National Library of Energy BETA

Sample records for final boiling point

  1. CONTINUOUS ANALYZER UTILIZING BOILING POINT DETERMINATION

    DOEpatents

    Pappas, W.S.

    1963-03-19

    A device is designed for continuously determining the boiling point of a mixture of liquids. The device comprises a distillation chamber for boiling a liquid; outlet conduit means for maintaining the liquid contents of said chamber at a constant level; a reflux condenser mounted above said distillation chamber; means for continuously introducing an incoming liquid sample into said reflux condenser and into intimate contact with vapors refluxing within said condenser; and means for measuring the temperature of the liquid flowing through said distillation chamber. (AEC)

  2. Correlations estimate volume distilled using gravity, boiling point

    SciTech Connect

    Moreno, A.; Consuelo Perez de Alba, M. del; Manriquez, L.; Guardia Mendoz, P. de la

    1995-10-23

    Mathematical nd graphic correlations have been developed for estimating cumulative volume distilled as a function of crude API gravity and true boiling point (TBP). The correlations can be used for crudes with gravities of 21--34{degree} API and boiling points of 150--540 C. In distillation predictions for several mexican and Iraqi crude oils, the correlations have exhibited accuracy comparable to that of laboratory measurements. The paper discusses the need for such a correlation and the testing of the correlation.

  3. Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory

    SciTech Connect

    Fellhauer, C.R.; Boing, L.E.; Aldana, J.

    1997-03-01

    The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

  4. Microsoft PowerPoint - Tsinghua Slideshow final for distribution...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Tsinghua Slideshow final for distribution (2) Microsoft PowerPoint - Tsinghua Slideshow final for distribution (2) PDF icon Microsoft PowerPoint - Tsinghua Slideshow final for ...

  5. Microsoft PowerPoint - Final translated version of Tsinghua Speech...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final translated version of Tsinghua Speech Microsoft PowerPoint - Final translated version of Tsinghua Speech PDF icon Microsoft PowerPoint - Final translated version of Tsinghua ...

  6. Pressure drop, heat transfer, critical heat flux, and flow stability of two-phase flow boiling of water and ethylene glycol/water mixtures - final report for project "Efficent cooling in engines with nucleate boiling."

    SciTech Connect

    Yu, W.; France, D. M.; Routbort, J. L.

    2011-01-19

    Because of its order-of-magnitude higher heat transfer rates, there is interest in using controllable two-phase nucleate boiling instead of conventional single-phase forced convection in vehicular cooling systems to remove ever increasing heat loads and to eliminate potential hot spots in engines. However, the fundamental understanding of flow boiling mechanisms of a 50/50 ethylene glycol/water mixture under engineering application conditions is still limited. In addition, it is impractical to precisely maintain the volume concentration ratio of the ethylene glycol/water mixture coolant at 50/50. Therefore, any investigation into engine coolant characteristics should include a range of volume concentration ratios around the nominal 50/50 mark. In this study, the forced convective boiling heat transfer of distilled water and ethylene glycol/water mixtures with volume concentration ratios of 40/60, 50/50, and 60/40 in a 2.98-mm-inner-diameter circular tube has been investigated in both the horizontal flow and the vertical flow. The two-phase pressure drop, the forced convective boiling heat transfer coefficient, and the critical heat flux of the test fluids were determined experimentally over a range of the mass flux, the vapor mass quality, and the inlet subcooling through a new boiling data reduction procedure that allowed the analytical calculation of the fluid boiling temperatures along the experimental test section by applying the ideal mixture assumption and the equilibrium assumption along with Raoult's law. Based on the experimental data, predictive methods for the two-phase pressure drop, the forced convective boiling heat transfer coefficient, and the critical heat flux under engine application conditions were developed. The results summarized in this final project report provide the necessary information for designing and implementing nucleate-boiling vehicular cooling systems.

  7. Microsoft PowerPoint - 05 Okonski final Project Management Workshop...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    5 Okonski final Project Management Workshop Slides O'Konski Microsoft PowerPoint - 05 Okonski final Project Management Workshop Slides O'Konski Microsoft PowerPoint - 05 Okonski ...

