading of 100 umho/cm corresponds to about 50 ppm of TDS. As can be seen, the amount of material actually added in this vault cleanup of {approx}15 ppm per amp-min compared to the existing {approx}1500 ppm of TDS present (0.5 X conductivity of 3000 {mu}mho/cm) is minimal. In this vault cleanup, as a precautionary measure, the HIC was a specially designed Press-Pak with internal sheet filters, final dewatering leg, and a expandable, outer bladder if needed for final dewatering. It was found after filling the first HIC, of two, that the material dewatered and passed final dewatering tests without the need for the precautionary Press-Pak feature. Original estimates by the evaluation team estimated it would take some 11 to 12 HICs to remove the vault contents to a remote location for treatment, dewatering and final shipment. With the use of the SAFE{sup TM} Solution, the project was completed dur

  1. A computerized main control room for NPP: Development and investigation

    SciTech Connect (OSTI)

    Anokhin, A. N.; Marshall, E. C.; Rakitin, I. D.; Slonimsky, V. M.

    2006-07-01

    An ergonomics assessment of the control room at Leningrad Nuclear Power Plant has been undertaken as part of an international project funded by the EU TACIS program. The project was focused on the upgrading of the existing control facilities and the installation of a validation facility to evaluate candidate refurbishment proposals before their implementation at the plant. The ergonomics methodology applied in the investigation was wide ranging and included an analysis of reported events, extensive task analysis (including novel techniques) and validation studies using experienced operators. The paper addresses the potential difficulties for the human operator associated with fully computerized interfaces and shows how the validation facility and the outcomes from ergonomics assessment will be used to minimise any adverse impact on performance that may be caused by proposed control room changes. (authors)

  2. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems

    SciTech Connect (OSTI)

    Sindelar, R.L.

    2001-04-10

    Nuclear power plants (NPPs) must ensure that the emergency core cooling system (ECCS) or safety-related containment spray system (CSS) remains capable of performing its design safety function throughout the life of the plant. This requires ensuring that long-term core cooling can be maintained following a postulated loss-of-coolant accident (LOCA). Adequate safety operation can be impaired if the protective coatings which have been applied to the concrete and steel structures within the primary containment fail, producing transportable debris which could then accumulate on BWR ECCS suction strainers or PWR ECCS sump debris screens located within the containment. This document will present the data collected during the investigation of coating specimens from plants.

  3. Degradation and failure characteristics of NPP containment protective coating systems

    SciTech Connect (OSTI)

    Sindelar, R.L.

    2000-03-30

    A research program to investigate the performance and potential for failure of Service Level 1 coating systems used in nuclear power plant containment is in progress. The research activities are aligned to address phenomena important to cause failure as identified by the industry coatings expert panel. The period of interest for performance covers the time from application of the coating through 40 years of service, followed by a medium-to-large break loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario. The interactive program elements are discussed in this report and the application of these elements to the System 5 coating system (polyamide epoxy primer, carbon steel substrate) is used to evaluate performance.

  4. ARM - Field Campaign - ARM Radiosondes for NPOESS/NPP Validation...

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

    - NSA Comments? We would love to hear from you Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : ARM Radiosondes for NPOESSNPP Validation - NSA ...

  5. Fuel and Core Design Experiences in Cofrentes NPP

    SciTech Connect (OSTI)

    Garcia-Delgado, L.; Lopez-Carbonell, M.T.; Gomez-Bernal, I.

    2002-07-01

    The electricity market deregulation in Spain is increasing the need for innovations in nuclear power generation, which can be achieved in the fuel area by improving fuel and core designs and by introducing vendors competition. Iberdrola has developed the GIRALDA methodology for design and licensing of Cofrentes reloads, and has introduced mixed cores with fuel from different vendors. The application of GIRALDA is giving satisfactory results, and is showing its capability to adequately reproduce the core behaviour. The nuclear design team is acquiring an invaluable experience and a deep knowledge of the core, very useful to support cycle operation. Continuous improvements are expected for the future in design strategies as well as in the application of new technologies to redesign the methodology processes. (authors)

  6. ELECTROCHEMICAL CORROSION TESTS FOR TANK 241-AY-101 CORE 325 SEGMENTS 16R1 & 16R2

    SciTech Connect (OSTI)

    DUNCAN JB; WYRWAS RB

    2007-11-14

    The interstitial liquid in the double-shell tank 241-AY-101 settled solids layer is below the hydroxide chemistry control limit required by HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements, Administrative Control 5.16, 'Corrosion Mitigation Controls'. Operating tanks outside of the specification may increase the propensity corrosion of the carbon steel wall. This report is concerned with generalized electrochemical corrosion mechanism that may occur at specific loci. All cyclic potentiodynamic polarization scans exhibited a negative hysteresis, scan reversing at lower current density, indicating that there was no pitting propensity. The general electrochemical corrosion rates ranged from 4.4E-02 to 1.5E-03 mpy with the first round of coupons, while the second round yielded corrosion rates of 2.5E-03 to 2.9E-02 mpy.

  7. Thermolysis of (1R,2R)-1,2-dideuteriocyclobutane. An application of vibrational circular dichroism to kinetic analysis

    SciTech Connect (OSTI)

    Chickos, J.S.; Annamalai, A.; Keiderling, T.A.

    1986-07-23

    The relative rates of geometric isomerization to racemization have been studied for the title compound by using a combination of infrared (IR) and vibrational circular dichroism (VCD) spectroscopies, respectively. The results are interpreted with a kinetic and mechanistic scheme which parallels that used by Berson, Pedersen, and Carpenter on a similar study of chiral cyclopropane-d/sub 2/ thermolysis. Relative rates of isomerization to stereomutation of 1.5 +/- 0.4 were obtained which can be interpreted to be consistent with a mechanism best described by random methylene rotation in tetramethylene-d/sub 2/. This is the first application of VCD to kinetic analysis, and the advantages of IR techniques over the more usually employed UV spectroscopies to this type of basic mechanistic problem are illustrated.

  8. Microsoft Word - P&RA CoP 2016 Techncial Exchange Draft Agenda 2016-08-16 R1

    Office of Environmental Management (EM)

    Department of Energy NationalPolicyAssurancesAwardTermsFinal81804.doc Microsoft Word - NationalPolicyAssurancesAwardTermsFinal81804.doc Microsoft Word - NationalPolicyAssurancesAwardTermsFinal81804.doc (31.13 KB) More Documents & Publications Microsoft Word - National Policy AssurancesAwardTermsREVJuly2005.doc National Policy Assurances to be Incorporated as Award Terms Microsoft Word - NationalPolicyAssurances5-06.doc

    freshfrommexico.com info@freshfrommexico.com PO Box 848 Nogales,

  9. Title V Semi-Annual Emissions Report for Permit P100R1 July 1, 2011 - December 31, 2011

    SciTech Connect (OSTI)

    Whetham, Walter

    2012-03-15

    Reports of actual emissions from permitted sources in Section 2.0 shall be submitted on a 6 month basis. Reports shall not include emissions from insignificant activities. Emission estimates of criteria pollutants NOx, CO, SO2, PM and VOCs shall not include fugitive emissions. Emission estimates of HAPs shall include fugitive emissions. The reports shall include a comparison of actual emissions that occurred during the reporting period with the facility-wide allowable emission limits specified in Section 2.11 of this permit. The report required by Condition 4.1 shall be submitted within 90 days from the end of the reporting period. The semiannual report required by Condition 4.2 shall be submitted within 45 days from the end of the reporting period. The reporting periods are January 1st to June 30th and July 1st to December 31st. This condition is pursuant to 20.2.70.302.E.1 NMAC.

  10. Estimation of net primary productivity using a process-based model in Gansu Province, Northwest China

    SciTech Connect (OSTI)

    Wang, Peijuan; Xie, Donghui; Zhou, Yuyu; E, Youhao; Zhu, Qijiang

    2014-01-16

    The ecological structure in the arid and semi-arid region of Northwest China with forest, grassland, agriculture, Gobi, and desert, is complex, vulnerable, and unstable. It is a challenging and sustaining job to keep the ecological structure and improve its ecological function. Net primary productivity (NPP) modeling can help to improve the understanding of the ecosystem, and therefore, improve ecological efficiency. The boreal ecosystem productivity simulator (BEPS) model provides the possibility of NPP modeling in terrestrial ecosystem, but it has some limitations for application in arid and semi-arid regions. In this paper we improve the BEPS model, in terms of its water cycle by adding the processes of infiltration and surface runoff, to be applicable in arid and semi-arid regions. We model the NPP of forest, grass, and crop in Gansu Province as an experimental area in Northwest China in 2003 using the improved BEPS model, parameterized with moderate resolution remote sensing imageries and meteorological data. The modeled NPP using improved BEPS agrees better with the ground measurements in Qilian Mountain than that with original BEPS, with a higher R2 of 0.746 and lower root mean square error (RMSE) of 46.53 gC/m2 compared to R2 of 0.662 and RMSE of 60.19 gC/m2 from original BEPS. The modeled NPP of three vegetation types using improved BEPS show evident differences compared to that using original BEPS, with the highest difference ratio of 9.21% in forest and the lowest value of 4.29% in crop. The difference ratios between different vegetation types lie on the dependence on natural water sources. The modeled NPP in five geographic zones using improved BEPS are higher than those with original BEPS, with higher difference ratio in dry zones and lower value in wet zones.

  11. The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2

    SciTech Connect (OSTI)

    Kupca, L.; Beno, P.

    1997-04-01

    A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided.

  12. The resilience and functional role of moss in boreal and arctic...

    Office of Scientific and Technical Information (OSTI)

    influence the cycling of water, nutrients, energy and carbon. Here we use a literature review and synthesis as well as model simulations to explore the role of moss in ecological...

  13. Emission and transport of cesium-137 from boreal biomass burning in the summer of 2010

    SciTech Connect (OSTI)

    Strode, S.; Ott, Lesley E.; Pawson, Steven; Bowyer, Ted W.

    2012-05-09

    While atmospheric concentrations of cesium-137 have decreased since the nuclear testing era, resuspension of Cs-137 during biomass burning provides an ongoing emission source. The summer of 2010 was an intense biomass burning season in western Russia, with high levels of particulate matter impacting air quality and visibility. A radionuclide monitoring station in western Russia shows enhanced airborne Cs-137 concentrations during the wildfire period. Since Cs-137 binds to aerosols, satellite observations of aerosols and fire occurrences can provide a global-scale context for Cs-137 emissions and transport during biomass burning events.

  14. On the influence of shrub height and expansion on boreal climate...

    Office of Scientific and Technical Information (OSTI)

    Authors: Bonfils, C ; Phillips, T ; Lawrence, D ; Cameron-Smith, P ; Riley, W ; Subin, Z Publication Date: 2011-08-22 OSTI Identifier: 1113486 Report Number(s): LLNL-JRNL-495260 ...

  15. Risk of large-scale fires in boreal forests of Finland under changing climate

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

    Lehtonen, I.; Venäläinen, A.; Kamarainen, M.; Peltola, H.; Gregow, H.

    2016-01-21

    Here, the target of this work was to assess the impact of projected climate change on forest-fire activity in Finland with special emphasis on large-scale fires. In addition, we were particularly interested to examine the inter-model variability of the projected change of fire danger. For this purpose, we utilized fire statistics covering the period 1996-2014 and consisting of almost 20,000 forest fires, as well as daily meteorological data from five global climate models under representative concentration pathway RCP4.5 and RCP8.5 scenarios. The model data were statistically downscaled onto a high-resolution grid using the quantile-mapping method before performing the analysis. Inmore » examining the relationship between weather and fire danger, we applied the Canadian fire weather index (FWI) system. Our results suggest that the number of large forest fires may double or even triple during the present century. This would increase the risk that some of the fires could develop into real conflagrations which have become almost extinct in Finland due to active and efficient fire suppression. However, the results reveal substantial inter-model variability in the rate of the projected increase of forest-fire danger, emphasizing the large uncertainty related to the climate change signal in fire activity. We moreover showed that the majority of large fires in Finland occur within a relatively short period in May and June due to human activities and that FWI correlates poorer with the fire activity during this time of year than later in summer when lightning is a more important cause of fires.« less

  16. U*2-5-~~~~ D0E10R1DOE/OR/20722-77 Formerly Utilized Sites Remedial...

    Office of Legacy Management (LM)

    DE-AC05-810R20722 POST-REMEDIAL ACTION REPORT FOR THE RESIDENTIAL PROPERTIES ON DAVISON ... Neither the United States nor the United States Department of Energy, nor any of their ...

  17. Gas Generation and Release in Near-Surface Repository at Armenian NPP - 13372

    SciTech Connect (OSTI)

    Grigoryan, G.; Amirjanyan, A.; Hovhannisyan, A.; Gondakyan, Y.

    2013-07-01

    The potential nuclear waste repository at Armenian Nuclear Power Plant (ANPP) can store Low and Intermediate Level Radioactive waste (LL/ILW). In this kind of near-surface repository for radioactive waste, significant quantities of gases may be generated as a result of microbial degradation and corrosion. A discussion is presented of the microbial and chemical degradation of cellulose. For the release of gas, it is assumed that the complete conversion of cellulosic wastes to gases by the action of microbes, is, in principle, permitted. Released radioactive gases such as {sup 14}CO{sub 2} and {sup 14}CH{sub 4} could have a direct pathway to the atmosphere. The potential impact of gas generation, accumulation and migration on the long-term of repository, should therefore be assessed properly. We present here safety assessment result of gas producing radioactive waste disposal by the inhalation dose to a maximally exposed individual above ground, based on some conservative assumptions about release from waste as well as gas generation calculations. (authors)

  18. Preparation and Execution of the GIS First Overhaul for Qinshan NPP Phase One

    SciTech Connect (OSTI)

    Kaihong Lou; Jiapeng Yan

    2006-07-01

    This paper addresses the necessity and feasibility of the first major overhaul on the GIS based on the analysis of the special conditions and the issues we confronted; After the comparison of various schemes, the optimized scheme is put forward; the paper also expounds the proper preparation and cautious practice which led to the hard but final accomplishment of the initial overhaul on the GIS; this article further explains the necessity of the major overhaul on the GIS through the disposal of abnormalities during the execution of this major overhaul. (authors)

  19. Cost estimation of HVDC transmission system of Bangka’s NPP candidates

    SciTech Connect (OSTI)

    Liun, Edwaren Suparman

    2014-09-30

    Regarding nuclear power plant development in Bangka Island, it can be estimated that produced power will be oversupply for the Bangka Island and needs to transmit to Sumatra or Java Island. The distance between the regions or islands causing considerable loss of power in transmission by alternating current, and a wide range of technical and economical issues. The objective of this paper addresses to economics analysis of direct current transmission system to overcome those technical problem. Direct current transmission has a stable characteristic, so that the power delivery from Bangka to Sumatra or Java in a large scale efficiently and reliably can be done. HVDC system costs depend on the power capacity applied to the system and length of the transmission line in addition to other variables that may be different.

  20. REVIEW OF PRACTICE FOR DEEPLY EMBEDDED/BURIED NPP STRUCTURES SUBJECT TO SEISMIC LOADINGS.

    SciTech Connect (OSTI)

    XU,J.HOFMAYER,C.MILLER,C.GRAVES,H.

    2004-03-24

    Motivated by many design considerations, several conceptual designs for advanced reactors have proposed that the entire reactor building and a significant portion of the steam generator building will be either partially or completely embedded below grade. For the analysis of seismic events, the soil-structure interaction (SSI) effect and passive earth pressure for these types of deeply embedded structures will have a significant influence on the predicted seismic response. Sponsored by the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) is carrying out a research program to assess the significance of these proposed design features for advanced reactors, and to evaluate the existing analytical methods to determine their applicability and adequacy in capturing the seismic behavior of the proposed designs. This paper summarizes a literature review performed by BNL to determine the state of knowledge and practice for seismic analyses of deeply embedded and/or buried (DEB) nuclear containment type structures. Included in the paper is BNL's review of the open literature of existing standards, tests, and practices that have been used in the design and analysis of DEB structures. The paper also provides BNL's evaluation of available codes and guidelines with respect to seismic design practice of DEB structures. Based on BNL's review, a discussion is provided to highlight the applicability of the existing technologies for seismic analyses of DEB structures and to identify gaps that may exist in knowledge and potential issues that may require better understanding and further research.

  1. The characteristics of local atmospheric circulation around the Wolsung NPP in Korea

    SciTech Connect (OSTI)

    Lee, G.B.; Lee, M.C.; Song, Y.I.

    1998-12-31

    The transport of air pollutants in coastal regions has been known to be strongly affected by the mesoscale atmospheric circulations such as sea-land breezes. These mesoscale atmospheric circulations depend on synoptic weather conditions. In this study, a three-dimensional sea-land breeze model was developed to evaluate the effects of the sea and land breezes on the atmospheric dispersion of radioactive materials released from nuclear power plants in Korea. In the model, the hydrostatic primitive equations in the terrain-following coordinate system were used. The mesoscale atmospheric circulation simulation were carried out under various synoptic weather conditions for all seasons around the Wolsung nuclear power plant site.

  2. The Radioactivity Characteristics of the NPP Charcoal Sample Contaminated by Carbon-14 - 13531

    SciTech Connect (OSTI)

    Kim, Hee Reyoung

    2013-07-01

    The radioactivity of {sup 14}C-contaminated charcoal sample was analyzed by using a high temperature oxidation and liquid scintillation counting method. The radioactivity of the sample was monotonically increased according to the increase of the combustion time at each temperature where the experimental uncertainty was calculated in the 95 % confidence level. It showed that the {sup 14}C radioactivity was not completely extracted from the sample by simply increasing the combustion time unless the combustion temperature was high enough. The higher the combustion temperature was, the higher the recovery during the first 30 minutes was. The first 30 minute recoveries were 100 % at a temperature equal to or greater than 450 deg. C. The ratios of the recovery during the first 30 minutes to the total recovery during whole duration were more than 90 % at each experiment temperature. It was understood that the temperature was a critical factor for the complete removal of the {sup 14}C from the waste sample. (authors)

  3. The concepts of leak before break and absolute reliability of NPP equipment and piping

    SciTech Connect (OSTI)

    Getman, A.F.; Komarov, O.V.; Sokov, L.M.

    1997-04-01

    This paper describes the absolute reliability (AR) concept for ensuring safe operation of nuclear plant equipment and piping. The AR of a pipeline or component is defined as the level of reliability when the probability of an instantaneous double-ended break is near zero. AR analysis has been applied to Russian RBMK and VVER type reactors. It is proposed that analyses required for application of the leak before break concept should be included in AR implementation. The basic principles, methods, and approaches that provide the basis for implementing the AR concept are described.

  4. Managing the Night Off-Peak Power Demand in the Central Region UPS with Newly Commissioned NPP Capacities

    SciTech Connect (OSTI)

    Aminov, R. Z.; Pron, D. M.

    2014-01-15

    The use of hydrogen technologies as a controlled-load consumer based on the newly commissioned base-load nuclear power plants to level out the daily load profile is justified for the Unified Power System (UPS) of the Central Region of Russia, as an example, for the period till 2020.

  5. Peculiarities of highly burned-up NPP SNF reprocessing and new approach to simulation of solvent extraction processes

    SciTech Connect (OSTI)

    Fedorov, Y.S.; Zilberman, B.Y.; Goletskiy, N.D.; Puzikov, E.A.; Ryabkov, D.V.; Rodionov, S.A.; Beznosyuk, V.I.; Petrov, Y.Y.; Saprykin, V.F.; Murzin, A.A.; Bibichev, B.A.; Aloy, A.S.; Kudinov, A.S.; Blazheva, I.V.; Kurenkov, N.V.

    2013-07-01

    Substantiation, general description and performance characteristics of a reprocessing flowsheet for WWER-1000 spent fuel with burn-up >60 GW*day/t U is given. Pu and U losses were <0.1%, separation factor > 10{sup 4}; their decontamination factor from γ-emitting fission products was 4*10{sup 4} and 3*10{sup 7}, respectively. Zr, Tc, Np removal was >98% at U and Pu losses <0.05%. A new approach to simulation of extraction equilibrium has been developed. It is based on a set of simultaneous chemical reactions characterized by apparent concentration constants. A software package was created for simulation of spent fuel component distribution in multistage countercurrent extraction processes in the presence of salting out agents. (authors)

  6. The LBB methodology application results performed on the safety related piping of NPP V-1 in Jaslovske Bohunice

    SciTech Connect (OSTI)

    Kupca, L.; Beno, P.

    1997-04-01

    A broad overview of the leak before break (LBB) application to the Slovakian V-1 nuclear power plant is presented in the paper. LBB was applied to the primary cooling circuit and surge lines of both WWER 440 type units, and also used to assess the integrity of safety related piping in the feed water and main steam systems. Experiments and calculations performed included analyses of stresses, material mechanical properties, corrosion, fatigue damage, stability of heavy component supports, water hammer, and leak rates. A list of analysis results and recommendations are included in the paper.

  7. The Use of Tritiated Wastewater from NPP Cernavoda to Estimate Maximum Soluble Pollutants on Danube-Black Sea Channel

    SciTech Connect (OSTI)

    Varlam, Carmen; Stefanescu, Ioan; Patrascub, Vasile; Varlam, Mihai; Raceanu, Mircea; Enache, Adrian; Bucur, Cristina

    2005-07-15

    In this paper we propose to use tritiated liquid effluents from a CANDU type reactor as a tracer, to study hydrodynamics on Danube-Black Sea Channel. Tritiated water can be used to simulate the transport and dispersion of solutes in mentioned Channel, because it has the same physical characteristic as water. Measured tracer response curves produced from controlled evacuations provide an efficient method of obtaining necessary data. This paper presents the establishing of proper mixing length, and the base line of tritium concentration in studied area. These first steps were used to construct the unit-peak attenuation (UPA) curve for a sector of the Danube-Black Sea Channel.

  8. http://www.wmsym.org/archives/2005/72.html

    National Nuclear Security Administration (NNSA)

    Repository Near Cernavoda NPP 3 Management of Low-Level Liquid Waste from Underground Tanks of NPP A- 1 in Slovakia - Retrieval, Treatment, Transport and Disposal 4 Operational...