  8. Simultaneous boiling and spreading of liquefied petroleum gas on water. Final report, December 12, 1978-March 31, 1981

    SciTech Connect

    Chang, H.R.; Reid, R.C.

    1981-04-01

    An experimental and theoretical investigation was carried out to study the boiling and spreading of liquid nitrogen, liquid methane and liquefied petroleum gas (LPG) on water in a one-dimensional configuration. Primary emphasis was placed on the LPG studies. Experimental work involved the design and construction of a spill/spread/boil apparatus which permitted the measurement of spreading and local boil-off rates. With the equations of continuity and momentum transfer, a mathematical model was developed to describe the boiling-spreading phenomena of cryogens spilled on water. The model accounted for a decrease in the density of the cryogenic liquid due to bubble formation. The boiling and spreading rates of LPG were found to be the same as those of pure propane. An LPG spill was characterized by the very rapid and violent boiling initially and highly irregular ice formation on the water surface. The measured local boil-off rates of LPG agreed reasonably well with theoretical predictions from a moving boundary heat transfer model. The spreading velocity of an LPG spill was found to be constant and determined by the size of the distributor opening. The maximum spreading distance was found to be unaffected by the spilling rate. These observations can be explained by assuming that the ice formation on the water surface controls the spreading of LPG spills. While the mathematical model did not predict the spreading front adequately, it predicted the maximum spreading distance reasonably well.

  9. Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

    SciTech Connect

    1997-05-01

    This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff`s review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff`s review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.

  10. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

    SciTech Connect

    Not Available

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  11. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices

    SciTech Connect

    Not Available

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  12. BOILING REACTORS

    DOEpatents

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  13. Microsoft PowerPoint - Saudi Arabia 2-22-10 final for distribution...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Saudi Arabia 2-22-10 final for distribution.pptx Microsoft PowerPoint - Saudi Arabia 2-22-10 final for distribution.pptx Microsoft PowerPoint - Saudi Arabia 2-22-10 final for ...

  14. Microsoft PowerPoint - 16.1555_Chad Henderson_Final | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    555Chad HendersonFinal Microsoft PowerPoint - 16.1555Chad HendersonFinal PDF icon Microsoft PowerPoint - 16.1555Chad HendersonFinal More Documents & Publications Microsoft...

  15. Estimating boiling water reactor decommissioning costs: A user`s manual for the BWR Cost Estimating Computer Program (CECP) software. Final report

    SciTech Connect

    Bierschbach, M.C.

    1996-06-01

    Nuclear power plant licensees are required to submit to the US Nuclear Regulatory Commission (NRC) for review their decommissioning cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personal computer, provides estimates for the cost of decommissioning boiling water reactor (BWR) power stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

  16. Microsoft PowerPoint - UAE Masdar 2-24-10 final for distribution...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    final for distribution.pptx Microsoft PowerPoint - UAE Masdar 2-24-10 final for distribution.pptx (4.87 MB) More Documents & Publications Microsoft PowerPoint - Saudi Arabia 2-22

  17. Microsoft PowerPoint - AGA webinar July 2013 Final .pptx | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Microsoft PowerPoint - AGA webinar July 2013 Final .pptx Microsoft PowerPoint - AGA webinar July 2013 Final .pptx Home Energy Score Program Overview for the American Gas ...

  18. Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    [Compatibility Mode] | Department of Energy 0 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] (964.42 KB) More Documents & Publications LINAC Coherent Light Source Microsoft PowerPoint - 16.1045_Peer Reviews Panel_Lehman Workshop Briefing w-headings Microsoft PowerPoint - 09 Lehman final 1003 SC

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

    SciTech Connect

    Konzek, G.J.; Smith, R.I.

    1988-07-01

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

  20. Microsoft PowerPoint - FinalModule1.ppt

    Energy.gov [DOE] (indexed site)

    ... Along with the schedule and cost results discussed, earned value management enables you to forecast the final results of the project (blue dashed line). 0 25 50 75 100 125 150 ...

  1. Microsoft PowerPoint - WH Energy and Climate Stakeholders 10-7-09 final.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    | Department of Energy WH Energy and Climate Stakeholders 10-7-09 final.ppt Microsoft PowerPoint - WH Energy and Climate Stakeholders 10-7-09 final.ppt Microsoft PowerPoint - WH Energy and Climate Stakeholders 10-7-09 final.ppt (1.78 MB) More Documents & Publications Microsoft PowerPoint - CHU_Grid Week 9-21-09 final.ppt Microsoft PowerPoint - 5.3 Item 01 Top Kill Operation Status 09 June 1400.pptx Microsoft PowerPoint - Enterprise Top Hat Phases - 07-04-2010.pptx

  2. Microsoft PowerPoint - AGA webinar July 2013 Final .pptx

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... higher at point of sale Additional cost can be rolled into the loan with little impact on the mortgage payment Common for general home improvements to be made during first year ...

  3. Microsoft PowerPoint - 15.1130_Jeff Baker_Final Ultra-High Efficiency...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    130Jeff BakerFinal Ultra-High Efficiency Commercial Buildings Microsoft PowerPoint - 15.1130Jeff BakerFinal Ultra-High Efficiency Commercial Buildings PDF icon Microsoft...

  4. Material for Point Design (final summary of DIME material)

    SciTech Connect

    Bradley, Paul A.

    2014-02-25

    These slides summarize the motivation of the Defect Induced Mix Experiment (DIME) project, the point design of the Polar Direct Drive (PDD) version of the NIF separated reactant capsule, the experimental requirements, technical achievements, and some useful backup material. These slides are intended to provide much basic material in one convenient location and will hopefully be of some use for subsequent experimental projects.

  5. Enhanced convective and film boiling heat transfer by surface gas injection

    SciTech Connect

    Duignan, M.R.; Greene, G.A. ); Irvine, T.F., Jr. . Dept. of Mechanical Engineering)

    1992-04-01

    Heat transfer measurements were made for stable film boiling of water over a horizontal, flat stainless steel plate from the minimum film boiling point temperature, T{sub SURFACE} {approximately}500K, to T{sub SURFACE} {approximately}950K. The pressure at the plate was approximately 1 atmosphere and the temperature of the water pool was maintained at saturation. The data were compared to the Berenson film-boiling model, which was developed for minimum film-boiling-point conditions. The model accurately represented the data near the minimum film-boiling point and at the highest temperatures measured, as long it was corrected for the heat transferred by radiation. On the average, the experimental data lay within {plus minus}7% of the model. Measurements of heat transfer were made without film boiling for nitrogen jetting into an overlying pool of water from nine 1-mm- diameter holes, drilled in the heat transfer plate. The heat flux was maintained constant at approximately 26.4 kW/m{sup 2}. For water-pool heights of less than 6cm the heat transfer coefficient deceased linearly with a decrease in heights. Above 6cm the heat transfer coefficient was unaffected. For the entire range of gas velocities measured (0 to 8.5 cm/s), the magnitude of the magnitude of the heat transfer coefficient only changed by approximately 20%. The heat transfer data bound the Konsetov model for turbulent pool heat transfer which was developed for vertical heat transfer surfaces. This agreement suggests that surface orientation may not be important when the gas jets do not locally affect the surface heat transfer. Finally, a database was developed for heat transfer from the plate with both film boiling and gas jetting occurring simultaneously, in a pool of water maintained at its saturation temperature. The effect of passing nitrogen through established film boiling is to increase the heat transfer from that surface. 60 refs.

  6. Enhanced convective and film boiling heat transfer by surface gas injection

    SciTech Connect

    Duignan, M.R.; Greene, G.A.; Irvine, T.F., Jr.