  9. Hot Electron Diagnostic in a Solid Laser Target by K-Shell Lines Measurement from Ultra-Intense Laser-Plasma Interactions R=1.06 (micron)m, 3x10 W/cm -2(less than or equal to) 500 J

    SciTech Connect (OSTI)

    Yasuike, K.; Wharton, K.B.; Key, M.; Hatchett, S.; Snavely, R.

    2000-07-27

    Characterization of hot electron production (a conversion efficiency from laser energy into electrons) from ultra intense laser-solid target interaction by observing molybdenum (Mo) K{beta} as well as K{alpha} emissions from a buried fluorescence tracer layer in the targets has been done. The experiments used 1.06 {micro}m laser light with an intensity of from 2 x 10{sup 18} up to 3 x 10{sup 20} W cm{sup -2} (20-0.5 ps pulse width) and an on target laser energy of 280-500 J. The conversion efficiency from the laser energy into the energy, carried by hot electrons, has been estimated to be {approx}50% for the 0.5 ps shots at an on-target laser intensity of 3 x 10{sup 20} W cm{sup -2}, which increased from {approx}30% at 1 x 10{sup 19} W cm{sup -2} 5 ps shots and {approx} 12% at 2 x 10{sup 18} W cm{sup -2} 20 ps shots.

  10. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    permafrost soils of boreal forest ecosystems, where it is currently protected from decomposition. The surface organic horizons insulate the deeper soil from variations in...

  11. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Boreal forests, situated in a circumpolar belt in the Northern latitudes throughout the United States, Canada, Russia, and Scandinavia, are, of all biomes, among the most active ...

  12. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    (limit 5000) Have feedback or suggestions for a way to improve these results? The resilience and functional role of moss in boreal and arctic ecosystems Turetsky, Merritt ;...

  13. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Nuclear Security Agency Service Center (United States) ... Net primary productivity (NPP) modeling can help to improve the understanding of the ecosystem, and therefore, improve ...

  14. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... productivity simulator (BEPS) model provides the possibility of NPP modeling in terrestrial ecosystem, but it has some limitations for application in arid and semi-arid regions. ...

  15. RESIDUAL STRESSES IN ADDITIVELY MANUFACTURED INCONEL 718 ENGINE...

    Office of Scientific and Technical Information (OSTI)

    Title: RESIDUAL STRESSES IN ADDITIVELY MANUFACTURED INCONEL 718 ENGINE MOUNT Authors: Watkins, Thomas R 1 ; Cornwell, Paris A 1 ; Dehoff, Ryan R 1 ; Nangia, Vinod 2 ; ...

  16. PRELIMINARY DEMONSTRATION REACTOR POINT DESIGN FOR THE FLUORIDE...

    Office of Scientific and Technical Information (OSTI)

    HIGH-TEMPERATURE REACTOR Authors: Qualls, A L 1 ; Betzler, Benjamin R 1 ; Brown, Nicholas R 1 ; Carbajo, Juan 1 ; Greenwood, Michael Scott 1 ; Hale, Richard...

  17. Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point...

    Office of Scientific and Technical Information (OSTI)

    ... Authors: Qualls, A. L. 1 ; Betzler, Benjamin R. 1 ; Carbajo, Juan 1 ; Hale, Richard Edward 1 ; Harrison, Thomas J. 1 ; Powers, Jeffrey J. 1 ; Robb, Kevin R. 1 ; ...

  18. Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations

    SciTech Connect (OSTI)

    Katya L Le Blanc; Ronald L Boring; David I Gertman

    2001-11-01

    With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

  19. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... On the influence of shrub height and expansion on boreal climate Bonfils, C ; Phillips, T ; Lawrence, D ; Cameron-Smith, P ; Riley, W ; Subin, Z Full Text Available August 2011 ...

  20. Modeling the effects of fire severity and climate warming on...

    Office of Scientific and Technical Information (OSTI)

    in permafrost to decomposition. In this study we ask how warming and fire regime may influence spatial and temporal changes in active layer and carbon dynamics across a boreal...

  1. Aircraft-measured indirect cloud effects from biomass burning...

    Office of Scientific and Technical Information (OSTI)

    The incidence of wildfires in the Arctic and subarctic is increasing; in boreal North America, for example, the burned area is expected to increase by 200-300% over the next 50-100 ...

  2. Evaluation of the Parameters of Radioactive Contamination of Soils

    SciTech Connect (OSTI)

    Panasyuk M.I.; Skorbun A.D.; Klyuchnikov O.O.

    2002-02-26

    After Chornobyl NPP (ChNPP) accident the territory near destroyed Unit 4 (that now with the special confinement has the name the ''Shelter'' object) is contaminated of fuel fallouts. During liquidation of the accident consequences this territory was covered with pure earth, concrete, etc. As a result a contaminated anthropogenic layer of the soil on the depth up to 10 m was formed. Now the problem of contamination estimation and the soils management arose. For this tasks a gamma logging method was modified conformably to ChNPP conditions. The methods for necessary coefficients receiving and log treatment have been suggested.

  3. Variation and Trends of Landscape Dynamics, Land Surface Phenology...

    Office of Scientific and Technical Information (OSTI)

    The NPP increased by 2.68 gC m-2yr-2 in more Appalachian Mountains regions from 1981 to 2000. The comparison with the North America reveals the effects of topography and ...

  4. NASA/Ames Global Emissions Data Set (GLEMIS) | Open Energy Information

    Open Energy Info (EERE)

    sets include global maps for predicted fluxes of soil nitrogen gases (N2O and NO), methane (CH4), and carbon monoxide (CO), plus predictions of net primary production (NPP) and...

  5. RAVEN as Control Logic and Probabilistic Risk Assessment Driver for RELAP-7

    SciTech Connect (OSTI)

    C. Rabiti; A. Alfonsi; D. Mandelli; J. Cogliati; R. Martineau

    2012-11-01

    The Next Generation of System Analysis Code (NGSAC) [1] aims to model and simulate the Nuclear Power Plant (NPP) thermo-hydraulic behavior with high level of accuracy. In this respect, Idaho National Laboratory (INL) is developing a NGSAC (known as RELAP-7) which will allow to model NPP responses for a set of accident scenarios (e.g., loss of off-site power).

  6. AmeriFlux CA-NS4 UCI-1964 burn site wet

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS4 UCI-1964 burn site wet. Site Description - The UCI-1964 wet site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  7. AmeriFlux CA-NS3 UCI-1964 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS3 UCI-1964 burn site. Site Description - The UCI-1964 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  8. AmeriFlux CA-NS7 UCI-1998 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS7 UCI-1998 burn site. Site Description - The UCI-1998 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  9. AmeriFlux CA-NS8 UCI-2003 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS8 UCI-2003 burn site. Site Description - The UCI-2003 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  10. AmeriFlux CA-NS1 UCI-1850 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS1 UCI-1850 burn site. Site Description - The UCI-1850 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  11. AmeriFlux CA-NS5 UCI-1981 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS5 UCI-1981 burn site. Site Description - The UCI-1981 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  12. AmeriFlux CA-NS6 UCI-1989 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS6 UCI-1989 burn site. Site Description - The UCI-1989 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  13. AmeriFlux CA-NS2 UCI-1930 burn site

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Goulden, Mike [University of California - Irvine

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-NS2 UCI-1930 burn site. Site Description - The UCI-1930 site is located in a continental boreal forest, dominated by black spruce trees, within the BOREAS northern study area in central Manitoba, Canada. The site is a member of a chronological series of sites that are representative secondary succession growth stages after large stand replacement fires. Black spruce trees undergo a slow growth process enabling the accurate determination of the chronosequence of stand age disturbance. Additionally, boreal forests make up approximately 25% of forest ecosystems on earth. With both of these in mind, the UCI sites provide an excellent location to study the CO2 exchange between the atmosphere and boreal forest ecosystems as a function of sequential wildfires.

  14. Clean Air for London (CLEARFLO) Final Campaign Summary (Technical...

    Office of Scientific and Technical Information (OSTI)

    Authors: Worsnop, D. R. 1 ; Williams, L. R. 1 ; Herndon, S. C. 1 ; Dubey, M. 2 ; Ng, N. L. 3 ; Thornton, J. 4 ; Knighton, B. 5 ; Coulter, R. 6 ; Prvt, Ash 7 + ...

  15. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Gehin, Jess C (2) Bari, R. (1) Baylor, Larry R (1) Bell, Gary L (1) Bradley, Eric Craig ... Joel Lee ; Carbajo, Juan J ; Felde, David K January 2014 Comparison of Alternatives ...

  16. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Brophy, John R. (1) Buratti, Bonnie J. (1) Ervin, Joan (1) Fernandez, Yan R. (1) Grundy, ... John R. ; Buratti, Bonnie J. ; Ervin, Joan ; et al Today, our questions and ...

  17. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    ... Lang, Jared (1) Meech, Karen J. (1) Newhouse, Alan (1) Noble, Robert J. (1) Oleson, Steven R. (1) Schmidt, George R. (1) Spilker, Thomas (1) West, John L. (1) Save Results Save ...

  18. UTILITY_ID","UTILNAME","STATE_CODE","YEAR","MONTH","RES_REV ...

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

    ...0,0,183241,2189905,1081602 12919,"Morenci Water and Electric","AZ","2007R",1,154,1330,1816... 17612,"Southern California Water Co","CA","2007R",1,1831,8334,21746,1030,47...

  19. Radiochemistry Results from the IER-163 COMET Irradiation (Technical...

    Office of Scientific and Technical Information (OSTI)

    The results from the non-destructive and radiochemical analyses of six of these foils are presented. Authors: Jackman, Kevin R. 1 ; Bredeweg, Todd Allen 1 ; Schake, Ann R. 1 ...

  20. FL J. Smith, Jr.

    Office of Legacy Management (LM)

    ct. B. Duillap (THPJJs L. Kassel) FL J. Smith, Jr. c c Kelley from R. 1. Cook, Kslley from R. 1. Cook, J J cit cit In accordawe with Secret memorandum dated October , 1951 ta IA. ...

  1. I IIII1IiI II1Ii

    Office of Legacy Management (LM)

    I * - c-- . ;- . '--- - A ... * ' ' - * 'A r? -: * '; ' ' - ' .: 1', - '. *, , .. I ,, *,, . * .t1- ) ' , ** J' * *I :* : - - I j-- - - * I- , -j -. -** :- * * . *' ' , 9 ;* 3 . ...

  2. Development of an NDA system for high-level waste from the Chernobyl new safe confinement construction site

    SciTech Connect (OSTI)

    Lee, Sang-yoon; Browne, Michael C; Rael, Carlos D; Carroll, Colin J; Sunshine, Alexander; Novikov, Alexander; Lebedev, Evgeny

    2010-01-01

    In early 2009, preliminary excavation work has begun in preparation for the construction of the New Safe Confinement (NSC) at the Chernobyl Nuclear Power Plant (ChNPP) in Ukraine. The NSC is the structure that will replace the present containment structure and will confine the radioactive remains of the ChNPP Unit-4 reactor for the next 100 years. It is expected that special nuclear material (SNM) that was ejected from the Unit-4 reactor during the accident in 1986 could be uncovered and would therefore need to be safeguarded. ChNPP requested the assistance of the United States Department of Energy/National Nuclear Security Administration (NNSA) with developing a new non-destructive assay (NDA) system that is capable of assaying radioactive debris stored in 55-gallon drums. The design of the system has to be tailored to the unique circumstances and work processes at the NSC construction site and the ChNPP. This paper describes the Chernobyl Drum Assay System (CDAS), the solution devised by Los Alamos National Laboratory, Sonalysts Inc., and the ChNPP, under NNSA's International Safeguards and Engagement Program (INSEP). The neutron counter measures the spontaneous fission neutrons from the {sup 238}U, {sup 240}Pu, {sup 244}Cm in a waste drum and estimates the mass contents of the SNMs in the drum by using of isotopic compositions determined by fuel burnup. The preliminary evaluation on overall measurement uncertainty shows that the system meets design performance requirements imposed by the facility.

  3. Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4

    SciTech Connect (OSTI)

    Wang, S.-J.; Chien, C.-S.; Wang, T.-C.; Chiang, K.-S

    2000-11-15

    The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release fractions associated with the SBO accident were simulated. The predicted results are plausible and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed. The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future.

  4. The Pleistocene biogeography of eastern North America: A nonmigration scenario for deciduous forest

    SciTech Connect (OSTI)

    Loehle, C.; Iltis, H.

    1998-12-31

    The current reconstruction of the vegetation of eastern North America at the last glacial maximum postulates a very wide zone of tundra and boreal forest south of the ice. This reconstruction requires that the deciduous forest retreated far to the south. The authors believe that this reconstruction is seriously in error. Geologic evidence for glacial activity or tundra is absent from the southern Appalachians. Positive evidence for boreal forest is based on pollen identifications for Picea, Betula, and Pinus, when in reality southern members of these genera have pollen that cannot be distinguished from that of northern members. Further, pollen of typical southern species such as oaks and hickories occurs throughout profiles that past authors had labeled boreal. Pollen evidence for a far southern deciduous forest refuge is lacking. Data on endemics are particularly challenging for the scenario in which deciduous forest migrated to the south and back. The southern Appalachian region is rife with endemics that are often extreme-habitat specialists unable to migrate. The previously glaciated zone is almost completely lacking in endemics. Outlier populations, range boundaries, and absence of certain hybrids all argue against a large boreal zone. The new reconstruction postulates a cold zone no more than 75--100 miles wide south of the ice in the East.

  5. Cognitive decision errors and organization vulnerabilities in nuclear power plant safety management: Modeling using the TOGA meta-theory framework

    SciTech Connect (OSTI)

    Cappelli, M.; Gadomski, A. M.; Sepiellis, M.; Wronikowska, M. W.

    2012-07-01

    In the field of nuclear power plant (NPP) safety modeling, the perception of the role of socio-cognitive engineering (SCE) is continuously increasing. Today, the focus is especially on the identification of human and organization decisional errors caused by operators and managers under high-risk conditions, as evident by analyzing reports on nuclear incidents occurred in the past. At present, the engineering and social safety requirements need to enlarge their domain of interest in such a way to include all possible losses generating events that could be the consequences of an abnormal state of a NPP. Socio-cognitive modeling of Integrated Nuclear Safety Management (INSM) using the TOGA meta-theory has been discussed during the ICCAP 2011 Conference. In this paper, more detailed aspects of the cognitive decision-making and its possible human errors and organizational vulnerability are presented. The formal TOGA-based network model for cognitive decision-making enables to indicate and analyze nodes and arcs in which plant operators and managers errors may appear. The TOGA's multi-level IPK (Information, Preferences, Knowledge) model of abstract intelligent agents (AIAs) is applied. In the NPP context, super-safety approach is also discussed, by taking under consideration unexpected events and managing them from a systemic perspective. As the nature of human errors depends on the specific properties of the decision-maker and the decisional context of operation, a classification of decision-making using IPK is suggested. Several types of initial situations of decision-making useful for the diagnosis of NPP operators and managers errors are considered. The developed models can be used as a basis for applications to NPP educational or engineering simulators to be used for training the NPP executive staff. (authors)

  6. Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant

    SciTech Connect (OSTI)

    Meijing Wu; Guozhang Shen

    2006-07-01

    The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

  7. Plant maintenance and outage management issue, 2005

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2005-01-15

    The focus of the January-February issue is on plant maintenance and outage managment. Major articles/reports in this issue include: Dawn of a new era, by Joe Colvin, Nuclear Energy Institute (NEI); Plant profile: Beloyarsk NPP, Russia, by Nikolai Oshkanov, Beloyarsk NPP, Russia; Improving economic performance, by R. Spiegelberg-Planner, John De Mella, and Marius Condu, IAEA; A model for improving performance, by Pet Karns, MRO Software; ASME codes and standards, by Shannon Burke, ASME International; and, Refurbishment programs, by Craig S. Irish, Nuclear Logistics, Inc.

  8. Review of maintenance personnel practices at nuclear power plants

    SciTech Connect (OSTI)

    Chockie, A.D.; Badalamente, R.V.; Hostick, C.J.; Vickroy, S.C.; Bryant, J.L.; Imhoff, C.H.

    1984-05-01

    As part of the Nuclear Regulatory Commission (NRC) sponsored Maintenance Qualifications and Staffing Project, the Pacific Northwest Laboratory (PNL) has conducted a preliminary assessment of nuclear power plant (NPP) maintenance practices. As requested by the NRC, the following areas within the maintenance function were examined: personnel qualifications, maintenance training, overtime, shiftwork and staffing levels. The purpose of the assessment was to identify the primary safety-related problems that required further analysis before specific recommendations can be made on the regulations affecting NPP maintenance operations.

  9. Manuscript Title in Title Case

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

    Simulation of the NPP KRSKO Startup Core with CASL Core Simulator, VERA- CS Fausto Franceschini Westinghouse Electric Company LLC Marjan Kromar and Dušan Ćalić Jožef Stefan Institute Andrew T. Godfrey, Benjamin S. Collins, Thomas M. Evans, Jess C. Gehin Oak Ridge National Laboratory September 1, 2014 CASL-U-2014-0182-000 CASL-U-2014-0182-000 603.1 SIMULATION OF THE NPP KRSKO STARTUP CORE WITH CASL CORE SIMULATOR, VERA-CS Fausto Franceschini Westinghouse Electric Company LLC 1000 Westinghouse

  10. Activities for the remediation of TEPCO's Fukushima Daiichi nuclear power plant

    SciTech Connect (OSTI)

    Kinoshita, Hirofumi; Kometani, Yutaka; Asano, Takashi; Ishiwata, Masayuki; Fukasawa, Tetsuo; Tadokoro, Takahiro; Nagumo, Yasushi; Kani, Yuko; Matsui, Tetsuya

    2013-07-01

    With the aim of fulfilling recovery work for the Fukushima Daiichi NPP, technological efforts have been made for the development of a survey robot system, adequate communication infrastructure technologies, high radiation environment compatible gamma cameras, heavy machinery-type robots (ASTACO-SoRa), remote decontamination devices (AROUNDER), and contaminated waste water treatment system. We have developed a new type of absorbents which remove cesium (Cs) and strontium (Sr) simultaneously at a high removal rate of 99 % or more. We will provide valuable solutions and rational systems for waste water treatment using this developed adsorbent as well as other various adsorbents for the recovery of Fukushima Daiichi NPP.

  11. Regularization of Feedwater Flow Rate Evaluation for Venturi Meter Fouling Problem in Nuclear Power Plants

    SciTech Connect (OSTI)

    Gribok, Andrei V.; Attieh, Ibrahim K.; Hines, J. Wesley; Uhrig, Robert E.

    2001-04-15

    Inferential sensing is a method that can be used to evaluate parameters of a physical system based on a set of measurements related to these parameters. The most common method of inferential sensing uses mathematical models to infer a parameter value from correlated sensor values. However, since inferential sensing is an inverse problem, it can produce inconsistent results due to minor perturbations in the data. This research shows that regularization can be used in inferential sensing to produce consistent results. Data from Florida Power Corporation's Crystal River nuclear power plant (NPP) are used to give an important example of monitoring NPP feedwater flow rate.

  12. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

    SciTech Connect (OSTI)

    Heather D. Medema; Ronald K. Farris

    2012-09-01

    This report is a guidance document prepared for the benefit of commercial nuclear power plants (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making, planning, and preparation of a business case.

  13. Increasing summer net CO2 uptake in high northern ecosystems inferred from atmospheric inversions and comparisons to remote-sensing NDVI

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

    Welp, Lisa R.; Patra, Prabir K.; Rödenbeck, Christian; Nemani, Rama; Bi, Jian; Piper, Stephen C.; Keeling, Ralph F.

    2016-07-25

    Warmer temperatures and elevated atmospheric CO2 concentrations over the last several decades have been credited with increasing vegetation activity and photosynthetic uptake of CO2 from the atmosphere in the high northern latitude ecosystems: the boreal forest and arctic tundra. At the same time, soils in the region have been warming, permafrost is melting, fire frequency and severity are increasing, and some regions of the boreal forest are showing signs of stress due to drought or insect disturbance. The recent trends in net carbon balance of these ecosystems, across heterogeneous disturbance patterns, and the future implications of these changes are unclear.more » Here, we examine CO2 fluxes from northern boreal and tundra regions from 1985 to 2012, estimated from two atmospheric inversions (RIGC and Jena). Both used measured atmospheric CO2 concentrations and wind fields from interannually variable climate reanalysis. In the arctic zone, the latitude region above 60° N excluding Europe (10° W–63° E), neither inversion finds a significant long-term trend in annual CO2 balance. The boreal zone, the latitude region from approximately 50–60° N, again excluding Europe, showed a trend of 8–11 Tg C yr−2 over the common period of validity from 1986 to 2006, resulting in an annual CO2 sink in 2006 that was 170–230 Tg C yr−1 larger than in 1986. This trend appears to continue through 2012 in the Jena inversion as well. In both latitudinal zones, the seasonal amplitude of monthly CO2 fluxes increased due to increased uptake in summer, and in the arctic zone also due to increased fall CO2 release. These findings suggest that the boreal zone has been maintaining and likely increasing CO2 sink strength over this period, despite browning trends in some regions and changes in fire frequency and land use. Meanwhile, the arctic zone shows that increased summer CO2 uptake, consistent with strong greening trends, is offset by increased fall

  14. Search for: All records | SciTech Connect

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    ... Amini, Rashied (1) Beauchamp, Patricia M. (1) Bennett, Gary L. (1) Brophy, John R. (1) ... Beauchamp, Patricia M. ; Caltech, JPL ; Bennett, Gary L. ; Metaspace Enterprises ; ...

  15. Dynamic Defrosting via Spontaneous Dewetting on Nanostructured...

    Office of Scientific and Technical Information (OSTI)

    Authors: Boreyko, Jonathan B 1 ; Srijanto, Bernadeta R 1 ; Nguyen, Trung D 1 ; Vega, Carlos 2 ; Fuentes-Cabrera, Miguel A 1 ; Collier, Pat 1 + Show Author Affiliations ...

  16. Inelastic neutron scattering as a possible background for neutrinoless...

    Office of Scientific and Technical Information (OSTI)

    Authors: Boswell, Melissa S 1 ; Devlin, Matthew J. 1 ; Elliott, Steven R 1 ; Fotiadis, Nikolaos 1 ; Hime, Andrew 1 ; Nelson, Ronald O. 1 ; Guiseppe, Vincente E. 2 ; ...