    1992-04-01

    Heat transfer measurements were made for stable film boiling of water over a horizontal, flat stainless steel plate from the minimum film boiling point temperature, T{sub SURFACE} {approximately}500K, to T{sub SURFACE} {approximately}950K. The pressure at the plate was approximately 1 atmosphere and the temperature of the water pool was maintained at saturation. The data were compared to the Berenson film-boiling model, which was developed for minimum film-boiling-point conditions. The model accurately represented the data near the minimum film-boiling point and at the highest temperatures measured, as long it was corrected for the heat transferred by radiation. On the average, the experimental data lay within {plus_minus}7% of the model. Measurements of heat transfer were made without film boiling for nitrogen jetting into an overlying pool of water from nine 1-mm- diameter holes, drilled in the heat transfer plate. The heat flux was maintained constant at approximately 26.4 kW/m{sup 2}. For water-pool heights of less than 6cm the heat transfer coefficient deceased linearly with a decrease in heights. Above 6cm the heat transfer coefficient was unaffected. For the entire range of gas velocities measured [0 to 8.5 cm/s], the magnitude of the magnitude of the heat transfer coefficient only changed by approximately 20%. The heat transfer data bound the Konsetov model for turbulent pool heat transfer which was developed for vertical heat transfer surfaces. This agreement suggests that surface orientation may not be important when the gas jets do not locally affect the surface heat transfer. Finally, a database was developed for heat transfer from the plate with both film boiling and gas jetting occurring simultaneously, in a pool of water maintained at its saturation temperature. The effect of passing nitrogen through established film boiling is to increase the heat transfer from that surface. 60 refs.

  7. File:Microsoft PowerPoint - FINAL How to capture data from Wind...

    OpenEI (Open Energy Information) [EERE & EIA]

    Microsoft PowerPoint - FINAL How to capture data from Wind For Schools CAES energy site.pdf Jump to: navigation, search File File history File usage Metadata File:Microsoft...

  8. Geysering in boiling channels

    SciTech Connect

    Aritomi, Masanori; Takemoto, Takatoshi; Chiang, Jing-Hsien

    1995-09-01

    A concept of natural circulation BWRs such as the SBWR has been proposed and seems to be promising in that the primary cooling system can be simplified. The authors have been investigating thermo-hydraulic instabilities which may appear during the start-up in natural circulation BWRs. In our previous works, geysering was investigated in parallel boiling channels for both natural and forced circulations, and its driving mechanism and the effect of system pressure on geysering occurrence were made clear. In this paper, geysering is investigated in a vertical column and a U-shaped vertical column heated in the lower parts. It is clarified from the results that the occurrence mechanism of geysering and the dependence of system pressure on geysering occurrence coincide between parallel boiling channels in circulation systems and vertical columns in non-circulation systems.

  9. Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb22_2010PB final rcvd 5

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Mar [Compatibility Mode] | Department of Energy 1 Bosco PM Workshop BOSCO Feb22_2010PB final rcvd 5 Mar [Compatibility Mode] Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb22_2010PB final rcvd 5 Mar [Compatibility Mode] Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb22_2010PB final rcvd 5 Mar [Compatibility Mode] (732.53 KB) More Documents & Publications Project Management Update - Paul Bosco, Director, Office of Acquisition & Project Mgt Microsoft PowerPoint - 07 Raines

  10. Microsoft PowerPoint - FY11 budget rollout 2-1-10 final | Department...

    Office of Environmental Management (EM)

    (823.93 KB) More Documents & Publications Department of Energy FY 2007 Budget Microsoft PowerPoint - FY 2007 DOE Budget Rollout--Printer Version.ppt FY 2011 Budget Justification

  11. Microsoft PowerPoint - FINAL 1Q14 presentation_20140821.pptx [Read-Only]

    Office of Legacy Management (LM)

    14 Surveillance and Maintenance Report for the LM Rocky Flats Site January-March 2014 Quarterly Monitoring and Reporting  Quarterly reports are required under the Rocky Flats Legacy Management Agreement (RFLMA) to document that the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedy continues to be protective * Primary goal is protection of surface water  Response action under the final remedy for Rocky Flats * Maintain two landfill covers * Maintain four

  12. Microsoft PowerPoint - Final 2015 Annual Report presentation.pptx

    Office of Legacy Management (LM)

    Rocky Flats Site, Colorado Annual Report of Site Surveillance and Maintenance Activities Calendar Year 2015 Rocky Flats Stewardship Council June 6, 2016 Quarterly Monitoring and Reporting  Quarterly reports are required under RFLMA to document that the CERCLA remedy continues to be protective * Primary goal: surface water protection  Response action under the final remedy for Rocky Flats * Maintain two landfill covers * Maintain four groundwater treatment systems * Monitor surface water