  17. Summary of Investigations on Technical Feasibility of Direct...

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

    Summary of Investigations on Technical Feasibility of Direct Disposal of Dual-Purpose Canisters R1 Summary of Investigations on Technical Feasibility of Direct Disposal of ...

  18. ScGaN alloy growth by molecular beam epitaxy: Evidence for a...

    Office of Scientific and Technical Information (OSTI)

    Authors: Constantin, Costel ; Al-Brithen, Hamad ; Haider, Muhammad B. ; Ingram, David ; Smith, Arthur R. 1 + Show Author Affiliations Condensed Matter and Surface Science ...

  19. Metal/semiconductor phase transition in chromium nitride(001...

    Office of Scientific and Technical Information (OSTI)

    Authors: Constantin, Costel ; Haider, Muhammad B. ; Ingram, David ; Smith, Arthur R. 1 + Show Author Affiliations Condensed Matter and Surface Science Program, Department of ...

  20. Vibration cancellation in a Stirling-cooled HPGe detector (Conference...

    Office of Scientific and Technical Information (OSTI)

    Authors: Mascarenas, David L 1 ; Johnson, William R 1 ; Long, Rose G 1 ; Nelson, Mark W 1 + Show Author Affiliations Los Alamos National Laboratory Los Alamos National ...

  1. p-Type transparent conducting oxides and methods for preparation...

    Office of Scientific and Technical Information (OSTI)

    Inventors: Shahriari, Dean Y. 1 ; Barnabe, Antoine 2 ; Mason, Thomas O. 1 ; Poeppelmeier, Kenneth R. 1 + Show Author Affiliations (Evanston, IL) (Toulouse, FR) Issue Date: ...

  2. Field Mapping At Raft River Geothermal Area (1993) | Open Energy...

    Open Energy Info (EERE)

    extension over broad areas of the northern Basin and Range. References Dumitru, T.; Miller, E.; Savage, C.; Gans, P.; Brown, R. (1 April 1993) Fission track evidence for...

  3. Field Mapping At Northern Basin and Range Geothermal Region ...

    Open Energy Info (EERE)

    extension over broad areas of the northern Basin and Range. References Dumitru, T.; Miller, E.; Savage, C.; Gans, P.; Brown, R. (1 April 1993) Fission track evidence for...

  4. Search for: All records | SciTech Connect

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    (1) dipole moments (1) dynamics (1) energy (1) fermilab tevatron (1) luminescence ... Fleming, Graham R. (1) Graham, Matt (1) Graham, Matt W. (1) Green, Johnny (1) Hupalo, ...

  5. Transforming growth factor-{beta}1 regulates fibronectin isoform...

    Office of Scientific and Technical Information (OSTI)

    Authors: Han Fei 1 ; Gilbert, James R. 1 ; Harrison, Gerald 1 ; Adams, Christopher S. 1 ; Freeman, Theresa 1 ; Tao Zhuliang 1 ; Zaka, Raihana 2 ; Liang Hongyan 3 ; ...

  6. Search for: All records | SciTech Connect

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    Sun, Shenfang (1) Waterman, Michael R. (1) Yoshimoto, Francis K. (1) Save Results Save ... Pradeep S. ; Wang, Chunxue ; Lei, Li ; Yoshimoto, Francis K. ; Auchus, Richard J. ; ...

  7. Search for: All records | SciTech Connect

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    ... Bailey, Stephen (1) Banerji, Manda (1) Barkhouse, Wayne A. (1) Beers, Timothy C. (1) Berlind, Perry (1) Bernstein, Gary (1) Bernstein, Rebecca (1) Blanton, Michael R. (1) Bridle, ...

  8. Document Library | Department of Energy

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

    Cask Handling R1 This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for...

  9. Gas mixture for diffuse-discharge switch (Patent) | DOEPatents

    Office of Scientific and Technical Information (OSTI)

    Inventors: Christophorou, Loucas G. 1 ; Carter, James G. 2 ; Hunter, Scott R. 1 + Show Author Affiliations (Oak Ridge, TN) (Knoxville, TN) Issue Date: 1984-01-01 OSTI ...

  10. Cuttings Analysis At Imperial Valley Geothermal Area (1976) ...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  11. Cuttings Analysis At Marysville Mountain Geothermal Area (1976...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  12. Cuttings Analysis At Jemez Mountain Geothermal Area (1976) |...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  13. Cuttings Analysis At Geysers Geothermal Area (1976) | Open Energy...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  14. Cuttings Analysis At Roosevelt Hot Springs Geothermal Area (1976...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  15. Cuttings Analysis At Bacca Ranch Geothermal Area (1976) | Open...

    Open Energy Info (EERE)

    and overlying cap rock. References Pratt, H. R.; Simonson, E. R. (1 January 1976) Geotechnical studies of geothermal reservoirs Additional References Retrieved from "http:...

  16. Shear Rolling of Magnesium Sheet for Automotive, Defense, and...

    Office of Scientific and Technical Information (OSTI)

    Title: Shear Rolling of Magnesium Sheet for Automotive, Defense, and Energy Applications Authors: Muralidharan, Govindarajan 1 ; Muth, Thomas R 1 ; Peter, William H 1 ; ...

  17. High Resolution Lithium Mapping Using Fe State of Charge in Energy...

    Office of Scientific and Technical Information (OSTI)

    Fenton, Kyle R 1 ; Kotula, Paul G. 1 ; Sullivan, John P. ; Bartelt, Norman C. ; Chueh, William ; Tyliszczak, Tolek + Show Author Affiliations (Sandia National Laboratories, ...

  18. High Resolution Lithium Mapping Using Fe State of Charge in Energy...

    Office of Scientific and Technical Information (OSTI)

    Bartelt, Norman C. ; Kotula, Paul G. 1 ; Fenton, Kyle R 1 ; Sullivan, John P. ; Chueh, William + Show Author Affiliations (Sandia National Laboratories, Albuquerque, NM) ...

  19. Vectorial mapping of noncollinear antiferromagnetic structure...

    Office of Scientific and Technical Information (OSTI)

    Authors: Zhang, K. F. ; Yang, Fang ; Song, Y. R. 1 ; Zhang, Xiaole 2 ; The State Key Laboratory of Advanced Optical Communication Systems and Networks, Department of Physics ...

  20. Infrared microcalorimetric spectroscopy using quantum cascade...

    Office of Scientific and Technical Information (OSTI)

    Authors: Morales Rodriguez, Marissa E 1 ; Senesac, Larry R 1 ; Rajic, Slobodan 1 ; Lavrik, Nickolay V 1 ; Smith, Barton 1 ; Datskos, Panos G 1 + Show Author ...

  1. Thermographic In-Situ Process Monitoring of the Electron Beam...

    Office of Scientific and Technical Information (OSTI)

    Authors: Dinwiddie, Ralph Barton 1 ; Dehoff, Ryan R 1 ; Lloyd, Peter D 1 ; Lowe, Larry E 1 ; Ulrich, Joseph B 1 + Show Author Affiliations ORNL ORNL Publication Date: ...

  2. Search for: All records | DOE PAGES

    Office of Scientific and Technical Information (OSTI)

    Fast, Jerome D. (1) Fletcher, Jennifer (1) George, R. (1) Ghate, Virendra (1) Gustafson, ... ; Clarke, A. D. ; Fast, Jerome D. ; George, R. ; Gustafson, William I. ; Hannay, ...

  3. Thinking Small: Plutonium Separations and Processing at the Microscale...

    Office of Scientific and Technical Information (OSTI)

    Donivan R. 1 ; Manard, Benjamin Thomas 1 ; Martinez, Patrick Thomas 1 ; Montoya, Dennis Patrick 1 ; Gardner, Kyle Shelton 1 ; Boland, Kevin Sean 1 ; Goff, George Scott ...

  4. Microsoft Word - DRAFT RFP Language V1_2.docx

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

    Energy FINAL1.DOC Microsoft Word - DP_cover_and_front matter_FINAL1.DOC Microsoft Word - DP_cover_and_front matter_FINAL1.DOC (43.57 MB) More Documents & Publications Microsoft Word - DP_cover_and_front matter_R1_Draft_3.DOC CX-013777: Categorical Exclusion Determination EA-1552: Final Environmental Assessment Energy

    R1_Draft_3.DOC Microsoft Word - DP_cover_and_front matter_R1_Draft_3.DOC Microsoft Word - DP_cover_and_front matter_R1_Draft_3.DOC (11.21 MB) More Documents &

  5. Application of In-situ Electrochemical Liquid Cells for Electrical...

    Office of Scientific and Technical Information (OSTI)

    Title: Application of In-situ Electrochemical Liquid Cells for Electrical Energy Storage Research Authors: Unocic, Raymond R 1 ; Sun, Xiao-Guang 1 ; Dudney, Nancy J 1 ; ...

  6. Single line-of-sight dual energy backlighter for mix width experiments...

    Office of Scientific and Technical Information (OSTI)

    S. A. ; Felker, S. ; Seugling, R. ; Doane, D. ; Wallace, R. 1 ; Guymer, T. M. ; Moore, A. S. 2 ; Whiting, N. ; Sorce, C. 3 + Show Author Affiliations Lawrence Livermore ...

  7. Laser parametric instability experiments of a 3ω, 15 kJ, 6-ns...

    Office of Scientific and Technical Information (OSTI)

    Authors: Rousseaux, C. ; Huser, G. ; Loiseau, P. ; Casanova, M. ; Alozy, E. ; Villette, B. ; Wrobel, R. 1 ; Henry, O. ; Raffestin, D. 2 + Show Author Affiliations Commissariat ...

  8. The Use of Additive Manufacturing for Fabrication of Multi-Function...

    Office of Scientific and Technical Information (OSTI)

    Authors: Horais, Brian J 1 ; Love, Lonnie J 1 ; Dehoff, Ryan R 1 + Show Author ... Research Org: Oak Ridge National Laboratory (ORNL) Sponsoring Org: USDOE Country of ...

  9. Microsoft PowerPoint - Tribal_Johnson

    Office of Environmental Management (EM)

    20140228businessenergy-environmentbakkan-crude-rolling-through-albany.html?r1. 8 Prairie Island Indian Community 5162014 5 12 Mile Isolation & Evacuation...

  10. Nonlinear Laser-Plasma Interaction in Magnetized Liner Inertial...

    Office of Scientific and Technical Information (OSTI)

    ; Bliss, David E. 1 ; Campbell, Edward Michael 2 ; Gomez, Matthew R. 1 ; Harding, ... Christopher 1 ; Vesey, Roger A. 1 ; Porter, John L. 1 less + Show Author ...

  11. Energy Balance Bowen Ratio (EBBR) Handbook (Technical Report...

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    A unique aspect of the system is the automatic exchange mechanism (AEM), which helps to reduce errors from instrument offset drift. Authors: Cook, D. R. 1 + Show Author ...

  12. Search for: All records | DOE PAGES

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    Jupp, Andrew R. (1) Lefvre, Julia (1) Maron, Laurent (1) Settineri, Nicholas (1) Save Results Excel (limit 2000) CSV (limit 5000) XML (limit 5000) Have feedback or suggestions ...

  13. Micro-Earthquake At Coso Geothermal Area (2007) | Open Energy...

    Open Energy Info (EERE)

    area Julian, B.R.; Foulger, G.R. (1 January 2010) IMPROVED METHODS FOR MAPPING PERMEABILITY AND HEAT SOURCES IN GEOTHERMAL AREAS USING MICROEARTHQUAKE DATA Additional...

  14. Ultrashort pulse laser-triggering of long gap high voltage switches...

    Office of Scientific and Technical Information (OSTI)

    Dale Robert 1 ; Rose, David V. 1 ; Thoma, Carsten 1 ; Clark, Robert E. 1 ; Miller, Craig 1 ; Zimmerman, William R. 1 ; Pitts, Todd Alan ; Laine, Mark R. ; ...

  15. Need for High-Purity Uranium-233 (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Abstract is at the beginning of the paper. Authors: Krichinsky, Alan M 1 ; Canaan, R Douglas 2 ; Giaquinto, Joseph 1 ; Hexel, Cole R 1 + Show Author Affiliations ORNL ...

  16. Real-time condition assessment of RAPTOR telescope systems (Journal...

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    Authors: Stull, Christopher J 1 ; Taylor, Stuart G 1 ; Wren, James 1 ; Mascarenas, David L 1 ; Farrar, Charles R 1 + Show Author Affiliations Los Alamos National ...

  17. Real-time condition assessment of RAPTOR telescope systems (Conference...

    Office of Scientific and Technical Information (OSTI)

    Authors: Stull, Christopher J 1 ; Taylor, Stuart G 1 ; Wren, James 1 ; Mascarenas, David L 1 ; Farrar, Charles R 1 + Show Author Affiliations Los Alamos National ...

  18. Platforms and Methods for In Situ Characterization of Li-ion...

    Office of Scientific and Technical Information (OSTI)

    Electron Transmission X-ray Microscopies. Abstract not provided. Authors: Sullivan, John P ; Bartelt, Norman C. ; El Gabaly Marquez, Farid ; Fenton, Kyle R 1 ;...

  19. Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4

    SciTech Connect (OSTI)

    Su Weinian; Wang, S.-J.; Chiang, S.-C

    2005-06-15

    Containment flooding is an important strategy for severe accident management of a conventional boiling water reactor (BWR) system. The purpose of this work is to investigate the containment flooding strategy of the Mark-III system after a reactor pressure vessel (RPV) breach. The Kuosheng Power Plant is a typical BWR-6 nuclear power plant (NPP) with Mark-III containment. The Severe Accident Management Guideline (SAMG) of the Kuosheng NPP has been developed based on the BWR Owners Group (BWROG) Emergency Procedure and Severe Accident Guidelines, Rev. 2. Therefore, the Kuosheng NPP is selected as the plant for study, and the MAAP4 code is chosen as the tool for analysis. A postulated specific station blackout sequence for the Kuosheng NPP is cited as a reference case for this analysis. Because of the design features of Mark-III containment, the debris in the reactor cavity may not be submerged after an RPV breach when one follows the containment flooding strategy as suggested in the BWROG generic guideline, and the containment integrity could be challenged eventually. A more specific containment flooding strategy with drywell venting after an RPV breach is investigated, and a more stable plant condition is achieved with this strategy. Accordingly, the containment flooding strategy after an RPV breach will be modified for the Kuosheng SAMG, and these results are applicable to typical Mark-III plants with drywell vent path.

  20. US graphite reactor D&D experience

    SciTech Connect (OSTI)

    Garrett, S.M.K.; Williams, N.C.

    1997-02-01

    This report describes the results of the U.S. Graphite Reactor Experience Task for the Decommissioning Strategy Plan for the Leningrad Nuclear Power Plant (NPP) Unit 1 Study. The work described in this report was performed by the Pacific Northwest National Laboratory (PNNL) for the Department of Energy (DOE).

  1. RELAP5/MOD3.2 Investigation of a VVER-1000 MCP Switching on Problem

    SciTech Connect (OSTI)

    Groudev, Pavlin; Pavlova, Malinka

    2002-07-01

    This paper provides a discussion of various RELAP5 parameters calculated for the investigation of the nuclear power reactor parameter behavior in case of switching on one main coolant pump (MCP) when the other three MCPs are in operation. The reference power plant for this analysis is Unit 6 at the Kozloduy Nuclear Power Plant (NPP) site. Operational data from Kozloduy NPP have been used for the purpose of assessing how the RELAP5 model compares against plant data. During the plant-commissioning phase at Kozloduy NPP Unit 6 a number of experiments have been performed. One of them is switching on MCP when the other three MCPs are in operation. The event is characterized by rapid increase in the flow through the core resulting in a coolant temperature decrease, which leads to insertion of positive reactivity due to the modeled feedback mechanisms. This investigation has been conducted by Bulgarian and Russian specialists on the stage when the reactor power was at 75% of the nominal level. The purpose of the experiment was the complete testing of reliability of all power plant equipment, testing the reliability of the main regulators and defining a jump of the neutron reactor power in case of switching on of one main coolant pump. The Institute for Nuclear Research and Nuclear Energy - Bulgarian Academy of Sciences (INRNE-BAS), Sofia, and Kozloduy NPP have been developing a RELAP5/MOD3.2 model for Kozloduy NPP VVER-1000 for investigation of operational occurrences, abnormal events, and design basis scenarios. This investigation is a process that compares the analytical results obtained by the RELAP5 computer model of the VVER-1000 against the experimental transient data received from the Kozloduy NPP Unit 6. The comparisons between the RELAP5 results and the test data indicate good agreement. This report was possible through the participation of leading specialists from Kozloduy NPP and with the support of Argonne National Laboratory, under the International Nuclear

  2. Global and Regional Ecosystem Modeling: Databases of Model Drivers and Validation Measurements

    SciTech Connect (OSTI)

    Olson, R.J.

    2002-03-19

    Understanding global-scale ecosystem responses to changing environmental conditions is important both as a scientific question and as the basis for making policy decisions. The confidence in regional models depends on how well the field data used to develop the model represent the region of interest, how well the environmental model driving variables (e.g., vegetation type, climate, and soils associated with a site used to parameterize ecosystem models) represent the region of interest, and how well regional model predictions agree with observed data for the region. To assess the accuracy of global model forecasts of terrestrial carbon cycling, two Ecosystem Model-Data Intercomparison (EMDI) workshops were held (December 1999 and April 2001). The workshops included 17 biogeochemical, satellite-driven, detailed process, and dynamic vegetation global model types. The approach was to run regional or global versions of the models for sites with net primary productivity (NPP) measurements (i.e., not fine-tuned for specific site conditions) and analyze the model-data differences. Extensive worldwide NPP data were assembled with model driver data, including vegetation, climate, and soils data, to perform the intercomparison. This report describes the compilation of NPP estimates for 2,523 sites and 5,164 0.5{sup o}-grid cells under the Global Primary Production Data Initiative (GPPDI) and the results of the EMDI review and outlier analysis that produced a refined set of NPP estimates and model driver data. The EMDI process resulted in 81 Class A sites, 933 Class B sites, and 3,855 Class C cells derived from the original synthesis of NPP measurements and associated driver data. Class A sites represent well-documented study sites that have complete aboveground and below ground NPP measurements. Class B sites represent more numerous ''extensive'' sites with less documentation and site-specific information available. Class C cells represent estimates of NPP for 0.5{sup o

  3. Divergent predictions of carbon storage between two global land models: attribution of the causes through traceability analysis

    SciTech Connect (OSTI)

    Rafique, Rashid; Xia, Jianyang; Hararuk, Oleksandra; Asrar, Ghassem R.; Wang, Yingping; Luo, Yiqi

    2015-08-27

    Representations of the terrestrial carbon cycle in land models are becoming increasingly complex. It is crucial to develop approaches for critical assessment of the complex model properties in order to understand key factors contributing to models’ performance. In this study, we applied a traceability analysis, which decomposes carbon cycle models into traceable components, to two global land models (CABLE and CLM-CASA’) to diagnose the causes of their differences in simulating ecosystem carbon storage capacity. Driven with similar forcing data, the CLM-CASA’ model predicted ~31% larger carbon storage capacity than the CABLE model. Since ecosystem carbon storage capacity is a product of net primary productivity (NPP) and ecosystem residence time (τE), the predicted difference in the storage capacity between the two models results from differences in either NPP or τE or both. Our analysis showed that CLM-CASA’ simulated 37% higher NPP than CABLE due to higher rates of carboxylation (Vcmax) in CLM-CASA’. On the other hand, τE , which was a function the baseline carbon residence time (τ´E) and environmental effect on carbon residence time, was on average 11 years longer in CABLE than CLM-CASA’. The difference in τE was mainly found to be caused by longer τ´E in CABLE than CLM-CASA’. This difference in τE was mainly caused by longer τ´E of woody biomass (23 vs. 14 years in CLM-CASA’) and higher proportion of NPP allocated to woody biomass (23% vs. 16%). Differences in environmental effects on carbon residence times had smaller influences on differences in ecosystem carbon storage capacities compared to differences in NPP and τ´E. Overall; the traceability analysis is an effective method for identifying sources of variations between the two models.

  4. Atmospheric carbonyl sulfide exchange in bog microcosms

    SciTech Connect (OSTI)

    Fried, A.; Klinger, L.F.; Erickson, D.J. III (National Center for Atmospheric Research, Boulder, CO (United States))

    1993-01-22

    Measurements of Carbonyl sulfide (OCS) fluxes were carried out on bog microcosms using chamber sampling and tunable diode laser analysis. Intact bog microcosms (vascular plants, mosses, and peat) removed ambient levels of OCS in the light and dark with rates from [minus]2.4 to [minus]8.1 ng S min[sup [minus]1] m[sup [minus]2]. Peat and peat plus mosses emitted OCS in the light with rates of 17.4 and 10.9 ng S min[sup [minus]1] m[sup [minus]2], respectively. In the dark, the mosses apparently removed OCS at a rate equivalent to the peat emissions. A 3-D numerical tracer model using this data indicated that boreal bog ecosystems remove at most 1% of ambient OCS, not sufficient to account for an observed OCS depletion in boreal air masses. 13 refs., 1 fig., 1 tab.

  5. Scientific Objective

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

    Biogenic Aerosols - Effects on Clouds and Climate Scientific Objective Aerosols in the sky are essential to Earth's climate because they can reflect light into space, cooling the atmosphere, or they can combine with other particles to create clouds that have both warming and cooling effects. Biogenic aerosols are emitted by the biosphere directly, or are formed from biogenic volatile gases in gas-to-particle conversion. Examples include dead cells and pollen spores. Boreal forests are among the

  6. Research Highlight

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

    The Organic Molecules Explaining New Particle Growth in the Boreal Forest Download a printable PDF Submitter: Thornton, J., University of Washington Area of Research: Aerosol Processes Working Group(s): Aerosol Life Cycle Journal Reference: Ehn M, JA Thornton, E Kleist, M Sipila, H Junninen, I Pullinen, M Springer, F Rubach, R Tillmann, B Lee, F Lopez-Hilfiker, S Andres, I Acir, M Rissanen, T Jokinen, S Schobesberger, J Kangasluoma, J Kontkanen, T Nieminen, T Kurten, LB Nielsen, S Jorgensen, HG

  7. AmeriFlux CA-Man Manitoba - Northern Old Black Spruce (former BOREAS Northern Study Area)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Amiro, Brian [University of Manitoba

    2016-01-01

    This is the AmeriFlux version of the carbon flux data for the site CA-Man Manitoba - Northern Old Black Spruce (former BOREAS Northern Study Area). Site Description - 55.880° N, 98.481° W, elevation of 259 m, Boreal coniferous: Black spruce; occasional larch present in poorly-drained areas. Groundcover is moss (feathermosses and Sphagnum), Labrador Tea, Vaccinium, and willows are a main component of the understory. It was established in 1993 as a BOREAS site.