  13. Microsoft PowerPoint - Public Workshop - FY12 Budget Briefing Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    2 Public Workshop Briefing U.S. Department of Energy May 25, 2010 FY 2012 Public Workshop Briefing May 2010 Key Points * The U.S. Department of Energy (DOE), Richland Operations Office (RL) is committed to significant accomplishment in cleaning up the Hanford Site and meeting our compliance commitments * This briefing reflects the proposed milestones in the Tri- Party Agreement (TPA) tentative agreements dated March 29, 2010 (M-15) and April 20, 2010 (M-91) 2 March 29, 2010 (M-15) and April 20,

  14. Microsoft PowerPoint - Upcoming NMMSS Training 2014 and 2015 Final.pptx

    National Nuclear Security Administration (NNSA)

    2014 Date Course Location February 25-28, 2014 DOE - NMMSS I Sandia Nat'l Lab, NM March 25-27, 2014 NRC - NMMSS I* Germantown, MD June 10-12, 2014 DOE - NMMSS II Germantown, MD July 15-17, 2014 NRC - NMMSS I* Germantown, MD September 9-12, 2014 DOE - NMMSS I Germantown, MD December 2-4, 2014 NRC - NMMSS I* Germantown, MD *The NRC-NMMSS I training now includes a model on reconciliation Training Point of Contact: John Ballard, 301-903-0092, John.Ballard@nnsa.doe.gov Upcoming NMMSS Training 2015

  15. Enhancement of pool boiling from a vertical rod using guide disks

    SciTech Connect

    Whitehouse, J.C.

    1992-11-01

    This report provides experimental and theoretical investigation of the boiling process which used a system of evenly spaced disks to constrain the path of bubbles from point origin to point of collapse. The experiments identified five distinct heat-transfer regimes, two of which (flange and strobe) are unique to this geometry and cannot be explained by conventional heat-transfer correlations. Bubble and wave models developed for flange and strobe boiling, respectively, predict these phenomena with reasonable success.

  16. Enhancement of pool boiling from a vertical rod using guide disks

    SciTech Connect

    Whitehouse, J.C.

    1992-01-01

    This report provides experimental and theoretical investigation of the boiling process which used a system of evenly spaced disks to constrain the path of bubbles from point origin to point of collapse. The experiments identified five distinct heat-transfer regimes, two of which (flange and strobe) are unique to this geometry and cannot be explained by conventional heat-transfer correlations. Bubble and wave models developed for flange and strobe boiling, respectively, predict these phenomena with reasonable success.

  17. Measurement of point defect energetics in potassium dihydrogen phosphate (KDP). Final report

    SciTech Connect

    Cooke, D.W.; Muenchausen, R.E.; Bennett, B.L.

    1997-10-01

    Potassium dihydrogen phosphate (KDP) in the normal and deuterated form (KD*P) exhibits excellent electrooptical and nonlinear optical properties and is commonly used in frequency conversion applications. Frequency doubling (2 {omega}) of Nd:YAG or Nd:YLF laser fundamental output at 1.06 {micro}m produces visible radiation at 532 nm with relatively good conversion efficiency. Frequency tripling (3{omega}) and quadrupling (4{omega}) are also utilized for production of ultraviolet (uv) radiation at 355 and 266 nm, respectively. However in the latter case the conversion efficiency is relatively low, especially at high incident fluences ({approximately}2 GW/cm{sup 2}). A fundamental problem associated with high peak-power laser excitation of KDP is the production of transient optical absorption that inhibits conversion efficiency. The role of point defects on frequency conversion efficiency and optoelectronic device performance in KDP and its isomorphs is not fully understood. However, it is evident from the extant data that their existence, even in pure specimens, affects the overall performance of these technologically important materials, and that further research is required to elucidate their role. Accordingly, they have investigated the temperature-dependent optical absorption and radioluminescence (RL) of pure KDP as well as doped specimens: KDP:Fe, KDP:Cr, and KDP:Al.