  8. barr(2)-98.pdf

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

    Frequency Interactions to Explain Madden Julian Oscillations and Intra Seasonal Oscillations S. A. Barr-Kumarakulasinghe Brookhaven National Laboratory Upton, New York Deep convective activity as seen by outgoing longwave radiation (OLR) (< 180 wm -2 ) is shown to occur at 20 to 60 periods in a more coherent manner during the boreal winters of El-Nino Southern Oscillation (ENSO) warm events. The coherent pattern is seen in the spectra of the TWP equatorial region closer to the date line. The

  9. frisch(1)-99.PDF

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

    Effect of Cumulus Cloud Formation on Boundary Layer Turbulence A. S. Frisch, B. E. Martner, and B. W. Orr National Oceanic and Atmospheric Administration Environmental Technology Laboratory Boulder, Colorado D. H. Lenschow National Center for Atmospheric Research Boulder, Colorado Introduction The National Oceanic and Atmospheric Administration's (NOAA's) 35-GHz Doppler radar measured the turbulent motions in the planetary boundary layer (PBL) over the boreal forest as a contribution to the

  10. ARM - Publications: Science Team Meeting Documents

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

    Simulation of the Intercontinental Transport, Aging, and Removal of a Boreal Fire Smoke Plume Over Oklahoma Ghan, S.(a), Chapman, E.(a), Easter, R.(a), Reid, J.(b), and Justice, C.(c), Pacific Northwest National Laboratory (a), Naval Research Laboratory (b), University of Maryland (c) Isentropic back trajectories suggest that an elevated aerosol plume observed over Oklahoma during the May 2003 ARM Aerosol IOP originated from intense fires in Siberia. To test this hypothesis the plume was

  11. UNCLASSIFIED

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

    Brian Aukema University of Minnesota Tamarack in Trouble? Climate change and altered population dynamics of eastern larch beetle in North America Wednesday, July 13, 2016 11:00 AM TA-51 Conference Room (TA-51, Building 25, Room 102) Abstract. Eastern larch or tamarack Larix laricina is an important lowland conifer of northern boreal and peat ecosystems found from Alaska to the Canadian maritimes. Its primary bark beetle, the eastern larch beetle Dendroctonus simplex, has been documented by

  12. DOE Science Showcase - Carbon Capture research in DOE Databases | OSTI,

    Office of Scientific and Technical Information (OSTI)

    US Dept of Energy Office of Scientific and Technical Information DOE Science Showcase - Carbon Capture research in DOE Databases Information Bridge : Natural materials for carbon capture. ... Realistic costs of carbon capture ... Technology and international climate policy Energy Citations Database : What Can China Do? China's Best Alternative Outcome for Energy Efficiency and CO2 Emissions ... Effects of warming on the structure and function of a boreal black spruce forest ... ScienceCinema

  13. DOE Science Showcase - Earth System Models | OSTI, US Dept of Energy Office

    Office of Scientific and Technical Information (OSTI)

    of Scientific and Technical Information Earth System Models U.S. DOE Office of Science: Getting Forest Carbon Right in Climate Models. "Boreal Forest" Image Credit: Wikimedia Commons, peupleloup. Optimizing emerging high-performance computing and information technologies, the Department of Energy's (DOE) Earth System Modeling (ESM) Program concentrates on advancing coupled climate and earth system models for climate change projections at global-to-regional spatial scales and

  14. January 2013 Most Viewed Documents for Biology And Medicine | OSTI, US Dept

    Office of Scientific and Technical Information (OSTI)

    of Energy Office of Scientific and Technical Information January 2013 Most Viewed Documents for Biology And Medicine Nevada Test Site Radiological Control Manual Radiological Control Managers' Council Nevada Test Site Effects of ionizing radiation on the boreal forest: Canada's FIG experiment, with implications for radionuclides Amiro, B.D.; Sheppard, S.C Assessment of atmospheric metallic pollution in the metropolitan region of Sao Paulo, Brazil, employing Tillandsia usneoides L. as

  15. Is the northern high latitude land-based CO2 sink weakening?

    SciTech Connect (OSTI)

    Mcguire, David; Kicklighter, David W.; Gurney, Kevin R; Burnside, Todd; Melillo, Jerry

    2011-01-01

    Studies indicate that, historically, terrestrial ecosystems of the northern high latitude region may have been responsible for up to 60% of the global net land-based sink for atmospheric CO2. However, these regions have recently experienced remarkable modification of the major driving forces of the carbon cycle, including surface air temperature warming that is significantly greater than the global average and associated increases in the frequency and severity of disturbances. Whether arctic tundra and boreal forest ecosystems will continue to sequester atmospheric CO2 in the face of these dramatic changes is unknown. Here we show the results of model simulations that estimate a 41 Tg C yr-1 sink in the boreal land regions from 1997 to 2006, which represents a 73% reduction in the strength of the sink estimated for previous decades in the late 20th Century. Our results suggest that CO2 uptake by the region in previous decades may not be as strong as previously estimated. The recent decline in sink strength is the combined result of 1) weakening sinks due to warming-induced increases in soil organic matter decomposition and 2) strengthening sources from pyrogenic CO2 emissions as a result of the substantial area of boreal forest burned in wildfires across the region in recent years. Such changes create positive feedbacks to the climate system that accelerate global warming, putting further pressure on emission reductions to achieve atmospheric stabilization targets.

  16. Word Pro - S1

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

    ... ...... 1,335 1,260 1,334 R 1,266 645 R 835 R 624 R 817 469 890 February ...... 1,415 R 1,321 1,404 1,306 R 667 865 R 500 R 600 R 331 867 March ......

  17. Slide 1

    Office of Environmental Management (EM)

    M a r - 1 0 A p r - 1 0 M a y - 1 0 J u n - 1 0 J u l - 1 0 A u g - 1 0 S e p - 1 0 O c t-1 0 N o v - 1 0 D e c - 1 0 Month Oxygen Levels (%) GB-1 GB-500 GB-1000 GB-1500 GB-2000 ...

  18. Light Water Reactor Sustainability Program FY13 Status Update for EPRI - RISMC Collaboration

    SciTech Connect (OSTI)

    Curtis Smith

    2013-09-01

    The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced "RISMC toolkit" that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory (INL) is collaborating with the Electric Power Research Institute (EPRI) in order to focus on applications of interest to the U.S. nuclear power industry. This report documents the collaboration activities performed between INL and EPRI during FY2013.

  19. TOOKUIL: A case study in user interface development for safety code application

    SciTech Connect (OSTI)

    Gray, D.L.; Harkins, C.K.; Hoole, J.G.

    1997-07-01

    Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today`s safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL.

  20. Research subjects for analytical estimation of core degradation at Fukushima-Daiichi nuclear power plant

    SciTech Connect (OSTI)

    Nagase, F.; Ishikawa, J.; Kurata, M.; Yoshida, H.; Kaji, Y.; Shibamoto, Y.; Amaya, M; Okumura, K.; Katsuyama, J.

    2013-07-01

    Estimation of the accident progress and status inside the pressure vessels (RPV) and primary containment vessels (PCV) is required for appropriate conductance of decommissioning in the Fukushima-Daiichi NPP. For that, it is necessary to obtain additional experimental data and revised models for the estimation using computer codes with increased accuracies. The Japan Atomic Energy Agency (JAEA) has selected phenomena to be reviewed and developed, considering previously obtained information, conditions specific to the Fukushima-Daiichi NPP accident, and recent progress of experimental and analytical technologies. As a result, research and development items have been picked up in terms of thermal-hydraulic behavior in the RPV and PCV, progression of fuel bundle degradation, failure of the lower head of RPV, and analysis of the accident. This paper introduces the selected phenomena to be reviewed and developed, research plans and recent results from the JAEA's corresponding research programs. (authors)

  1. Nondestructive Testing Qualification of Main Circulatory Tube Pipes DU 500

    SciTech Connect (OSTI)

    Tabakova, Bojana M.; Tzokov, Petio

    2004-07-01

    The criteria for safe operation of nuclear energetic installations is given a higher priority in the policy of Kozloduy Nuclear Power Plant. An efficient non-destructive inspection is the key point for the safe service. Kozloduy NPP keeps on making investments in equipment and qualification of specialists in this field. The processes of qualification of the NDT components, important for the nuclear and radiation safety, make considerable improvement in Kozloduy NPP, thanks to the accumulated in the years experience in the activities of NDT inspection qualification, and to the help of our partners Serco Assurance and the Institute of Rzes. The results obtained by ultrasonic non-destructive inspection of circulation tube mains DU 500 WWER 440 type are under discussion in this report. (authors)

  2. Improving Outage Performance: Outage Optimization Process

    SciTech Connect (OSTI)

    LaPlatney, Jere J.

    2006-07-01

    Planned outage performance is a key measure of how well an Nuclear Power Plant (NPP) is operated. Performance during planned outages strongly affects virtually all of a plant's performance metrics. In recognition of this fact, NPP operators worldwide have and continue to focus on improving their outage performance. The process of improving outage performance is commonly referred to as 'Outage Optimization' in the industry. This paper starts with a summary of the principles of Outage Optimization. It then provides an overview of a process in common use in the USA and elsewhere to manage the improvement of planned outages. The program described is comprehensive in that it involves managing improvement in both the Preparation and Execution phases of outage management. (author)

  3. Fatigue flaw growth assessment and inclusion of stratification to the LBB assessment

    SciTech Connect (OSTI)

    Samohyl, P.

    1997-04-01

    The application of the LBB requires also fatigue flaw growth assessment. This analysis was performed for PWR nuclear power plants types VVER 440/230, VVER 440/213c, VVER 1000/320. Respecting that these NPP`s were designed according to Russian codes that differ from US codes it was needed to compare these approaches. Comparison with our experimental data was accomplished, too. Margins of applicability of the US methods and their modifications for the materials used for construction of Czech and Slovak NPP`s are shown. Computer code accomplishing the analysis according to described method is presented. Some measurement and calculations show that thermal stratifications in horizontal pipelines can lead to additive loads that are not negligible and can be dangerous. An attempt to include these loads induced by steady-state stratification was made.

  4. Maintenance personnel performance simulation (MAPPS) model: overview and evaluation efforts

    SciTech Connect (OSTI)

    Knee, H.E.; Haas, P.M.; Siegel, A.I.; Bartter, W.D.; Wolf, J.J.; Ryan, T.G.

    1984-01-01

    The development of the MAPPS model has been completed and the model is currently undergoing evaluation. These efforts are addressing a number of identified issues concerning practicality, acceptability, usefulness, and validity. Preliminary analysis of the evaluation data that has been collected indicates that MAPPS will provide comprehensive and reliable data for PRA purposes and for a number of other applications. The MAPPS computer simulation model provides the user with a sophisticated tool for gaining insights into tasks performed by NPP maintenance personnel. Its wide variety of input parameters and output data makes it extremely flexible for application to a number of diverse applications. With the demonstration of favorable model evaluation results, the MAPPS model will represent a valuable source of NPP maintainer reliability data and provide PRA studies with a source of data on maintainers that has previously not existed.

  5. Export Control Guide: Loose Parts Monitoring Systems for Nuclear Power Plants

    SciTech Connect (OSTI)

    Langenberg, Donald W.

    2012-12-01

    This report describes a typical LPMS, emphasizing its application to the RCS of a modern NPP. The report also examines the versatility of AE monitoring technology by describing several nuclear applications other than loose parts monitoring, as well as some non-nuclear applications. In addition, LPMS implementation requirements are outlined, and LPMS suppliers are identified. Finally, U.S. export controls applicable to LPMSs are discussed.

  6. Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes

    SciTech Connect (OSTI)

    Wang, T.-C.; Wang, S.-J.; Teng, J.-T

    2005-05-15

    This paper demonstrates a large-break loss-of-coolant accident (LOCA) sequence of the Kuosheng nuclear power plant (NPP) and station blackout sequence of the Maanshan NPP with the SCDAP/RELAP5 (SR5), Modular Accident Analysis Program (MAAP), and MELCOR codes. The large-break sequence initiated with double-ended rupture of a recirculation loop. The main steam isolation valves (MSIVs) closed, the feedwater pump tripped, the reactor scrammed, and the assumed high-pressure and low-pressure spray systems of the emergency core cooling system (ECCS) were not functional. Therefore, all coolant systems to quench the core were lost. MAAP predicts a longer vessel failure time, and MELCOR predicts a shorter vessel failure time for the large-break LOCA sequence. The station blackout sequence initiated with a loss of all alternating-current (ac) power. The MSIVs closed, the feedwater pump tripped, and the reactor scrammed. The motor-driven auxiliary feedwater system and the high-pressure and low-pressure injection systems of the ECCS were lost because of the loss of all ac power. It was also assumed that the turbine-driven auxiliary feedwater pump was not functional. Therefore, the coolant system to quench the core was also lost. MAAP predicts a longer time of steam generator dryout, time interval between top of active fuel and bottom of active fuel, and vessel failure time than those of the SR5 and MELCOR predictions for the station blackout sequence. The three codes give similar results for important phenomena during the accidents, including SG dryout, core uncovery, cladding oxidation, cladding failure, molten pool formulation, debris relocation to the lower plenum, and vessel head failure. This paper successfully demonstrates the large-break LOCA sequence of the Kuosheng NPP and the station blackout sequence of the Maanshan NPP.

  7. Microsoft Word - DOE-ID-14-049 Iowa State University EC B3-6.doc

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

    49 SECTION A. Project Title: Advanced Models for Nondestructive Evaluation of Aging Nuclear Power Plant Cables - Iowa State University SECTION B. Project Description Iowa State University will perform R&D related to modeling the aging of two major NPP cable polymers - ethylene propylene rubber (EPR) and cross-linked polyethylene (XLPE). The cable polymers will be aged under various conditions e.g. elevated temperature, neutron/gamma irradiation, and water immersion. The testing using

  8. Slide 1

    Office of Environmental Management (EM)

    Issues DOE's Nuclear Energy Programs Dr. Peter Lyons Assistant Secretary for Nuclear Energy U.S. Department of Energy Nuclear Energy Advisory Committee December 10, 2014 2 Overview  FY15 President's Budget Request  Assessment of Disposal Options for DOE HLW and SNF  NEUP/NEET R&D and Infrastructure Awards  Hybrid Energy Systems  Continued Evaluation of NPP Economics  Startup of Nuclear Cyber Security Activities  Idaho National Lab-led Innovation Workshops in March 2015

  9. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM ADVANCED INSTRUMENTATION, INFORMATION, AND CONTROL SYSTEMS TECHNOLOGIES TECHNICAL PROGRAM PLAN FOR 2013

    SciTech Connect (OSTI)

    Hallbert, Bruce; Thomas, Ken

    2014-07-01

    Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

  10. Light Water Reactor Sustainability Program Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for 2013

    SciTech Connect (OSTI)

    Hallbert, Bruce; Thomas, Ken

    2014-09-01

    Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

  11. LWR Sustainability: Assessment of Aging of Nuclear Power Plant Safety Related Concrete Strutures

    SciTech Connect (OSTI)

    Graves III, Herman; Naus, Dan J

    2013-01-01

    Current regulatory testing and inspection requirements are reviewed and a summary of degradation experience is presented. Techniques commonly used to inspect NPP concrete structures to assess and quantify age-related degradation are summarized. An approach for conduct of condition assessments of structures in NPPs is presented. Criteria, based primarily on visual indications, are provided for use in classification and assessment of concrete degradation. Materials and techniques for repair of degraded structures are generally discussed.

  12. Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan

    SciTech Connect (OSTI)

    Bruce Hallbert

    2012-09-01

    Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

  13. A reactor core on-line monitoring program - COMP

    SciTech Connect (OSTI)

    Wang, C.; Wu, H.; Cao, L.

    2012-07-01

    A program named COMP is developed for on-line monitoring PWRs' in-core power distribution in this paper. Harmonics expansion method is used in COMP. The Unit 1 reactor of Daya Bay Nuclear Power Plant (Daya Bay NPP) in China is considered for verification. The numerical results show that the maximum relative error between measurement and reconstruction results from COMP is less than 5%, and the computing time is short, indicating that COMP is capable for online monitoring PWRs. (authors)

  14. Maintenance personnel performance simulation (MAPPS): a model for predicting maintenance performance reliability in nuclear power plants

    SciTech Connect (OSTI)

    Knee, H.E.; Krois, P.A.; Haas, P.M.; Siegel, A.I.; Ryan, T.G.

    1983-01-01

    The NRC has developed a structured, quantitative, predictive methodology in the form of a computerized simulation model for assessing maintainer task performance. Objective of the overall program is to develop, validate, and disseminate a practical, useful, and acceptable methodology for the quantitative assessment of NPP maintenance personnel reliability. The program was organized into four phases: (1) scoping study, (2) model development, (3) model evaluation, and (4) model dissemination. The program is currently nearing completion of Phase 2 - Model Development.

  15. Public opinion and nuclear energy

    SciTech Connect (OSTI)

    Nealey, S.M.; Melber, B.D.; Rankin, W.L.

    1983-01-01

    Public acceptance of a nuclear power plant (NPP) built near one's residence has declined steadily since the early 1970's. Following the TMI accident, this acceptance decreased dramatically. There has been some attitude rebound, however, and through mid-1981, the % who supported continued NPP construction in USA was 5 to 10% more than those in opposition. Men's and women's attitudes are different and were differentially affected by the TMI accident. Beliefs and attitudes about specific nuclear power issues were explored using questionnaires. Reactor-safety concerns were found to be more important than nuclear-waste concerns. Nuclear fuel-supply considerations are believed to be a major advantage of nuclear power. The public was largely unaware of the breeder-reactor concept. The US public generally does not favor selling US reactors abroad. It also greatly underestimates how long it takes to build a NPP. Most people believed solar-generated electricity is cheapest. The public has little information or has misinformation about some areas of nuclear power. (DLC)

  16. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect (OSTI)

    Wang, S.-J. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, K.-S. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, S.-C. [Taiwan Power Company, Taiwan (China)

    2004-05-15

    Reactor coolant system (RCS) injection is an important strategy for severe accident management of a pressurized water reactor (PWR) system. Maanshan is a typical Westinghouse PWR nuclear power plant (NPP) with large, dry containment. The severe accident management guideline (SAMG) of Maanshan NPP is developed based on the Westinghouse Owners Group (WOG) SAMG.The purpose of this work is to analyze the RCS injection strategy of PWR system in an overheated core condition. Power is assumed recovered as the vessel water level drops to the bottom of active fuel. The Modular Accident Analysis Program version 4.0.4 (MAAP4) code is chosen as a tool for analysis. A postulated station blackout sequence for Maanshan NPP is cited as a reference case for this analysis. The hot leg creep rupture occurs during the mitigation action with immediate injection after power recovery according to WOG SAMG, which is not desired. This phenomenon is not considered while developing the WOG SAMG. Two other RCS injection methods are analyzed by using MAAP4. The RCS injection strategy is modified in the Maanshan SAMG. These results can be applied for typical PWR NPPs.

  17. Multidisciplinary framework for human reliability analysis with an application to errors of commission and dependencies

    SciTech Connect (OSTI)

    Barriere, M.T.; Luckas, W.J.; Wreathall, J.; Cooper, S.E.; Bley, D.C.; Ramey-Smith, A.

    1995-08-01

    Since the early 1970s, human reliability analysis (HRA) has been considered to be an integral part of probabilistic risk assessments (PRAs). Nuclear power plant (NPP) events, from Three Mile Island through the mid-1980s, showed the importance of human performance to NPP risk. Recent events demonstrate that human performance continues to be a dominant source of risk. In light of these observations, the current limitations of existing HRA approaches become apparent when the role of humans is examined explicitly in the context of real NPP events. The development of new or improved HRA methodologies to more realistically represent human performance is recognized by the Nuclear Regulatory Commission (NRC) as a necessary means to increase the utility of PRAS. To accomplish this objective, an Improved HRA Project, sponsored by the NRC`s Office of Nuclear Regulatory Research (RES), was initiated in late February, 1992, at Brookhaven National Laboratory (BNL) to develop an improved method for HRA that more realistically assesses the human contribution to plant risk and can be fully integrated with PRA. This report describes the research efforts including the development of a multidisciplinary HRA framework, the characterization and representation of errors of commission, and an approach for addressing human dependencies. The implications of the research and necessary requirements for further development also are discussed.

  18. Benchmark Report on Key Outage Attributes: An Analysis of Outage Improvement Opportunities and Priorities

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    Germain, Shawn St.; Farris, Ronald

    2014-09-01

    Advanced Outage Control Center (AOCC), is a multi-year pilot project targeted at Nuclear Power Plant (NPP) outage improvement. The purpose of this pilot project is to improve management of NPP outages through the development of an AOCC that is specifically designed to maximize the usefulness of communication and collaboration technologies for outage coordination and problem resolution activities. This report documents the results of a benchmarking effort to evaluate the transferability of technologies demonstrated at Idaho National Laboratory and the primary pilot project partner, Palo Verde Nuclear Generating Station. The initial assumption for this pilot project was that NPPs generally do not take advantage of advanced technology to support outage management activities. Several researchers involved in this pilot project have commercial NPP experience and believed that very little technology has been applied towards outage communication and collaboration. To verify that the technology options researched and demonstrated through this pilot project would in fact have broad application for the US commercial nuclear fleet, and to look for additional outage management best practices, LWRS program researchers visited several additional nuclear facilities.

  19. O Ti-tE LOVE

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  3. Energy Intensity Indicators: Residential Source Energy Consumption

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    Figure R1 below reports as index numbers over the period 1970 through 2011: 1) the number of U.S. households, 2) the average size of those housing units, 3) residential source energy consumption, 4...

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  7. A-6005-441 (REV 0)

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    The contractor will provide also provide SME support during the Headquarter PFP Peer Review. This is in support of the independent review of the ARRA RL-011.R1 Acquisition ...

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    ... Mills",21,"R",1159,"R","*","*",10,,"*",0,0,4 323,"Printing and Related Support",13,,1947,,"*","*",5,,"*",0,0,"*" 324,"Petroleum and Coal Products",89,,4095,"R",1,1,45,,"*","*",...