  18. POINT 2012: ENDF/B-VII.1 Final Temperature Dependent Cross Section Library

    SciTech Connect

    Cullen, D E

    2012-02-26

    This report is one in the series of 'POINT' reports that over the years have presented temperature dependent cross sections for the then current version of ENDF/B [R1]. In each case I have used my personal computer at home and publicly available data and codes: (1) publicly available nuclear data (the current ENDF/B data, available on-line at the National Nuclear Data Center, Brookhaven National Laboratory, http://www.nndc.bnl.gov/) and, (2) publicly available computer codes (the current PREPRO codes, available on-line at the Nuclear Data Section, IAEA, Vienna, Austria, http://www-nds.iaea.or.at/ndspub/endf/prepro/) and, (3) My own personal computer located in my home. I have used these in combination to produce the temperature dependent cross sections used in applications and described in this report. I should mention that today anyone with a personal computer can produce these results: by its very nature I consider this data to be born in the public domain.

  19. CHIMNEY FOR BOILING WATER REACTOR

    DOEpatents

    Petrick, M.

    1961-08-01

    A boiling-water reactor is described which has vertical fuel-containing channels for forming steam from water. Risers above the channels increase the head of water radially outward, whereby water is moved upward through the channels with greater force. The risers are concentric and the radial width of the space between them is somewhat small. There is a relatively low rate of flow of water up through the radially outer fuel-containing channels, with which the space between the risers is in communication. (AE C)

  20. Validation Data Plan Implementation: Subcooled Flow Boiling

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Validation Data Plan Implementation: Subcooled Flow Boiling Case Study Anh Bui and Nam Dinh Idaho National Laboratory September 28, 2012 CASL-U-2012-0162-000 CASL-U-2012-0162-000 Subcooled Flow Boiling Case Study INL-MIS-12-27303 1 INL/MIS-12-27303 September 2012 Validation Data Plan Implementation: Subcooled Flow Boiling Case Study Anh Bui Nam Dinh CASL-U-2012-0162-000 Subcooled Flow Boiling Case Study INL-MIS-12-27303 2 ABSTRACT This report presents a step forward in the development and

  1. FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    2 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010 DOE/EA-1712 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010

  2. Lattice Boltzmann modeling of boiling heat transfer: The boiling curve and the effects of wettability

    DOE PAGES [OSTI]

    Li, Q.; Kang, Q. J.; Francois, M. M.; He, Y. L.; Luo, K. H.

    2015-03-03

    A hybrid thermal lattice Boltzmann (LB) model is presented to simulate thermal multiphase flows with phase change based on an improved pseudopotential LB approach (Li et al., 2013). The present model does not suffer from the spurious term caused by the forcing-term effect, which was encountered in some previous thermal LB models for liquid–vapor phase change. Using the model, the liquid–vapor boiling process is simulated. The boiling curve together with the three boiling stages (nucleate boiling, transition boiling, and film boiling) is numerically reproduced in the LB community for the first time. The numerical results show that the basic featuresmore » and the fundamental characteristics of boiling heat transfer are well captured, such as the severe fluctuation of transient heat flux in the transition boiling and the feature that the maximum heat transfer coefficient lies at a lower wall superheat than that of the maximum heat flux. Moreover, the effects of the heating surface wettability on boiling heat transfer are investigated. It is found that an increase in contact angle promotes the onset of boiling but reduces the critical heat flux, and makes the boiling process enter into the film boiling regime at a lower wall superheat, which is consistent with the findings from experimental studies.« less

  3. Lattice Boltzmann modeling of boiling heat transfer: The boiling curve and the effects of wettability

    SciTech Connect

    Li, Q.; Kang, Q. J.; Francois, M. M.; He, Y. L.; Luo, K. H.

    2015-03-03

    A hybrid thermal lattice Boltzmann (LB) model is presented to simulate thermal multiphase flows with phase change based on an improved pseudopotential LB approach (Li et al., 2013). The present model does not suffer from the spurious term caused by the forcing-term effect, which was encountered in some previous thermal LB models for liquid–vapor phase change. Using the model, the liquid–vapor boiling process is simulated. The boiling curve together with the three boiling stages (nucleate boiling, transition boiling, and film boiling) is numerically reproduced in the LB community for the first time. The numerical results show that the basic features and the fundamental characteristics of boiling heat transfer are well captured, such as the severe fluctuation of transient heat flux in the transition boiling and the feature that the maximum heat transfer coefficient lies at a lower wall superheat than that of the maximum heat flux. Moreover, the effects of the heating surface wettability on boiling heat transfer are investigated. It is found that an increase in contact angle promotes the onset of boiling but reduces the critical heat flux, and makes the boiling process enter into the film boiling regime at a lower wall superheat, which is consistent with the findings from experimental studies.