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    ... X H or OH; Z H or CH 2 OH ; R 1 R 2 R 3 R4 H, OH, or OCH3. Quantum Mechanical (QM) methods: Geometry optimization and electronic energy calculations ...

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  20. Gillard Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 12 MW 1 Click "Edit With Form" above to add content History and...

  1. Boiling Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  2. Fales Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  3. Sespe Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 11 MW 1 Click "Edit With Form" above to add content History and...

  4. Little Melozitna Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    88C361.15 K 190.4 F 650.07 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  5. Mt Signal Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    135C408.15 K 275 F 734.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 15 MW 1 Click "Edit With Form" above to add content History and...

  6. Roystone Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  7. Latty Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  8. Dyke Hot Springs Geothermal Area | Open Energy Information

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    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  9. Spencer Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  10. Kwiniuk Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    75C348.15 K 167 F 626.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  11. Clear Lake Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    300C573.15 K 572 F 1,031.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 29 MW 1 Click "Edit With Form" above to add content History and...

  12. The Needles Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 17 MW 1 Click "Edit With Form" above to add content History and...

  13. Boulder Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  14. McGee Mountain Geothermal Area | Open Energy Information

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    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  15. Newcastle Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 12 MW 1 Click "Edit With Form" above to add content History and...

  16. Okpilak Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    85C358.15 K 185 F 644.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 2 MW 1 Click "Edit With Form" above to add content History and...

  17. Surprise Valley Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    115C388.15 K 239 F 698.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 8 MW 1 Click "Edit With Form" above to add content History and...

  18. Wilbur Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    160C433.15 K 320 F 779.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 29 MW 1 Click "Edit With Form" above to add content History and...

  19. Melozi Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  20. Calistoga Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    140C413.15 K 284 F 743.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 17 MW 1 Click "Edit With Form" above to add content History and...

  1. Dall Hot Spring Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3.5 MW 1 Click "Edit With Form" above to add content History and...

  2. Magic Reservoir Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 9 MW 1 Click "Edit With Form" above to add content History and...

  3. Serpentine Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    145C418.15 K 293 F 752.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 17 MW 1 Click "Edit With Form" above to add content History and...

  4. Fort Bidwell Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 9 MW 1 Click "Edit With Form" above to add content History and...

  5. Makushin Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    205C478.15 K 401 F 860.67 R 1 USGS Estimated Reservoir Volume: 12 km 1 USGS Mean Capacity: 107 MW 1 Click "Edit With Form" above to add content History and...

  6. Indian Creek Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  7. Lakeview Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    135C408.15 K 275 F 734.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 20 MW 1 Click "Edit With Form" above to add content History and...

  8. Worswick Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  9. Moana Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  10. Maple Grove Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  11. Crane Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  12. Sonoma Mission Inn Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  13. Breitenbush Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    150C423.15 K 302 F 761.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 8 MW 1 Click "Edit With Form" above to add content History and...

  14. Little Valley Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    125C398.15 K 257 F 716.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 15 MW 1 Click "Edit With Form" above to add content History and...

  15. Mcdermitt Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  16. Cherry Creek Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4.5 MW 1 Click "Edit With Form" above to add content History and...

  17. Emigrant Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    165C438.15 K 329 F 788.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 40 MW 1 Click "Edit With Form" above to add content History and...

  18. Clear Creek Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  19. Deer Creek Hot Spring Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    125C398.15 K 257 F 716.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 16 MW 1 Click "Edit With Form" above to add content History and...

  20. Huckleberry Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 39 MW 1 Click "Edit With Form" above to add content History and...

  1. Warfield Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  2. Vale Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    145C418.15 K 293 F 752.67 R 1 USGS Estimated Reservoir Volume: 8 km 1 USGS Mean Capacity: 45 MW 1 Click "Edit With Form" above to add content History and...

  3. Geyser Bight Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    182C455.15 K 359.6 F 819.27 R 1 USGS Estimated Reservoir Volume: 12 km 1 USGS Mean Capacity: 98 MW 1 Click "Edit With Form" above to add content History and...

  4. Routt Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 8 MW 1 Click "Edit With Form" above to add content History and...

  5. Riverside Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 8 MW 1 Click "Edit With Form" above to add content History and...

  6. Idaho Bath Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  7. Hot Lake Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    150C423.15 K 302 F 761.67 R 1 USGS Estimated Reservoir Volume: 5 km 1 USGS Mean Capacity: 43 MW 1 Click "Edit With Form" above to add content History and...

  8. Circle Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  9. Fallon Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    195C468.15 K 383 F 842.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 53 MW 1 Click "Edit With Form" above to add content History and...

  10. Kellog Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  11. Manley Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  12. Dunes Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    145C418.15 K 293 F 752.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 19 MW 1 Click "Edit With Form" above to add content History and...

  13. Mickey Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    170C443.15 K 338 F 797.67 R 1 USGS Estimated Reservoir Volume: 4 km 1 USGS Mean Capacity: 41 MW 1 Click "Edit With Form" above to add content History and...

  14. Brockway Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 2 MW 1 Click "Edit With Form" above to add content History and...

  15. Mitchell Butte Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 10 MW 1 Click "Edit With Form" above to add content History and...

  16. Hot Spring On Umnak Island Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 3.7 MW 1 Click "Edit With Form" above to add content History and...

  17. Lava Creek Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 5 MW 1 Click "Edit With Form" above to add content History and...

  18. Medical Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  19. Randsburg Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    105C378.15 K 221 F 680.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 7 MW 1 Click "Edit With Form" above to add content History and...

  20. South Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    85C358.15 K 185 F 644.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 1.7 MW 1 Click "Edit With Form" above to add content History and...

  1. Neinmeyer Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 6 MW 1 Click "Edit With Form" above to add content History and...

  2. Black Warrior Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    135C408.15 K 275 F 734.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 17 MW 1 Click "Edit With Form" above to add content History and...

  3. Summer Lake Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 8 MW 1 Click "Edit With Form" above to add content History and...

  4. Grass Valley Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    120C393.15 K 248 F 707.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 7 MW 1 Click "Edit With Form" above to add content History and...

  5. Weberg Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  6. Grovers Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  7. Kilo Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    75C348.15 K 167 F 626.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 2 MW 1 Click "Edit With Form" above to add content History and...

  8. Ophir Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    85C358.15 K 185 F 644.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 2.3 MW 1 Click "Edit With Form" above to add content History and...

  9. Sharkey Hot Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    115C388.15 K 239 F 698.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 10 MW 1 Click "Edit With Form" above to add content History and...

  10. East Basin Creek Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  11. Jemez Springs Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 9 MW 1 Click "Edit With Form" above to add content History and...

  12. Willow Well Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    75C348.15 K 167 F 626.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 1.3 MW 1 Click "Edit With Form" above to add content History and...

  13. Paso Robles Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    95C368.15 K 203 F 662.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3 MW 1 Click "Edit With Form" above to add content History and...

  14. Radio Towers Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    90C363.15 K 194 F 653.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 4 MW 1 Click "Edit With Form" above to add content History and...

  15. Great Sitkin Island Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    130C403.15 K 266 F 725.67 R 1 USGS Estimated Reservoir Volume: 3 km 1 USGS Mean Capacity: 15 MW 1 Click "Edit With Form" above to add content History and...

  16. Tolovana Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    110C383.15 K 230 F 689.67 R 1 USGS Estimated Reservoir Volume: 2 km 1 USGS Mean Capacity: 15 MW 1 Click "Edit With Form" above to add content History and...

  17. Sierra Valley Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    100C373.15 K 212 F 671.67 R 1 USGS Estimated Reservoir Volume: 1 km 1 USGS Mean Capacity: 3.5 MW 1 Click "Edit With Form" above to add content History and...

  18. Harmonic mode competition in a terahertz gyrotron backward-wave...

    Office of Scientific and Technical Information (OSTI)

    The viability of a harmonic gyro-BWO is assessed on the basis of the results obtained. Authors: Kao, S. H. ; Chiu, C. C. ; Chang, P. C. ; Wu, K. L. ; Chu, K. R. 1 + Show Author ...

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  1. OZZ Solar Inc Sky Ozz International | Open Energy Information

    Open Energy Info (EERE)

    OZZ Solar Inc Sky Ozz International Jump to: navigation, search Name: OZZ Solar Inc. (Sky Ozz International) Place: Concord, Ontario, Canada Zip: L4K 4R1 Sector: Solar Product:...

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    ... Yang, Nan (2) Howe, Jane Y (1) Hubbard, Camden R (1) Jordan, Tyson L (1) Shingledecker, ... Shyam, Amit ; Blau, Peter Julian ; Jordan, Tyson L ; Yang, Nan ; Pollard, Michael J ...

  3. The LANL urban consequences project (Conference) | SciTech Connect

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    Authors: Bos, Randall J 1 ; Brown, Michael J 1 ; Goorley, John T 1 ; Grinstein, Fernando 1 ; Heger, Arlen S 1 ; Linn, Rodman R 1 ; Zhang, Duan Z 1 + Show Author ...

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    ... Abbasi, Daniel (1) Armstrong, Tom (1) Arndt, Deke (1) Arnold, J. R. (1) Arnott, J. C. (1) Baptista, Sandra (1) Bartuska, Ann (1) Behar, D. (1) Blair, Maria (1) Brasseur, Guy P. (1) ...

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    ... Hudson, G B (1) Kane, S R (1) Rice, D W (1) Smith, M M (1) Tompson, A B (1) Walsh, S C (1) ... dissolutionreprecipitation reactions Smith, M M ; Walsh, S C ; McNab, W W ; Carroll, ...

  7. Phenylnaphthalene Derivatives as Heat Transfer Fluids for Concentratin...

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    Results highlighted the advantages of inherent thermal energy storage in the power conversion system. less Authors: McFarlane, Joanna 1 ; Bell, Jason R 1 ; Felde, David K 1 ...

  8. Using field observations to inform thermal hydrology models of...

    Office of Scientific and Technical Information (OSTI)

    Authors: Atchley, Adam L. 1 ; Painter, Scott L. 2 ; Harp, Dylan R. 1 ; Coon, Ethan T. 1 ; Wilson, Cathy J. 1 ; Liljedahl, Anna K. 3 ; Romanovsky, V. E. 3 Search DOE ...

  9. Vapor Extraction Well Performance and Recommendations for Future...

    Office of Scientific and Technical Information (OSTI)

    No abstract provided. Authors: Jackson, D. 1 ; Hyde, W. 1 ; Walker, R. 1 ; Riha, B. 1 ; Ross, J. 1 ; Kramer, M. 1 + Show Author Affiliations Savannah River Site (SRS), ...

  10. Fast response of electron-scale turbulence to auxiliary heating...

    Office of Scientific and Technical Information (OSTI)

    Search SciTech Connect for author "Domier, C. W." Search SciTech Connect for ORCID "0000000280807773" Search orcid.org for ORCID "0000000280807773" ; Bell, R. 1 ; Smith, D. R. ...

  11. | Department of Energy

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

    Agenda5-20-11r1.pdf More Documents & Publications 2011 Cost Symposium Agenda 4-28-11 web draft.xls 2011 Cost Symposium Agenda for web (2)-OPAM...

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    Greenhill, Andrew R. (1) Maldonado-Gmez, Maria X. (1) Martnez, Ins (1) Siba, Peter ... ; Stegen, James C. ; Maldonado-Gmez, Maria X. ; Eren, A. Murat ; Siba, Peter M. ; ...

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    (1) Metz, Thomas O. (1) Mitchell, Hugh (1) Pomraning, Kyle R. (1) Sherman, Louis A (1) Smith, Richard D (1) Taylor, Ronald (1) Thimmapuram, Jyothi (1) Wei, Siwei (1) Welkie, David...

  14. Seawood Designs Inc | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Seawood Designs Inc Address: 201 Marine Drive Cobble Hill Place: Vancouver Island Zip: V0R 1L1 Region: Canada Sector: Marine and Hydrokinetic...

  15. BPA-2014-01924-FOIA Request

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

    Harkonen, P.Eng. Consulting Specialist, Power Systems NORDMIN ENGINEERING LTD. 160 Logan Avenue Thunder Bay, ON, CANADA P7A 6R1 Phone: (807) 683-4858 Fax: (807) 344-0404 ww W...

  16. BPA-2014-01924-FOIA Response

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

    Nordmin Engineering Ltd. Attn: Harold Harkonen, P. Eng., Consulting Specialist 160 Logan Avenue Thunder Bay, Ontario Canada P7A6R1 Mr. Harkonen: We have received your request...

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    Available Full TextPublicly Available Full Text1 Citation Only0 Filtered Results Filter Results Filter by Author Chin, Mian (1) Meyer, Kerry (1) Norris, Joel R. (1) Oreopoulos, ...

  18. A SEARCH FOR NEW CANDIDATE SUPER-CHANDRASEKHAR-MASS TYPE Ia SUPERNOVAE...

    Office of Scientific and Technical Information (OSTI)

    Authors: Scalzo, R. 1 ; Aldering, G. ; Aragon, C. ; Bailey, S. ; Childress, M. ; Fakhouri, H. K. ; Hsiao, E. Y. 2 ; Antilogus, P. ; Bongard, S. ; Canto, A. ; Cellier-Holzem, F. ...

  19. Wavelength-tunable optical ring resonators (Patent) | DOEPatents

    Office of Scientific and Technical Information (OSTI)

    Inventors: Watts, Michael R. 1 ; Trotter, Douglas C. 1 ; Young, Ralph W. 1 ; Nielson, Gregory N. 1 + Show Author Affiliations (Albuquerque, NM) Issue Date: 2011-07-19 OSTI ...

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    ... Helm, Lothar (1) Jensen, P. (1) Kampf, Anthony R. (1) Kolitsch, U. (1) Liu, Weihua (1) Martinez-Criado, Gema (1) Mills, Stuart J. (1) Pluth, Joseph J. (1) Pring, A. (1) Pring, ...

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    CN Long (1) Charles E. Kolb (1) Collins, D. R. (1) Save Results Save this search to My ... from active wildfire and agricultural burns to help identify the impact of these ...

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    ... Filter Results Filter by Subject Filter by Author Courter, Joel R. (1) Freire, Ernesto (1) ... Daniel J. ; Princiotto, Amy M. ; Seaman, Michael S. ; Freire, Ernesto ; et al April 2016

  3. Biogenic Aerosols - Effects on Climate and Clouds. Cloud Optical...

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    A good range of cloud conditions were observed from clear sky to heavy rainfall. Authors: Niple, E. R. 1 ; Scott, H. E. 1 + Show Author Affiliations Aerodyne Research, Inc., ...

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    Filter Results Filter by Author Anderson, Bill (1) De Haro, Leyma P. (1) Flynn, Edward R. (1) Hathaway, Helen J. (1) Huber, Dale L. (1) Karaulanov, Todor (1) Matlashov, Andrei N. ...

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    Meyer, Kerry (1) Nenes, Athanasios (1) Norris, Joel R. (1) Platnick, Steven (1) Sullivan, Sylvia C. (1) Yu, Hongbin (1) Yuan, Tianle (1) Zelinka, Mark (1) Save Results Excel (limit ...

  7. Pinoresinol reductase 1 impacts lignin distribution during secondary cell wall biosynthesis in Arabidopsis

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

    Zhao, Qiao; Zeng, Yining; Yin, Yanbin; Pu, Yunqiao; Jackson, Lisa A.; Engle, Nancy L.; Martin, Madhavi Z.; Tschaplinski, Timothy J.; Ding, Shi-You; Ragauskas, Arthur J.; et al

    2014-08-05

    In this paper, pinoresinol reductase (PrR) catalyzes the conversion of the lignan (-)-pinoresinol to (-)-lariciresinol in Arabidopsis thaliana, where it is encoded by two genes, PrR1 and PrR2, that appear to act redundantly. PrR1 is highly expressed in lignified inflorescence stem tissue, whereas PrR2 expression is barely detectable in stems. Co-expression analysis has indicated that PrR1 is co-expressed with many characterized genes involved in secondary cell wall biosynthesis, whereas PrR2 expression clusters with a different set of genes. The promoter of the PrR1 gene is regulated by the secondary cell wall related transcription factors SND1 and MYB46. The loss-of-function mutantmore » of PrR1 shows, in addition to elevated levels of pinoresinol, significantly decreased lignin content and a slightly altered lignin structure with lower abundance of cinnamyl alcohol end groups. Stimulated Raman scattering (SRS) microscopy analysis indicated that the lignin content of the prr1-1 loss-of-function mutant is similar to that of wild-type plants in xylem cells, which exhibit a normal phenotype, but is reduced in the fiber cells. Finally, together, these data suggest an association of the lignan biosynthetic enzyme encoded by PrR1 with secondary cell wall biosynthesis in fiber cells.« less

  8. Thick Concrete Specimen Construction, Testing, and Preliminary Analysis

    SciTech Connect (OSTI)

    Clayton, Dwight A.; Hoegh, Kyle; Khazanovich, Lev

    2015-03-01

    The purpose of the U.S. Department of Energy Office of Nuclear Energy’s Light Water Reactor Sustainability (LWRS) Program is to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the operating lifetimes of nuclear power plants (NPPs) beyond 60 years. Since many important safety structures in an NPP are constructed of concrete, inspection techniques must be developed and tested to evaluate the internal condition. In-service containment structures generally do not allow for the destructive measures necessary to validate the accuracy of these inspection techniques. This creates a need for comparative testing of the various nondestructive evaluation (NDE) measurement techniques on concrete specimens with known material properties, voids, internal microstructure flaws, and reinforcement locations. A preliminary report detailed some of the challenges associated with thick reinforced concrete sections and prioritized conceptual designs of specimens that could be fabricated to represent NPP concrete structures for using in NDE evaluation comparisons. This led to the construction of the concrete specimen presented in this report, which has sufficient reinforcement density and cross-sectional size to represent an NPP containment wall. Details on how a suitably thick concrete specimen was constructed are presented, including the construction materials, final nominal design schematic, as well as formwork and rigging required to safely meet the desired dimensions of the concrete structure. The report also details the type and methods of forming the concrete specimen as well as information on how the rebar and simulated defects were embedded. Details on how the resulting specimen was transported, safely anchored, and marked to allow access for systematic comparative NDE testing of defects in a representative NPP containment wall concrete specimen are also given. Data collection using the MIRA Ultrasonic NDE equipment and

  9. Structural analysis of three global land models on carbon cycle simulations using a traceability framework

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

    Rafique, R.; Xia, J.; Hararuk, O.; Luo, Y.

    2014-06-27

    Modeled carbon (C) storage capacity is largely determined by the C residence time and net primary productivity (NPP). Extensive research has been done on NPP dynamics but the residence time and their relationships with C storage are much less studied. In this study, we implemented a traceability analysis to understand the modeled C storage and residence time in three land surface models: CSIRO's Atmosphere Biosphere Land Exchange (CABLE) with 9 C pools, Community Land Model (version 3.5) combined with Carnegie-Ames-Stanford Approach (CLM3.5-CASA) with 12 C pools and Community Land Model (version 4) (CLM4) with 26 C pools. The globally averagedmoreC storage and residence time was computed at both individual pool and total ecosystem levels. The spatial distribution of total ecosystem C storage and residence time differ greatly among the three models. The CABLE model showed a closer agreement with measured C storage and residence time in plant and soil pools than CLM3.5-CASA and CLM4. However, CLM3.5-CASA and CLM4 were close to each other in modeled C storage but not with measured data. CABLE stores more C in root whereas CLM3.5-CASA and CLM4 store more C in woody pools, partly due to differential NPP allocation in respective pools. The C residence time in individual C pools is greatly different among models, largely because of different transfer coefficient values among pools. CABLE had higher bulk residence time for soil C pools than the other two models. Overall, the traceability analysis used in this study can help fully characterizes the behavior of complex land models.less

  10. Digital I and C system upgrade integration technique

    SciTech Connect (OSTI)

    Huang, H. W.; Shih, C.; Wang, J. R.; Huang, K. C.

    2012-07-01

    This work developed an integration technique for digital I and C system upgrade, the utility can replace the I and C systems step by step systematically by this method. Inst. of Nuclear Energy Research (INER) developed a digital Instrumentation and Control (I and C) replacement integration technique on the basis of requirement of the three existing nuclear power plants (NPPs), which are Chin-Shan (CS) NPP, Kuo-Sheng (KS) NPP, and Maanshan (MS) NPP, in Taiwan, and also developed the related Critical Digital Review (CDR) Procedure. The digital I and C replacement integration technique includes: (I) Establishment of Nuclear Power Plant Digital Replacement Integration Guideline, (2) Preliminary Investigation on I and C System Digitalization, (3) Evaluation on I and C System Digitalization, and (4) Establishment of I and C System Digitalization Architectures. These works can be a reference for performing I and C system digital replacement integration of the three existing NPPs of Taiwan Power Company (TPC). A CDR is the review for a critical system digital I and C replacement. The major reference of this procedure is EPRI TR- 1011710 (2005) 'Handbook for Evaluating Critical Digital Equipment and Systems' which was published by the Electric Power Research Inst. (EPRI). With this document, INER developed a TPC-specific CDR procedure. Currently, CDR becomes one of the policies for digital I and C replacement in TPC. The contents of this CDR procedure include: Scope, Responsibility, Operation Procedure, Operation Flow Chart, CDR review items. The CDR review items include the comparison of the design change, Software Verification and Validation (SVandV), Failure Mode and Effects Analysis (FMEA), Evaluation of Diversity and Defense-in-depth (D3), Evaluation of Watchdog Timer, Evaluation of Electromagnetic Compatibility (EMC), Evaluation of Grounding for System/Component, Seismic Evaluation, Witness and Inspection, Lessons Learnt from the Digital I and C Failure Events. A

  11. Design and Validation of Control Room Upgrades Using a Research Simulator Facility

    SciTech Connect (OSTI)

    Ronald L. Boring; Vivek Agarwal; Jeffrey C. Joe; Julius J. Persensky

    2012-11-01

    Since 1981, the United States (U.S.) Nuclear Regulatory Commission (NRC) [1] requires a plant- specific simulator facility for use in training at U.S. nuclear power plants (NPPs). These training simulators are in near constant use for training and qualification of licensed NPP operators. In the early 1980s, the Halden Man-Machine Laboratory (HAMMLab) at the Halden Reactor Project (HRP) in Norway first built perhaps the most well known set of research simulators. The HRP offered a high- fidelity simulator facility in which the simulator is functionally linked to a specific plant but in which the human-machine interface (HMI) may differ from that found in the plant. As such, HAMMLab incorporated more advanced digital instrumentation and controls (I&C) than the plant, thereby giving it considerable interface flexibility that researchers took full advantage of when designing and validating different ways to upgrade NPP control rooms. Several U.S. partnersthe U.S. NRC, the Electrical Power Research Institute (EPRI), Sandia National Laboratories, and Idaho National Laboratory (INL) as well as international members of the HRP, have been working with HRP to run control room simulator studies. These studies, which use crews from Scandinavian plants, are used to determine crew behavior in a variety of normal and off-normal plant operations. The findings have ultimately been used to guide safety considerations at plants and to inform advanced HMI designboth for the regulator and in industry. Given the desire to use U.S. crews of licensed operators on a simulator of a U.S. NPP, there is a clear need for a research simulator facility in the U.S. There is no general-purpose reconfigurable research oriented control room simulator facility in the U.S. that can be used for a variety of studies, including the design and validation of control room upgrades.

  12. Moderate forest disturbance as a stringent test for gap and big-leaf models

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

    Bond-Lamberty, Benjamin; Fisk, Justin P.; Holm, Jennifer; Bailey, Vanessa L.; Bohrer, Gil; Gough, Christopher

    2015-01-27

    Disturbance-induced tree mortality is a key factor regulating the carbon balance of a forest, but tree mortality and its subsequent effects are poorly represented processes in terrestrial ecosystem models. It is thus unclear whether models can robustly simulate moderate (non-catastrophic) disturbances, which tend to increase biological and structural complexity and are increasingly common in aging US forests. We tested whether three forest ecosystem models – Biome-BGC (BioGeochemical Cycles), a classic big-leaf model, and the ZELIG and ED (Ecosystem Demography) gap-oriented models – could reproduce the resilience to moderate disturbance observed in an experimentally manipulated forest (the Forest Accelerated Succession Experimentmore » in northern Michigan, USA, in which 38% of canopy dominants were stem girdled and compared to control plots). Each model was parameterized, spun up, and disturbed following similar protocols and run for 5 years post-disturbance. The models replicated observed declines in aboveground biomass well. Biome-BGC captured the timing and rebound of observed leaf area index (LAI), while ZELIG and ED correctly estimated the magnitude of LAI decline. None of the models fully captured the observed post-disturbance C fluxes, in particular gross primary production or net primary production (NPP). Biome-BGC NPP was correctly resilient but for the wrong reasons, and could not match the absolute observational values. ZELIG and ED, in contrast, exhibited large, unobserved drops in NPP and net ecosystem production. The biological mechanisms proposed to explain the observed rapid resilience of the C cycle are typically not incorporated by these or other models. It is thus an open question whether most ecosystem models will simulate correctly the gradual and less extensive tree mortality characteristic of moderate disturbances.« less

  13. Comprehensive ecosystem model-experiment synthesis using multiple datasets at two temperate forest free-air CO2 enrichment experiments: model performance and compensating biases

    SciTech Connect (OSTI)

    Walker, Anthony P; Hanson, Paul J; DeKauwe, Martin G; Medlyn, Belinda; Zaehle, S; Asao, Shinichi; Dietze, Michael; Hickler, Thomas; Huntinford, Chris; Iversen, Colleen M; Jain, Atul; Lomas, Mark; Luo, Yiqi; McCarthy, Heather R; Parton, William; Prentice, I. Collin; Thornton, Peter E; Wang, Shusen; Wang, Yingping; Warlind, David; Weng, Ensheng; Warren, Jeffrey; Woodward, F. Ian; Oren, Ram; Norby, Richard J

    2014-01-01

    Free Air CO2 Enrichment (FACE) experiments provide a remarkable wealth of data to test the sensitivities of terrestrial ecosystem models (TEMs). In this study, a broad set of 11 TEMs were compared to 22 years of data from two contrasting FACE experiments in temperate forests of the south eastern US the evergreen Duke Forest and the deciduous Oak Ridge forest. We evaluated the models' ability to reproduce observed net primary productivity (NPP), transpiration and Leaf Area index (LAI) in ambient CO2 treatments. Encouragingly, many models simulated annual NPP and transpiration within observed uncertainty. Daily transpiration model errors were often related to errors in leaf area phenology and peak LAI. Our analysis demonstrates that the simulation of LAI often drives the simulation of transpiration and hence there is a need to adopt the most appropriate of hypothesis driven methods to simulate and predict LAI. Of the three competing hypotheses determining peak LAI (1) optimisation to maximise carbon export, (2) increasing SLA with canopy depth and (3) the pipe model the pipe model produced LAI closest to the observations. Modelled phenology was either prescribed or based on broader empirical calibrations to climate. In some cases, simulation accuracy was achieved through compensating biases in component variables. For example, NPP accuracy was sometimes achieved with counter-balancing biases in nitrogen use efficiency and nitrogen uptake. Combined analysis of parallel measurements aides the identification of offsetting biases; without which over-confidence in model abilities to predict ecosystem function may emerge, potentially leading to erroneous predictions of change under future climates.

  14. An Empirical Study on Ultrasonic Testing in Lieu of Radiography for Nuclear Power Plants

    SciTech Connect (OSTI)

    Moran, Traci L.; Pardini, Allan F.; Ramuhalli, Pradeep; Prowant, Matthew S.; Mathews, Royce

    2012-09-01

    Research is being conducted for the U.S. Nuclear Regulatory Commission (NRC) at the Pacific Northwest National Laboratory (PNNL) to assess the capability, effectiveness, and reliability of ultrasonic testing (UT) as a replacement method for radiographic testing (RT) for inspecting nuclear power plant (NPP) components. A primary objective of this work is to evaluate UT techniques to assess their ability to detect, locate, size, and characterize fabrication flaws in typical NPP weldments. This particular study focused on the evaluation of four carbon steel pipe-to-pipe welds on specimens that ranged in thicknesses from 19.05 mm (0.75 in.) to 27.8 mm (1.094 in.) and were 355.6 mm (14.0 in.) or 406.4 mm (16.0 in.) in diameter. The pipe welds contained both implanted (intentional) fabrication flaws as well as bonus (unintentional) flaws throughout the entire thickness of the weld and the adjacent base material. The fabrication flaws were a combination of planar and volumetric flaw types, including incomplete fusion, incomplete penetration, cracks, porosity, and slag inclusions. The examinations were conducted using phased-array UT (PA UT) techniques applied primarily for detection and length sizing of the flaws. Radiographic examinations were also conducted on the specimens with RT detection and length sizing results being used to establish true state. This paper will discuss the comparison of UT and RT (true state) detection results conducted to date along with a discussion on the technical gaps that need to be addressed before these methods can be used interchangeably for repair and replacement activities for NPP components.

  15. Moderate forest disturbance as a stringent test for gap and big-leaf models

    SciTech Connect (OSTI)

    Bond-Lamberty, Benjamin; Fisk, Justin P.; Holm, Jennifer; Bailey, Vanessa L.; Bohrer, Gil; Gough, Christopher

    2015-01-27

    Disturbance-induced tree mortality is a key factor regulating the carbon balance of a forest, but tree mortality and its subsequent effects are poorly represented processes in terrestrial ecosystem models. It is thus unclear whether models can robustly simulate moderate (non-catastrophic) disturbances, which tend to increase biological and structural complexity and are increasingly common in aging US forests. We tested whether three forest ecosystem models – Biome-BGC (BioGeochemical Cycles), a classic big-leaf model, and the ZELIG and ED (Ecosystem Demography) gap-oriented models – could reproduce the resilience to moderate disturbance observed in an experimentally manipulated forest (the Forest Accelerated Succession Experiment in northern Michigan, USA, in which 38% of canopy dominants were stem girdled and compared to control plots). Each model was parameterized, spun up, and disturbed following similar protocols and run for 5 years post-disturbance. The models replicated observed declines in aboveground biomass well. Biome-BGC captured the timing and rebound of observed leaf area index (LAI), while ZELIG and ED correctly estimated the magnitude of LAI decline. None of the models fully captured the observed post-disturbance C fluxes, in particular gross primary production or net primary production (NPP). Biome-BGC NPP was correctly resilient but for the wrong reasons, and could not match the absolute observational values. ZELIG and ED, in contrast, exhibited large, unobserved drops in NPP and net ecosystem production. The biological mechanisms proposed to explain the observed rapid resilience of the C cycle are typically not incorporated by these or other models. It is thus an open question whether most ecosystem models will simulate correctly the gradual and less extensive tree mortality characteristic of moderate disturbances.

  16. Inspection of Nuclear Power Plant Containment Structures

    SciTech Connect (OSTI)

    Graves, H.L.; Naus, D.J.; Norris, W.E.

    1998-12-01

    Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

  17. Application of different nuclides in retrospective dosimetry

    SciTech Connect (OSTI)

    Konheiser, J.; Mittag, S.; Viehrig, H.W.; Gleisberg, B.

    2011-07-01

    The activities of nuclides produced via the neutron irradiation of reactor pressure vessel (RPV) steel are used to validate respective fluence calculations. Niobium, nickel, and technetium isotopes from RPV trepans of the decommissioned NPP Greifswald (VVER-440) have been analyzed. The activities were determined by TRAMO (Monte-Carlo) fluence calculations, newly applying 640 neutron-energy groups and ENDF/B7 data. Relative to earlier results, fluences up to 20% higher have been computed, leading to somewhat better agreement between measurement and calculation, particularly in the case of Tc-99. (authors)

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

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2006-07-15

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

  19. Multiple recycle of REMIX fuel based on reprocessed uranium and plutonium mixture in thermal reactors

    SciTech Connect (OSTI)

    Fedorov, Y.S.; Bibichev, B.A.; Zilberman, B.Y.; Baryshnikov, M.V.; Kryukov, O.V.; Khaperskaya, A.V.

    2013-07-01

    REMIX fuel consumption in WWER-1000 is considered. REMIX fuel is fabricated from non-separated mixture of uranium and plutonium obtained during NPP spent fuel reprocessing with further makeup by enriched natural uranium. It makes possible to recycle several times the total amount of uranium and plutonium obtained from spent fuel with 100% loading of the WWER-1000 core. The stored SNF could be also involved in REMIX fuel cycle by enrichment of regenerated uranium. The same approach could be applied to closing the fuel cycle of CANDU reactors. (authors)

  20. Migration and Retardation of Chemical Toxic Components from Radioactive Waste - Hydrochemical Aspects

    SciTech Connect (OSTI)

    Jedinakova-Krizova, V.; Hanslik, E.

    2003-02-24

    A systematic analysis of nuclear power plant (NPP) operation and radioactive wastes disposal (near-surface disposal and geologic disposal) in underground repositories has provided the basis for a comparison between the radiotoxicity and chemotoxicity as part of an EIA (environmental impact assessment) procedure. This contribution summarizes the hydrochemical mechanisms of transport and retardation processes, chemistry and migration behavior of radionuclides and chemical toxics in natural sorbents, especially bentonites. The effect of solubility and dissolution reactions, diffusion and sorption/desorption, complexation and variations in the aqueous phase composition, pH-value and oxidation-reduction properties and other phenomena affecting distribution coefficients (Kd values) is discussed.

  1. Review of Quantitative Software Reliability Methods

    SciTech Connect (OSTI)

    Chu, T.L.; Yue, M.; Martinez-Guridi, M.; Lehner, J.

    2010-09-17

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I&C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I&C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I&C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of digital systems

  2. Current and anticipated uses of thermal hydraulic codes at the Japan Atomic Energy Research Institute

    SciTech Connect (OSTI)

    Akimoto, Hajime; Kukita; Ohnuki, Akira

    1997-07-01

    The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission`s research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment.

  3. Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident

    SciTech Connect (OSTI)

    Kun Zhang; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

    2006-07-01

    The postulated total station blackout accident (SBO) of PWR NPP with 600 MWe in China is analyzed as the base case using SCDAP/RELAP5 code. Then the hot leg or surge line are assumed to rupture before the lower head of Reactor Pressure Vessel (RPV) ruptures, and the progressions are analyzed in detail comparing with the base case. The results show that the accidental rupture of hot leg or surge line will greatly influence the progression of accident. The probability of hot leg or surge line rupture in intentional depressurization is also studied in this paper, which provides a suggestion to the development of Severe Accident Management Guidelines (SAMG). (authors)

  4. Principles of providing inherent self-protection and passive safety characteristics of the SVBR-75/100 type modular reactor installation for nuclear power plants of different capacity and purpose

    SciTech Connect (OSTI)

    Toshinsky, G.I.; Komlev, O.G.; Novikova, N.N.; Tormyshev, I.V.; Stepanov, V.S.; Klimov, N.N.; Dedoul, A.V.

    2007-07-01

    The report presents a brief description of the reactor installation SVBR-75/100, states a concept of providing the RI safety and presents the basic results of the analysis of the most dangerous pre-accidental situations and beyond the design basis accidents, which have been obtained in the process of validating the RI safety. It has been shown that the safety functions concerning the accidental shutdown of the reactor, total blacking out of the NPP and localization of the accidental situation relating to the postulated simultaneous rupture of several steam-generator tubes are not subject to influence of the human factor and are entirely realized in a passive way. (authors)

  5. The Development of a Human Systems Simulation Laboratory at Idaho National Laoboratory: Progress, Requirements and Lessons Learned

    SciTech Connect (OSTI)

    David I Gertman; Katya L. LeBlanc; William phoenix; Alan R Mecham

    2010-11-01

    Next generation nuclear power plants and digital upgrades to the existing nuclear fleet introduce potential human performance issues in the control room. Safe application of new technologies calls for a thorough understanding of how those technologies affect human performance and in turn, plant safety. In support of advancing human factors for small modular reactors and light water reactor sustainability, the Idaho National Laboratory (INL) has developed a reconfigurable simulation laboratory capable of testing human performance in multiple nuclear power plant (NPP) control room simulations. This paper discusses the laboratory infrastructure and capabilities, the laboratory s staffing requirements, lessons learned, and the researchers approach to measuring human performance in the simulation lab.

  6. NSR&D Program Fiscal Year (FY) 2015 Call for Proposals Mitigation of Seismic Risk at Nuclear Facilities using Seismic Isolation

    SciTech Connect (OSTI)

    Coleman, Justin

    2015-02-01

    Seismic isolation (SI) has the potential to drastically reduce seismic response of structures, systems, or components (SSCs) and therefore the risk associated with large seismic events (large seismic event could be defined as the design basis earthquake (DBE) and/or the beyond design basis earthquake (BDBE) depending on the site location). This would correspond to a potential increase in nuclear safety by minimizing the structural response and thus minimizing the risk of material release during large seismic events that have uncertainty associated with their magnitude and frequency. The national consensus standard America Society of Civil Engineers (ASCE) Standard 4, Seismic Analysis of Safety Related Nuclear Structures recently incorporated language and commentary for seismically isolating a large light water reactor or similar large nuclear structure. Some potential benefits of SI are: 1) substantially decoupling the SSC from the earthquake hazard thus decreasing risk of material release during large earthquakes, 2) cost savings for the facility and/or equipment, and 3) applicability to both nuclear (current and next generation) and high hazard non-nuclear facilities. Issue: To date no one has evaluated how the benefit of seismic risk reduction reduces cost to construct a nuclear facility. Objective: Use seismic probabilistic risk assessment (SPRA) to evaluate the reduction in seismic risk and estimate potential cost savings of seismic isolation of a generic nuclear facility. This project would leverage ongoing Idaho National Laboratory (INL) activities that are developing advanced (SPRA) methods using Nonlinear Soil-Structure Interaction (NLSSI) analysis. Technical Approach: The proposed study is intended to obtain an estimate on the reduction in seismic risk and construction cost that might be achieved by seismically isolating a nuclear facility. The nuclear facility is a representative pressurized water reactor building nuclear power plant (NPP) structure

  7. Slide 1

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

    NENE 2014 Conference Presentation: Simulation of the NPP KRSKO Startup Core with CASL Core Simulator, VERA-CS Fausto Franceschini Westinghouse Electric Company LLC Marjan Kromar and Dušan Ćalić Jožef Stefan Institute Andrew T. Godfrey, Benjamin S. Collins, Thomas M. Evans, Jess C. Gehin Oak Ridge National Laboratory September 1, 2014 CASL-U-2014-0183-000 CASL-U-2014-0183-000 Westinghouse Non-Proprietary Class 3 © 2014 Westinghouse Electric Company LLC. All Rights Reserved. 1 Jožef Stefan

  8. Structural Determinants of Nitroxide Motion in Spin-labeled Proteins: Tertiary Contact and Solvent-inaccessible Sties in Helix G of T4 Lysozyme

    SciTech Connect (OSTI)

    Guo,Z.; Cascio, D.; Hideg, K.; Kalai, T.; Hubbell, W.

    2007-01-01

    A nitroxide side chain (R1) has been substituted at single sites along a helix-turn-helix motif in T4 lysozyme (residues 114-135). Together with previously published data, the new sites reported complete a continuous scan through the motif. Mutants with R1 at sites 115 and 118 were selected for crystallographic analysis to identify the structural origins of the corresponding two-component EPR spectra. At 115, R1 is shown to occupy two rotamers in the room temperature crystal structure, one of which has not been previously reported. The two components in the EPR spectrum apparently arise from differential interactions of the two rotamers with the surrounding structure, the most important of which is a hydrophobic interaction of the nitroxide ring. Interestingly, the crystal structure at 100 K reveals a single rotamer, emphasizing the possibility of rotamer selection in low-temperature crystal structures. Residue 118 is at a solvent-inaccessible site in the protein core, and the structure of 118R1, the first reported for the R1 side chain at a buried site, reveals how the side chain is accommodated in an overpacked core.

  9. Radionuclide transport in sandstones with WIPP brine

    SciTech Connect (OSTI)

    Weed, H.C.; Bazan, F.; Fontanilla, J.; Garrison, J.; Rego, J.; Winslow, A.M.

    1981-02-01

    Retardation factors (R) have been measured for the transport of /sup 3/H, /sup 95m/Tc, and /sup 85/Sr in WIPP brine using St. Peter, Berea, Kayenta, and San Felipe sandstone cores. If tritium is assumed to have R=1, /sup 95m/Tc has R=1.0 to 1.3 and therefore is essentially not retarded. Strontium-85 has R = 1.0 to 1.3 on St. Peter, Berea, and Kayenta, but R=3 on San Felipe. This is attributed to sorption on the matrix material of San Felipe, which has 45 volume % matrix compared with 1 to 10 volume % for the others. Retardation factors (R/sub s/) for /sup 85/Sr calculated from static sorption measurements are unity for all the sandstones. Therefore, the static and transport results for /sup 85/Sr disagree in the case of San Felipe, but agree for St. Peter, Berea, and Kayenta.

  10. Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    SciTech Connect (OSTI)

    Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

    2012-08-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

  11. Plant computer applications 'design and implementation tools' set

    SciTech Connect (OSTI)

    Anikanov, S. S.; Stolyetniy, I. V.; Tregubov, M. I.; Guslyakov, O. L.; Gladkov, Y. I.

    2006-07-01

    This paper describes functionality of the application programs' development tool, which is intended to support the full scope of the NPP plant computer applications' design process. The Application Development Tools' Set (ADTS), described in this paper, refers to a set of tools intended to capture functional requirements for applications and support design process from definition of design basis up to final testing of developed applications. There are several tools developed by Westinghouse that facilitate design of application software on different stages of design process. Those are: NAPDT - Nuclear Application Development Tool; SDODT - Simplified Display Object Development Tool; OPAL - Test case execution and documenting tool; The main idea of ADTS is to combine the aforementioned tools into one software environment with other Common out-of-shelf (COT) software to facilitate and expedite NPP plant computer applications. Combination of the software tools included into ADTS satisfies industry requirements for the application software intended for use in the Category B and C systems /2 - 4/. (authors)

  12. Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors

    SciTech Connect (OSTI)

    Hallbert, Bruce P

    2015-01-01

    Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are needed to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nations NPPs.

  13. Back-end of the fuel cycle - Indian scenario

    SciTech Connect (OSTI)

    Wattal, P.K.

    2013-07-01

    Nuclear power has a key role in meeting the energy demands of India. This can be sustained by ensuring robust technology for the back end of the fuel cycle. Considering the modest indigenous resources of U and a huge Th reserve, India has adopted a three stage Nuclear Power Programme (NPP) based on 'closed fuel cycle' approach. This option on 'Recovery and Recycle' serves twin objectives of ensuring adequate supply of nuclear fuel and also reducing the long term radio-toxicity of the wastes. Reprocessing of the spent fuel by Purex process is currently employed. High Level Liquid Waste (HLW) generated during reprocessing is vitrified and undergoes interim storage. Back-end technologies are constantly modified to address waste volume minimization and radio-toxicity reduction. Long-term management of HLW in Indian context would involve partitioning of long lived minor actinides and recovery of valuable fission products specifically cesium. Recovery of minor actinides from HLW and its recycle is highly desirable for the sustained growth of India's NPPs. In this context, programme for developing and deploying partitioning technologies on industrial scale is pursued. The partitioned elements could be either transmuted in Fast Reactors (FRs)/Accelerated Driven Systems (ADS) as an integral part of sustainable Indian NPP. (authors)

  14. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    SciTech Connect (OSTI)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  15. Methodology of Internal Assessment of Uncertainty and Extension to Neutron Kinetics/Thermal-Hydraulics Coupled Codes

    SciTech Connect (OSTI)

    Petruzzi, A.; D'Auria, F.; Giannotti, W.; Ivanov, K.

    2005-02-15

    The best-estimate calculation results from complex system codes are affected by approximations that are unpredictable without the use of computational tools that account for the various sources of uncertainty.The code with (the capability of) internal assessment of uncertainty (CIAU) has been previously proposed by the University of Pisa to realize the integration between a qualified system code and an uncertainty methodology and to supply proper uncertainty bands each time a nuclear power plant (NPP) transient scenario is calculated. The derivation of the methodology and the results achieved by the use of CIAU are discussed to demonstrate the main features and capabilities of the method.In a joint effort between the University of Pisa and The Pennsylvania State University, the CIAU method has been recently extended to evaluate the uncertainty of coupled three-dimensional neutronics/thermal-hydraulics calculations. The result is CIAU-TN. The feasibility of the approach has been demonstrated, and sample results related to the turbine trip transient in the Peach Bottom NPP are shown. Notwithstanding that the full implementation and use of the procedure requires a database of errors not available at the moment, the results give an idea of the errors expected from the present computational tools.

  16. Action-centered display design: Observations and conclusions to HMI by applying digital I and C in main control rooms

    SciTech Connect (OSTI)

    Treier, C.; Zeck, K.; Weich, A.; Schildheuer, R.

    2006-07-01

    With the increasing use of digital I and C systems, the shift personnel in a Nuclear Power Plant (NPP) has the chance to dispose of new supporting methods that influence their actions directly or indirectly. Besides the automation of monitoring and control functions, the task- and problem-oriented increased number of (current state) information in screen based displays is to be mentioned. A few released screen based displays of a German NPP illustrate the influence on the course of action. Therefore the design of displays won't only be determined by the operating mode in future but displays themselves are influencing the operating mode offering both very compact and dynamic information that can directly be used in the operating mode. In order to be able to take these future key functions adequately and early into consideration when designing screen based displays, the development of design instruments like Style Guides with Good Practice methods and construction catalogues both on a company and on an company spanning level is essential: a challenging task for economy and science and also for standardization committees that shall be illustrated in the following report. (authors)

  17. Response Time Test for The Application of the Data Communication Network to Nuclear Power Plant

    SciTech Connect (OSTI)

    Shin, Y.C.; Lee, J.Y.; Park, H.Y.; Seong, S.H.; Chung, H.Y.

    2002-07-01

    This paper discusses the response time test for the application of the Data Communication Network (DCN) to Nuclear Power Plant (NPP). Conventional Instrumentation and Control (I and C) Systems using the analog technology in NPP have raised many problems regarding the lack of spare parts, maintenance burden, inaccuracy, etc.. In order to solve the problems, the Korean Next Generation Reactor (KNGR) I and C system has adopted the digital technology and new design features of using the data communication networks. It is essential to prove the response time requirements that arise from the introduction of digital I and C technology and data communication networks to nuclear power plant design. For the response time test, a high reliable data communication network structure has been developed to meet the requirements of redundancy, diversity, and segmentation. This paper presents the results of network load analysis and response time test for the KNGR DCN prototype. The test has been focused on the response time from the field components to the gateway because the response times from the gateway to the specific systems are similar to those of the existing design. It is verified that the response time requirements are met through the prototype test for KNGR I and C systems. (authors)

  18. Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

    SciTech Connect (OSTI)

    Blanchat, T.K.; Pilch, M.M.; Allen, M.D.

    1997-02-01

    The Surtsey Test Facility is used to perform scaled experiments simulating High Pressure Melt Ejection accidents in a nuclear power plant (NPP). The experiments investigate the effects of direct containment heating (DCH) on the containment load. The results from Zion and Surry experiments can be extrapolated to other Westinghouse plants, but predicted containment loads cannot be generalized to all Combustion Engineering (CE) plants. Five CE plants have melt dispersal flow paths which circumvent the main mitigation of containment compartmentalization in most Westinghouse PWRs. Calvert Cliff-like plant geometries and the impact of codispersed water were addressed as part of the DCH issue resolution. Integral effects tests were performed with a scale model of the Calvert Cliffs NPP inside the Surtsey test vessel. The experiments investigated the effects of codispersal of water, steam, and molten core stimulant materials on DCH loads under prototypic accident conditions and plant configurations. The results indicated that large amounts of coejected water reduced the DCH load by a small amount. Large amounts of debris were dispersed from the cavity to the upper dome (via the annular gap). 22 refs., 84 figs., 30 tabs.

  19. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    SciTech Connect (OSTI)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  20. Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors

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

    Hallbert, Bruce P

    2015-01-01

    Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are neededmore » to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nation’s NPPs.« less

  1. Westinghouse Waste Simulation and Optimization Software Tool - 13493

    SciTech Connect (OSTI)

    Mennicken, Kim [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany); Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)

    2013-07-01

    Radioactive waste is produced during NPP operation and NPP D and D. Different kinds of waste with different volumes and properties have to be treated. Finding a technically and commercially optimized waste treatment concept is a difficult and time consuming process. The Westinghouse waste simulation and optimization software tool is an approach to study the total life cycle cost of any waste management facility. The tool enables the user of the simulation and optimization software to plan processes and storage buildings and to identify bottlenecks in the overall waste management design before starting detailed planning activities. Furthermore, application of the software enables the user to optimize the number of treatment systems, to determine the minimum design capacity for onsite storage facilities, to identify bottlenecks in the overall design and to identify the most cost-effective treatment paths by maintaining optimal waste treatment technologies. In combination with proven waste treatment equipment and integrated waste management solutions, the waste simulation and optimization software provides reliable qualitative results that lead to an effective planning and minimization of the total project planning risk of any waste management activity. (authors)

  2. Use of collaboration software to improve nuclear power plant outage management

    SciTech Connect (OSTI)

    Germain, Shawn

    2015-02-01

    Nuclear Power Plant (NPP) refueling outages create some of the most challenging activities the utilities face in both tracking and coordinating thousands of activities in a short period of time. Other challenges, including nuclear safety concerns arising from atypical system configurations and resource allocation issues, can create delays and schedule overruns, driving up outage costs. Today the majority of the outage communication is done using processes that do not take advantage of advances in modern technologies that enable enhanced communication, collaboration and information sharing. Some of the common practices include: runners that deliver paper-based requests for approval, radios, telephones, desktop computers, daily schedule printouts, and static whiteboards that are used to display information. Many gains have been made to reduce the challenges facing outage coordinators; however; new opportunities can be realized by utilizing modern technological advancements in communication and information tools that can enhance the collective situational awareness of plant personnel leading to improved decision-making. Ongoing research as part of the Light Water Reactor Sustainability Program (LWRS) has been targeting NPP outage improvement. As part of this research, various applications of collaborative software have been demonstrated through pilot project utility partnerships. Collaboration software can be utilized as part of the larger concept of Computer-Supported Cooperative Work (CSCW). Collaborative software can be used for emergent issue resolution, Outage Control Center (OCC) displays, and schedule monitoring. Use of collaboration software enables outage staff and subject matter experts (SMEs) to view and update critical outage information from any location on site or off.

  3. Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors

    SciTech Connect (OSTI)

    Hallbert, Bruce P

    2015-01-01

    Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are needed to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nation’s NPPs.

  4. Progress and Status of the Ignalina Nuclear Power Plant's New Solid Waste Management and Storage Facilities

    SciTech Connect (OSTI)

    Rausch, J.; Henderson, R.W.; Penkov, V.

    2008-07-01

    A considerable amount of dry radioactive waste from former NPP operation has accumulated up to date and is presently stored at the Ignalina NPP site, Lithuania. Current storage capacities are nearly exhausted and more waste is to come from future decommissioning of the two RMBKtype reactors. Additionally, the existing storage facilities does not comply to the state-of-the-art technology for handling and storage of radioactive waste. In 2005, INPP faced this situation of a need for waste processing and subsequent interim storage of these wastes by contracting NUKEM with the design, construction, installation and commissioning of new waste management and storage facilities. The subject of this paper is to describe the scope and the status of the new solid waste management and storage facilities at the Ignalina Nuclear Power Plant. In summary: The turnkey contract for the design, supply and commission of the SWMSF was awarded in December 2005. The realisation of the project was initially planned within 48 month. The basic design was finished in August 2007 and the Technical Design Documentation and Preliminary Safety Analyses Report was provided to Authorities in October 2007. The construction license is expected in July 2008. The procurement phase was started in August 2007, start of onsite activities is expected in November 2007. The start of operation of the SWMSF is scheduled for end of 2009. (authors)

  5. Seismic Data Gathering and Validation

    SciTech Connect (OSTI)

    Coleman, Justin

    2015-02-01

    Three recent earthquakes in the last seven years have exceeded their design basis earthquake values (so it is implied that damage to SSC’s should have occurred). These seismic events were recorded at North Anna (August 2011, detailed information provided in [Virginia Electric and Power Company Memo]), Fukushima Daichii and Daini (March 2011 [TEPCO 1]), and Kaswazaki-Kariwa (2007, [TEPCO 2]). However, seismic walk downs at some of these plants indicate that very little damage occurred to safety class systems and components due to the seismic motion. This report presents seismic data gathered for two of the three events mentioned above and recommends a path for using that data for two purposes. One purpose is to determine what margins exist in current industry standard seismic soil-structure interaction (SSI) tools. The second purpose is the use the data to validated seismic site response tools and SSI tools. The gathered data represents free field soil and in-structure acceleration time histories data. Gathered data also includes elastic and dynamic soil properties and structural drawings. Gathering data and comparing with existing models has potential to identify areas of uncertainty that should be removed from current seismic analysis and SPRA approaches. Removing uncertainty (to the extent possible) from SPRA’s will allow NPP owners to make decisions on where to reduce risk. Once a realistic understanding of seismic response is established for a nuclear power plant (NPP) then decisions on needed protective measures, such as SI, can be made.

  6. Synergistic Smart Fuel For In-pile Nuclear Reactor Measurements

    SciTech Connect (OSTI)

    James A. Smith; Dale K. Kotter; Randall A. Ali; Steven L . Garrett

    2013-10-01

    In March 2011, an earthquake of magnitude 9.0 on the Richter scale struck Japan with its epicenter on the northeast coast, near the Tohoku region. In addition to the immense physical destruction and casualties across the country, several nuclear power plants (NPP) were affected. It was the Fukushima Daiichi NPP that experienced the most severe and irreversible damage. The earthquake brought the reactors at Fukushima to an automatic shutdown and because the power transmission lines were damaged, emergency diesel generators (EDGs) were activated to ensure that there was continued cooling of the reactors and spent fuel pools. The situation was being successfully managed until the tsunami hit about forty-five minutes later with a maximum wave height of approximately 15 m. The influx of water submerged the EDGs, the electrical switchgear, and dc batteries, resulting in the total loss of power to the reactors.2 At this point, the situation became critical. There was a loss of the sensors and instrumentation within the reactor that could have provided valuable information to guide the operators to make informed decisions and avoid the unfortunate events that followed. In the light of these events, we have developed and tested a potential self-powered thermoacoustic system, which will have the ability to serve as a temperature sensor and can transmit data independently of electronic networks. Such a device is synergistic with the harsh environment of the nuclear reactor as it utilizes the heat from the nuclear fuel to provide the input power.

  7. Embedded Sensors and Controls to Improve Component Performance and Reliability Conceptual Design Report

    SciTech Connect (OSTI)

    Kisner, R.; Melin, A.; Burress, T.; Fugate, D.; Holcomb, D.; Wilgen, J.; Miller, J.; Wilson, D.; Silva, P.; Whitlow, L.; Peretz, F.

    2012-09-15

    The objective of this project is to demonstrate improved reliability and increased performance made possible by deeply embedding instrumentation and controls (I&C) in nuclear power plant (NPP) components and systems. The project is employing a highly instrumented canned rotor, magnetic bearing, fluoride salt pump as its I&C technology demonstration platform. I&C is intimately part of the basic millisecond-by-millisecond functioning of the system; treating I&C as an integral part of the system design is innovative and will allow significant improvement in capabilities and performance. As systems become more complex and greater performance is required, traditional I&C design techniques become inadequate and more advanced I&C needs to be applied. New I&C techniques enable optimal and reliable performance and tolerance of noise and uncertainties in the system rather than merely monitoring quasistable performance. Traditionally, I&C has been incorporated in NPP components after the design is nearly complete; adequate performance was obtained through over-design. By incorporating I&C at the beginning of the design phase, the control system can provide superior performance and reliability and enable designs that are otherwise impossible. This report describes the progress and status of the project and provides a conceptual design overview for the platform to demonstrate the performance and reliability improvements enabled by advanced embedded I&C.

  8. Science Plan Biogenic Aerosols – Effects on Clouds and Climate (BAECC)

    SciTech Connect (OSTI)

    Petäjä, T

    2013-12-01

    Atmospheric aerosol particles impact human health in urban environments, while on regional and global scales they can affect climate patterns, the hydrological cycle, and the intensity of radiation that reaches the Earth’s surface. In spite of recent advances in the understanding of aerosol formation processes and the links between aerosol dynamics and biosphere-atmosphere-climate interactions, great challenges remain in the analysis of related processes on a global scale. Boreal forests, situated in a circumpolar belt in the northern latitudes throughout the United States, Canada, Russia and Scandinavia, are among the most active areas of atmospheric aerosol formation among all biomes. The formation of aerosol particles and their growth to the sizes of cloud condensation nuclei in these areas are associated with biogenic volatile organic emissions from vegetation and soil.

  9. Production of extremely low volatile organic compounds from biogenic emissions: Measured yields and atmospheric implications

    SciTech Connect (OSTI)

    Jokinen, Tuija; Berndt, Torsten; Makkonen, Risto; Kerminen, Veli-Matti; Junninen, Heikki; Paasonen, Pauli; Stratmann, Frank; Herrmann, Hartmut; Guenther, Alex B.; Worsnop, Douglas R.; Kulmala, M.; Ehn, Mikael K.; Sipila, Mikko

    2015-06-09

    Extremely low volatility organic compounds (ELVOC) are suggested to promote aerosol particle formation and cloud condensation nuclei (CCN) production in the atmosphere. We show that the capability of biogenic VOC (BVOC) to produce ELVOC depends strongly on their chemical structure and relative oxidant levels. BVOC with an endocyclic double bond, representative emissions from, e.g., boreal forests, efficiently produce ELVOC from ozonolysis. Compounds with exocyclic double bonds or acyclic compounds including isoprene, emission representative of the tropics, produce minor quantities of ELVOC, and the role of OH radical oxidation is relatively larger. Implementing these findings into a global modeling framework shows that detailed assessment of ELVOC production pathways is crucial for understanding biogenic secondary organic aerosol and atmospheric CCN formation.

  10. Observing terrestrial ecosystems and the carbon cycle from space

    SciTech Connect (OSTI)

    Schimel, David; Pavlick, Ryan; Fisher, Joshua B.; Asner, Gregory P.; Saatchi, Sassan; Townsend, Philip; Miller, Charles E.; Frankenberg, Christian; Hibbard, Kathleen A.; Cox, Peter

    2015-02-06

    Modeled terrestrial ecosystem and carbon cycle feedbacks contribute substantial uncertainty to projections of future climate. The limitations of current observing networks contribute to this uncertainty. Here we present a current climatology of global model predictions and observations for photosynthesis, biomass, plant diversity and plant functional diversity. Carbon cycle tipping points occur in terrestrial regions where fluxes or stocks are largest, and where biological variability is highest, the tropics and Arctic/Boreal zones. Global observations are predominately in the mid-latitudes and are sparse in high and low latitude ecosystems. Observing and forecasting ecosystem change requires sustained observations of sufficient density in time and space in critical regions. Using data and theory available now, we can develop a strategy to detect and forecast terrestrial carbon cycle-climate interactions, by combining in situ and remote techniques.

  11. The plant cell wall decomposing machinery underlies the functional diversity of forest fungi

    SciTech Connect (OSTI)

    Eastwood, Daniel C.; Floudas, Dimitrios; Binder, Manfred; Majcherczyk, Andrzej; Schneider, Patrick; Aerts, Andrea; Asiegbu, Fred O.; Baker, Scott E.; Barry, Kerrie; Bendiksby, Mika; Blumentritt, Melanie; Coutinho, Pedro M.; Cullen, Dan; Vries, Ronald P. de; Gathman, Allen; Goodell, Barry; Henrissat, Bernard; Ihrmark, Katarina; Kauserud, Hä; vard,; Kohler, Annegret; LaButti, Kurt; Lapidus, Alla; Lavin, José; L.; Lee, Yong-Hwan; Lindquist, Erika; Lilly, Walt; Lucas, Susan; Morin, Emmanuelle; Murat, Claude; Oguiza, José; A.; Park, Jongsun; Pisabarro, Antonio G.; Riley, Robert; Rosling, Anna; Salamov, Asaf; Schmidt, Olaf; Schmutz, Jeremy; Skrede, Inger; Stenlid, Jan; Wiebenga, Ad; Xie, Xinfeng; Kü; es, Ursula; Hibbett, David S.; Hoffmeister, Dirk; Hö; gberg, Nils; Martin, Francis; Grigoriev, Igor V.; Watkinson, Sarah C.

    2011-05-01

    Brown rot decay removes cellulose and hemicellulose from wood?residual lignin contributing up to 30percent of forest soil carbon?and is derived from an ancestral white rot saprotrophy in which both lignin and cellulose are decomposed. Comparative and functional genomics of the ?dry rot? fungus Serpula lacrymans, derived from forest ancestors, demonstrated that the evolution of both ectomycorrhizal biotrophy and brown rot saprotrophy were accompanied by reductions and losses in specific protein families, suggesting adaptation to an intercellular interaction with plant tissue. Transcriptome and proteome analysis also identified differences in wood decomposition in S. lacrymans relative to the brown rot Postia placenta. Furthermore, fungal nutritional mode diversification suggests that the boreal forest biome originated via genetic coevolution of above- and below-ground biota

  12. The sensitivity of the terrestrial biosphere to climatic change: A simulation of the middle Holocene

    SciTech Connect (OSTI)

    Foley, J.A.

    1994-12-01

    A process-based ecosystem model, DEMETER, is used to simulate the sensitivity of the terrestrial biosphere to changes in climate. In this study, DEMETER is applied to the two following climatic regimes: (1) the modern observed climate and (2) a simulated mid-Holocene climate (6000 years before present). The mid-Holocene climate is simulated using the GENESIS global climate model, where shifts in the Earth`s orbital parameters result in warmer northern continents and enhanced monsoons in Asia, North Africa, and North America. DEMETER simulates large differences between modern and mid-Holocene vegetation cover: (1) mid-Holocene boreal forests extend farther poleward than present in much of Europe, Asia, and North America, and (2) mid-Holocene North African grasslands extend substantially farther north than present. The simulated patterns of mid-Holocene vegetation are consistent with many features of the paleobotanical record. Simulated mid-Holocene global net primary productivity is approximately 3% larger than present, largely due to the increase of boreal forest and tropical grasslands relative to tundra and desert. Global vegetation carbon is higher at 6 kyr B.P. compared to present by roughly the same amount (4%). Mid-Holocene global litter carbon is larger than present by 10%, while global soil carbon is approximately 1% less. Despite the regional changes in productivity and carbon storage the simulated total carbon storage potential of the terrestrial biosphere (not including changes in peat) does not change significantly between the two simulations. 53 refs., 12 figs., 4 tabs.

  13. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Lewicki, J P (4) Harley, S J (2) Hok, S (2) Leif, R N (2) Maiti, A (2) Valdez, C A (2) Vu, A K (2) Williams, A M (2) Albo, R (1) Albo, R F (1) Alviso, C T (1) Chinn, S. C. (1) ...

  14. I

    Office of Legacy Management (LM)

    Mk "3 . . * . T&,TTSTT: .: -53i&i-:r 1: c r I * .I " : , ; . . . 3. .i - w ... ;'A0 U.S. .' .LJf& Er++r;;;- LI3zL?.i w ' Lsriz Qcr&N.3 k:":' i Iiealth and Safety ...

  15. ENVIROX4ENTA.L MONITORING REPORT FOR THE BEVADA TEST S I T E

    Office of Legacy Management (LM)

    ENVIROX4ENTA.L MONITORING REPORT FOR THE BEVADA TEST S I T E AND OTHER TEST AREAS USED FOR LFqDERGROL'ND :iUCLEAR DETONATIONS J a n u a r y t h r o u g h D e c e m b e r 1 9 7 3 by ...

  16. Electric current-producing device having sulfone-based electrolyte

    DOE Patents [OSTI]

    Angell, Charles Austen; Sun, Xiao-Guang

    2010-11-16

    Electrolytic solvents and applications of such solvents including electric current-producing devices. For example, a solvent can include a sulfone compound of R1--SO2--R2, with R1 being an alkyl group and R2 a partially oxygenated alkyl group, to exhibit high chemical and thermal stability and high oxidation resistance. For another example, a battery can include, between an anode and a cathode, an electrolyte which includes ionic electrolyte salts and a non-aqueous electrolyte solvent which includes a non-symmetrical, non-cyclic sulfone. The sulfone has a formula of R1--SO2--R2, wherein R1 is a linear or branched alkyl or partially or fully fluorinated linear or branched alkyl group having 1 to 7 carbon atoms, and R2 is a linear or branched or partially or fully fluorinated linear or branched oxygen containing alkyl group having 1 to 7 carbon atoms. The electrolyte can include an electrolyte co-solvent and an electrolyte additive for protective layer formation.

  17. The

    Office of Scientific and Technical Information (OSTI)

    ... To prove this, note that the electromagnetic tensor for L,R is F L,R 1 2 (F ... Here igB n n * iD c , iD c is the collinear gluon field tensor; for the ...

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    Office of Scientific and Technical Information (OSTI)

    ... Ashmore, M (3) Finnie, J A (3) Worsley, M A (3) Alviso, C T (2) Chinn, S C (2) Mason, H E (2) Pielichowski, K (2) Albo, R (1) Baumann, T F (1) Beavis, P W (1) Bell, C (1) Eastwood, ...

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    ... Binns, W.R. (1) Chen, C. (1) Chen, P. (1) Clem, J.M. (1) Connolly, A. (1) Dowkontt, P.F. (1) DuVernois, M.A. (1) Field, R.C. (1) Goldstein, D. (1) Gorham, P.W. (1) Grashorn, E. (1) ...

  20. FINAL REPORT VELA UNIFORM PROJECT SPONSORED BY THE ADVANCED RESEARCH...

    Office of Legacy Management (LM)

    ... U S A r m y Raymond Moore, MD Donald Smith, DVM USPHS, Medical Officer USPHS, V e t e ... Ranch 2 1 Schur z 0709 - - - 2 1 3 4 2 Seyler R e s e r v o i r 1 1 Smith C r e e k Ranch ...

  1. Adsorption study for uranium in Rocky Flats groundwater

    SciTech Connect (OSTI)

    Laul, J.C.; Rupert, M.C.; Harris, M.J.; Duran, A.

    1995-01-01

    Six adsorbents were studied to determine their effectiveness in removing uranium in Rocky Flats groundwater. The bench column and batch (Kd) tests showed that uranium can be removed (>99.9%) by four adsorbents. Bone Charcoal (R1O22); F-1 Alumina (granular activated alumina); BIOFIX (immobilized biological agent); SOPBPLUS (mixed metal oxide); Filtrasorb 300 (granular activated carbon); and Zeolite (clinoptilolite).

  2. Characterization of a panel of somatic cell hybrids for regional mapping of the mouse X chromosome

    SciTech Connect (OSTI)

    Avner, P.; Arnaud, D.; Amar, L.; Cambrou, J.; Winking, H.; Russell, L.B.

    1987-08-01

    A panel of five hybrid cell lines containing mouse X chromosomes with various deletions has been obtained by fusing splenocytes from male mice carrying one of a series of reciprocal X-autosome translocations with the azaguanine-resistant Chinese hamster cell line CH3g. These hybrids have been extensively characterized by using the allozymes hypoxanthine/guanine phosphoribosyltransferase (encoded by the Hprt locus) and ..cap alpha..-galactosidase (Ags) and a series of 11 X-chromosome-specific DNA probes whose localization had been previously established by linkage studies. Such studies have established the genetic breakpoints of the T(X;12)13R1 and T(X;2)14R1 X-autosome translocations on the X chromosome and provided additional information as to the X-chromosome genetic breakpoints of the T(X;16)16H, T(X;4)7R1, and T(X;7)6R1 translocations. The data establish clearly that both the T(X;7)5RI and T(X;12)13R1 X-chromosome breakpoints are proximal to Hprt, the breakpoint of the former being more centromeric, lying as it does in the 9-centimorgan interval between the ornithine transcarbamoylase (Otc) and DXPas7 (M2C) loci. These five hybrid cell lines provide, with the previously characterized EBS4 hybrid cell line, a nested series of seven mapping intervals distributed along the length of the mouse X chromosome. Their characterization not only allows further correlation of the genetic and cytological X-chromosome maps but also should permit the rapid identification of DNA probes specific for particular regions of the mouse X chromosome.

  3. Comparison of Global Model Results from the Carbon-Land Model Intercomparison Project (C-LAMP) with Free-Air Carbon Dioxide Enrichment (FACE) Manipulation Experiments

    SciTech Connect (OSTI)

    Hoffman, Forrest M; Randerson, Jim; Fung, Inez; Thornton, Peter E; Covey, Curtis; Bonan, Gordon; Running, Steven; Norby, Richard J

    2008-01-01

    Free-Air CO{sub 2} Enrichment (FACE) manipulation experiments have been carried out at a handful of sites to gauge the response of the biosphere to significant increases in atmospheric [CO{sub 2}]. Early synthesis results from four temperate forest sites suggest that the response of net primary productivity (NPP) is conserved across a broad range of productivity with a stimulation at the median of 23 {+-} 2% when the surrounding air [CO{sub 2}] was raised to 550{approx}ppm. As a part of the Carbon-Land Model Intercomparison Project (C-LAMP), a community-based model-data comparison activity, the authors have performed a global FACE modeling experiment using two terrestrial biogeochemistry modules, CLM3-CASA and CLM3-CN, coupled to the National Center for Atmospheric Research (NCAR) Community Climate System Model (CCSM). The two models were forced with an improved NCEP/NCAR reanalysis data set and reconstructed atmospheric [CO{sub 2}] and N deposition data through 1997. At the beginning of 1997 in the transient simulations, global atmospheric [CO{sub 2}] was abruptly raised to 550{approx}ppm, the target value used at the FACE sites. In the control runs, [CO{sub 2}] continued to rise following observations until 2004, after which it was held constant out to year 2100. In both simulations, the last 25 years of reanalysis forcing and a constant N deposition were applied after year 2004. Across all forest biomes, the NPP responses from both models are weaker than those reported for the four FACE sites. Moreover, model responses vary widely geographically with a decreasing trend of NPP increases from 40{sup o}N to 70{sup o}N. For CLM3-CASA, the largest responses occur in arid regions of western North America and central Asia, suggesting that responses are most strongly influenced by increased water use efficiency for this model. CLM3-CN exhibits consistently weaker responses than CLM3-CASA' with the strongest responses in central Asia, but significantly constrained by N

  4. Qualitative and Quantitative Assessment of Nuclear Materials Contained in High-Activity Waste Arising from the Operations at the 'SHELTER' Facility

    SciTech Connect (OSTI)

    Cherkas, Dmytro

    2011-10-01

    As a result of the nuclear accident at the Chernobyl NPP in 1986, the explosion dispeesed nuclear materials contained in the nuclear fuel of the reactor core over the destroyed facilities at Unit No. 4 and over the territory immediately adjacent to the destroyed unit. The debris was buried under the Cascade Wall. Nuclear materials at the SHELTER can be characterized as spent nuclear fuel, fresh fuel assemblies (including fuel assemblies with damaged geometry and integrity, and individual fuel elements), core fragments of the Chernobyl NPP Unit No. 4, finely-dispersed fuel (powder/dust), uranium and plutonium compounds in water solutions, and lava-like nuclear fuel-containing masses. The new safe confinement (NSC) is a facility designed to enclose the Chernobyl NPP Unit No. 4 destroyed by the accident. Construction of the NSC involves excavating operations, which are continuously monitored including for the level of radiation. The findings of such monitoring at the SHELTER site will allow us to characterize the recovered radioactive waste. When a process material categorized as high activity waste (HAW) is detected the following HLW management operations should be involved: HLW collection; HLW fragmentation (if appropriate); loading HAW into the primary package KT-0.2; loading the primary package filled with HAW into the transportation cask KTZV-0.2; and storing the cask in temporary storage facilities for high-level solid waste. The CDAS system is a system of 3He tubes for neutron coincidence counting, and is designed to measure the percentage ratio of specific nuclear materials in a 200-liter drum containing nuclear material intermixed with a matrix. The CDAS consists of panels with helium counter tubes and a polyethylene moderator. The panels are configured to allow one to position a waste-containing drum and a drum manipulator. The system operates on the ‘add a source’ basis using a small Cf-252 source to identify irregularities in the matrix during an assay

  5. RELAP5-3D Code Application for RBMK-1500 Reactor Core Analysis

    SciTech Connect (OSTI)

    Bubelis, Evaldas; Kaliatka, Algirdas; Uspuras, Eugenijus

    2002-07-01

    The paper presents an evaluation of RELAP5-3D code suitability to model specific transients that take place during RBMK-1500 reactor operation, where the neutronic response of the core is important. A successful best estimate RELAP5-3D model of the Ignalina NPP RBMK-1500 reactor has been developed and validated against real plant data. Certain RELAP5-3D transient calculation results were benchmarked against calculation results obtained using the Russian code STEPAN, specially designed for RBMK reactor analysis. Comparison of the results obtained, using the RELAP5-3D and STEPAN codes, showed quite good mutual coincidence of the calculation results and good agreement with real plant data. (authors)

  6. Seismic fragility evaluation of a piping system in a nuclear power plant by shaking table test and numerical analysis

    SciTech Connect (OSTI)

    Kim, M. K.; Kim, J. H.; Choi, I. K.

    2012-07-01

    In this study, a seismic fragility evaluation of the piping system in a nuclear power plant was performed. For the evaluation of seismic fragility of the piping system, this research was progressed as three steps. At first, several piping element capacity tests were performed. The monotonic and cyclic loading tests were conducted under the same internal pressure level of actual nuclear power plants to evaluate the performance. The cracks and wall thinning were considered as degradation factors of the piping system. Second, a shaking tale test was performed for an evaluation of seismic capacity of a selected piping system. The multi-support seismic excitation was performed for the considering a difference of an elevation of support. Finally, a numerical analysis was performed for the assessment of seismic fragility of piping system. As a result, a seismic fragility for piping system of NPP in Korea by using a shaking table test and numerical analysis. (authors)

  7. Technical Exchange on Improved Design and Performance of High Level Waste Melters - Final Report

    SciTech Connect (OSTI)

    SK Sundaram; ML Elliott; D Bickford

    1999-11-19

    SIA Radon is responsible for management of low- and intermediate-level radioactive waste (LILW) produced in Central Russia. In cooperation with Minatom organizations Radon carries out R and D programs on treatment of simulated high level waste (HLW) as well. Radon scientists deal with a study of materials for LILW, HLW, and Nuclear Power Plants (NPP) wastes immobilization, and development and testing of processes and technologies for waste treatment and disposal. Radon is mostly experienced in LILW vitrification. This experience can be carried over to HLW vitrification especially in field of melting systems. The melter chosen as a basic unit for the vitrification plant is a cold crucible. Later on Radon experience in LILW vitrification as well as our results on simulated HLW vitrification are briefly described.

  8. Using Phased Array Ultrasonic Testing in Lieu of Radiography for Acceptance of Carbon Steel Piping Welds

    SciTech Connect (OSTI)

    Moran, Traci L.; Anderson, Michael T.; Cinson, Anthony D.; Crawford, Susan L.; Nove, Carol A.

    2014-08-01

    The Pacific Northwest National Laboratory (PNNL) is conducting studies for the U.S. Nuclear Regulatory Commission (NRC) to assess the capability, effectiveness, and reliability of ultrasonic testing (UT) as a replacement method for radiographic testing (RT) for volumetric examination of nuclear power plant (NPP) components. This particular study focused on evaluating the use of UT on carbon steel plate welds. Welding fabrication flaws included a combination of planar and volumetric types, e.g., incomplete fusion, lack of penetration, cracks, porosity, and slag inclusions. The examinations were conducted using phased-array (PA) UT techniques applied primarily for detection and flaw type characterization. This paper will discuss the results of using UT in lieu of RT for detection and classification of fabrication flaws in carbon steel plate welds.

  9. Effect of emitter parameter variation on the performance of heteroepitaxial indium phosphide solar cells

    SciTech Connect (OSTI)

    Jain, R.K.; Flood, D.J.

    1990-12-01

    Metallorganic chemical-vapor-deposited heteroepitaxial indium phosphide (InP) solar cell experimental results were simulated by using a PC-1D computer model. The effect of emitter parameter variation on the performance of n(+)/p/p(+) heteroepitaxial InP/GaAs solar cell was presented. The thinner and lighter doped emitters were observed to offer higher cell efficiencies. The influence of emitter thickness and minority carrier diffusion length on the cell efficiency with respect to dislocation density was studied. Heteroepitaxial cells with efficiencies similar to present day homojunction InP efficiencies (greater than 16 percent AMO) were shown to be attainable if a dislocation density lower than 10(exp 6)/sq cm could be achieved. A realistic optimized design study yielded InP solar cells of over 22 percent AMO efficiency at 25 C.

  10. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect (OSTI)

    Naus, Dan J

    2014-01-01

    Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  11. Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report

    SciTech Connect (OSTI)

    Swain, A D; Guttmann, H E

    1983-08-01

    The primary purpose of the Handbook is to present methods, models, and estimated human error probabilities (HEPs) to enable qualified analysts to make quantitative or qualitative assessments of occurrences of human errors in nuclear power plants (NPPs) that affect the availability or operational reliability of engineered safety features and components. The Handbook is intended to provide much of the modeling and information necessary for the performance of human reliability analysis (HRA) as a part of probabilistic risk assessment (PRA) of NPPs. Although not a design guide, a second purpose of the Handbook is to enable the user to recognize error-likely equipment design, plant policies and practices, written procedures, and other human factors problems so that improvements can be considered. The Handbook provides the methodology to identify and quantify the potential for human error in NPP tasks.

  12. Nondestructive Evaluation of Thick Concrete Using Advanced Signal Processing Techniques

    SciTech Connect (OSTI)

    Clayton, Dwight A; Barker, Alan M; Santos-Villalobos, Hector J; Albright, Austin P; Hoegh, Kyle; Khazanovich, Lev

    2015-09-01

    The purpose of the U.S. Department of Energy Office of Nuclear Energy’s Light Water Reactor Sustainability (LWRS) Program is to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the operating lifetimes of nuclear power plants (NPPs) beyond 60 years [1]. Since many important safety structures in an NPP are constructed of concrete, inspection techniques must be developed and tested to evaluate the internal condition. In-service containment structures generally do not allow for the destructive measures necessary to validate the accuracy of these inspection techniques. This creates a need for comparative testing of the various nondestructive evaluation (NDE) measurement techniques on concrete specimens with known material properties, voids, internal microstructure flaws, and reinforcement locations.

  13. Development of a new flux map processing code for moveable detector system in PWR

    SciTech Connect (OSTI)

    Li, W.; Lu, H.; Li, J.; Dang, Z.; Zhang, X.

    2013-07-01

    This paper presents an introduction to the development of the flux map processing code MAPLE developed by China Nuclear Power Technology Research Institute (CNPPJ), China Guangdong Nuclear Power Group (CGN). The method to get the three-dimensional 'measured' power distribution according to measurement signal has also been described. Three methods, namely, Weight Coefficient Method (WCM), Polynomial Expand Method (PEM) and Thin Plane Spline (TPS) method, have been applied to fit the deviation between measured and predicted results for two-dimensional radial plane. The measured flux map data of the LINGAO nuclear power plant (NPP) is processed using MAPLE as a test case to compare the effectiveness of the three methods, combined with a 3D neutronics code COCO. Assembly power distribution results show that MAPLE results are reasonable and satisfied. More verification and validation of the MAPLE code will be carried out in future. (authors)

  14. ENVIRONMENTAL RADIATION MONITORING IN THE CHERNOBYL EXCLUSION ZONE - HISTORY AND RESULTS 25 YEARS AFTER

    SciTech Connect (OSTI)

    Farfan, E.; Jannik, T.

    2011-10-01

    This article describes results of the radiation environmental monitoring performed in the Chernobyl Exclusion Zone (ChEZ) during the period following the 1986 Chernobyl Nuclear Power Plant accident. This article presents a brief overview of five comprehensive reports generated under Contract No. DE-AC09-96SR18500 (Washington Savannah River Company LLC, Subcontract No. AC55559N, SOW No. ON8778) and summarizes characteristics of the ChEZ and its post-accident status and the history of development of the radiation monitoring research in the ChEZ is described. This article addresses characteristics of the radiation monitoring in the ChEZ, its major goals and objectives, and changes of these goals and objectives in the course of time, depending on the tasks associated with the phase of mitigation of the ChNPP accident consequences. The results of the radiation monitoring in the ChEZ during the last 25 years are also provided.

  15. A creep-damage model for mesoscale simulations of concrete expansion-degradation phenomena

    SciTech Connect (OSTI)

    Giorla, Alain B; Le Pape, Yann

    2015-01-01

    Long-term performance of aging concrete in nuclear power plants (NPPs) requires a careful examination of the physical phenomena taking place in the material. Concrete under high neutron irradiation is subjected to large irreversible deformations as well as mechanical damage, caused by a swelling of the aggregates. However, these results, generally obtained in accelerated conditions in test reactors, cannot be directly applied to NPP irradiated structures, i.e., the biological shield, operating conditions due to difference in time scale and environmental conditions (temperature, humidity). Mesoscale numerical simulations are performed to separate the underlying mechanisms and their interactions. The cement paste creep-damage model accounts for the effect of the loading rate on the apparent damage properties of the material and uses an event-based approach to capture the competition between creep and damage. The model is applied to the simulation of irradiation experiments from the literature and shows a good agreement with the experimental data.

  16. Periodic Verification of the Scaling Factor for Radwastes in Korean NPPs - 13294

    SciTech Connect (OSTI)

    Park, Yong Joon; Ahn, Hong Joo; Song, Byoung Chul; Song, Kyuseok

    2013-07-01

    According to the acceptance criteria for a low and intermediate level radioactive waste (LILW) listed in Notice No. 2012-53 of the Nuclear Safety and Security Commission (NSSC), specific concentrations of radionuclides inside a drum has to be identified and quantified. In 5 years of effort, scaling factors were derived through destructive radiochemical analysis, and the dry active waste, spent resin, concentration bottom, spent filter, and sludge drums generated during 2004 ? 2008 were evaluated to identify radionuclide inventories. Eventually, only dry active waste among LILWs generated from Korean NPPs were first shipped to a permanent disposal facility on December 2010. For the LILWs generated after 2009, the radionuclides are being radiochemically quantified because the Notice clarifies that the certifications of the scaling factors should be verified biennially. During the operation of NPP, the radionuclides designated in the Notice are formed by neutron activation of primary coolant, reactor structural materials, corrosion products, and fission products released into primary coolant through defects or failures in fuel cladding. Eventually, since the radionuclides released into primary coolant are transported into the numerous auxiliary and support systems connected to primary system, the LILWs can be contaminated, and the radionuclides can have various concentration distributions. Thus, radioactive wastes, such as spent resin and dry active waste generated at various Korean NPP sites, were sampled at each site, and the activities of the regulated radionuclides present in the sample were determined using radiochemical methods. The scaling factors were driven on the basis of the activity ratios between a or ?-emitting nuclides and ?-emitting nuclides. The resulting concentrations were directly compared with the established scaling factors' data using statistical methods. In conclusions, the established scaling factors were verified with a reliability of within

  17. Lessons Learned from Raw Treatment in the Slovak Republic - Minimization for Final Disposal

    SciTech Connect (OSTI)

    Hanusik, V.; Hladky, E.; Krajc, T.; Pekar, A.; Stubna, M.; Urbanec, M. [Milan Zatkulak, VUJE, a.s., Trnava (Slovakia); Ehn, L.; Kover, M.; Remias, V.; Slezak, M. [JAVYS, a.s., Bohunice (Slovakia)

    2008-07-01

    This paper is referring about the utilization of technologies for the treatment and conditioning of low and intermediate level RAW from operation and decommissioning of nuclear facilities in Slovakia. This experience represents more than 116 reactor years of NPP operation, mainly of NPPs equipped with VVER 440 reactors, 30 years of decommissioning activities, 27 years of development and operation of technologies for the treatment and conditioning of RAW and 7 years of LLW and ILW final repository operation. These technologies are located in two localities: Jaslovske Bohunice and Mochovce. The complex treatment and conditioning center (cementation, bituminization, incineration, vitrification, fragmentation and compacting) for almost all types of radioactive waste is located in Jaslovske Bohunice NPP site. The treatment and conditioning center for liquid radioactive waste (cementation and bituminization) and the surface type repository for LLW and ILW final disposal are located in Mochovce area. The treated waste forms are disposed to repository in cubical Fiber Reinforced Concrete (FRC) containers. The experience from the phase of technology development and the phase of technology modifications for various types of RAW, the experience from long term operation of technologies and the experience from transportation of original and packed wastes are described in this paper. The method of optimally combined technology utilization in order to maximize the radionuclide inventory at the same time with respect of disposal safety limitations of repository is described, too. The significant RAW volume reduction for final disposal was achieved through mediation of the combination of treatment and conditioning technologies. The disposal of treated RAW in cubic FRC containers allowed the optimal utilization of volume and radiological capacity of LLW and ILW repository in Mochovce and the fulfillment of determined safety requirements at the same time. (authors)

  18. Ecosystem carbon storage capacity as affected by disturbance regimes: A general theoretical model

    SciTech Connect (OSTI)

    Weng, Ensheng; Luo, Yiqi; Wang, Weile; Wang, Han; Hayes, Daniel J; McGuire, A. David; Hastings, Alan; Schimel, David

    2012-01-01

    Disturbances have been recognized as a key factor shaping terrestrial ecosystem states and dynamics. A general model that quantitatively describes the relationship between carbon storage and disturbance regime is critical for better understanding large scale terrestrial ecosystem carbon dynamics. We developed a model (REGIME) to quantify ecosystem carbon storage capacities (E[x]) under varying disturbance regimes with an analytical solution E[x] = U {center_dot} {tau}{sub E} {center_dot} {lambda}{lambda} + s {tau} 1, where U is ecosystem carbon influx, {tau}{sub E} is ecosystem carbon residence time, and {tau}{sub 1} is the residence time of the carbon pool affected by disturbances (biomass pool in this study). The disturbance regime is characterized by the mean disturbance interval ({lambda}) and the mean disturbance severity (s). It is a Michaelis-Menten-type equation illustrating the saturation of carbon content with mean disturbance interval. This model analytically integrates the deterministic ecosystem carbon processes with stochastic disturbance events to reveal a general pattern of terrestrial carbon dynamics at large scales. The model allows us to get a sense of the sensitivity of ecosystems to future environmental changes just by a few calculations. According to the REGIME model, for example, approximately 1.8 Pg C will be lost in the high-latitude regions of North America (>45{sup o} N) if fire disturbance intensity increases around 5.7 time the current intensity to the end of the twenty-first century, which will require around 12% increases in net primary productivity (NPP) to maintain stable carbon stocks. If the residence time decreased 10% at the same time additional 12.5% increases in NPP are required to keep current C stocks. The REGIME model also lays the foundation for analytically modeling the interactions between deterministic biogeochemical processes and stochastic disturbance events.

  19. Biogenic carbon fluxes from global agricultural production and consumption

    SciTech Connect (OSTI)

    Wolf, Julie; West, Tristram O.; Le Page, Yannick LB; Kyle, G. Page; Zhang, Xuesong; Collatz, George; Imhoff, Marc L.

    2015-10-01

    Quantification of biogenic carbon fluxes from agricultural lands is needed to generate comprehensive bottom-up estimates of net carbon exchange for global and regional carbon monitoring. We estimated global agricultural carbon fluxes associated with annual crop net primary production (NPP), harvested biomass, and consumption of biomass by humans and livestock. These estimates were combined for a single estimate of net carbon exchange (NCE) and spatially distributed to 0.05 degree resolution using MODIS satellite land cover data. Global crop NPP in 2011 was estimated at 5.25 ± 0.46 Pg C yr-1, of which 2.05 ± 0.05 Pg C yr-1 was harvested and 0.54 Pg C yr-1 was collected from crop residues for livestock fodder. Total livestock feed intake in 2011 was 2.42 ± 0.21 Pg C yr-1, of which 2.31 ± 0.21 Pg C yr-1 was emitted as CO2, 0.07 ± 0.01 Pg C yr-1 was emitted as CH4, and 0.04 Pg C yr-1 was contained within milk and egg production. Livestock grazed an estimated 1.27 Pg C yr-1 in 2011, which constituted 52.4% of total feed intake. Global human food intake was 0.57 ± 0.03 Pg C yr-1 in 2011, the majority of which is respired as CO2. Completed global cropland carbon budgets accounted for the ultimate use of ca. 80% of harvested biomass. The spatial distribution of these fluxes may be used for global carbon monitoring, estimation of regional uncertainty, and for use as input to Earth system models.

  20. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and