  4. Experimental Investigation of Subcooled Flow Boiling

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    8 Experimental Investigation of Subcooled Flow Boiling Yassin A. Hassan TAMU September 30, 2013 CASL-8-2013-0214-000 TEXAS A&M UNIVERSITY Experimental Investigation of Subcooled Flow Boiling Milestone Report PI: Yassin A. Hassan 9/30/2013 CASL-U-2013-0214-000 Contents Introduction ....................................................................................................................................................... 5 Experimental Setup

  5. Boiling water reactor-full length emergency core cooling heat...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Boiling water reactor-full length emergency core cooling heat transfer ... Citation Details In-Document Search Title: Boiling water reactor-full length emergency ...

  6. 2010 Inspection and Status Report for the Boiling Nuclear Superheater...

    Office of Legacy Management (LM)

    Annual Inspection - Boiling Nuclear Superheat (BONUS) Site, Rincn, Puerto Rico October 2013 Page 1 2013 Inspection and Status Report for the Former Boiling Nuclear Superheater...

  7. PACCAR CRADA: Experimental Investigation in Coolant Boiling in...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Power Electronics of Electric Vehicles with Small Channel Coolant Boiling Cooling Boiling in Head Region - PACCAR Integrated Underhood Thermal and External Aerodynamics- Cummins

  8. CRADA with PACCAR Experimental Investigation in Coolant Boiling...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Circular Tube Efficient Cooling in Engines with Nucleated Boiling Cooling Boiling in Head Region - PACCAR Integrated Underhood Thermal and External Aerodynamics- Cummins

  9. Preliminary design study of small long life boiling water reactor...

    Office of Scientific and Technical Information (OSTI)

    boiling water reactor (BWR) with tight lattice thorium nitride fuel Citation Details In-Document Search Title: Preliminary design study of small long life boiling water reactor ...

  10. Great Boiling Springs Geothermal Area | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Great Boiling Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Great Boiling Springs Geothermal Area Contents 1 Area Overview 2 History and...

  11. Modeling acid-gas generation from boiling chloride brines (Journal...

    Office of Scientific and Technical Information (OSTI)

    Modeling acid-gas generation from boiling chloride brines Citation Details In-Document Search Title: Modeling acid-gas generation from boiling chloride brines This study ...

  12. Apparatus for pumping liquids at or below the boiling point

    DOEpatents

    Bingham, Dennis N.

    2002-01-01

    A pump comprises a housing having an inlet and an outlet. An impeller assembly mounted for rotation within the housing includes a first impeller piece having a first mating surface thereon and a second impeller piece having a second mating surface therein. The second mating surface of the second impeller piece includes at least one groove therein so that at least one flow channel is defined between the groove and the first mating surface of the first impeller piece. A drive system operatively associated with the impeller assembly rotates the impeller assembly within the housing.

  13. Numerical Simulations of Boiling Jet Impingement Cooling in Power Electronics

    SciTech Connect

    Narumanchi, S.; Troshko, A.; Hassani, V.; Bharathan, D.

    2006-12-01

    This paper explores turbulent boiling jet impingement for cooling power electronic components in hybrid electric vehicles.

  14. SUPERHEATING IN A BOILING WATER REACTOR

    DOEpatents

    Treshow, M.

    1960-05-31

    A boiling-water reactor is described in which the steam developed in the reactor is superheated in the reactor. This is accomplished by providing means for separating the steam from the water and passing the steam over a surface of the fissionable material which is not in contact with the water. Specifically water is boiled on the outside of tubular fuel elements and the steam is superheated on the inside of the fuel elements.

  15. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  16. ASTRID: A 3D Eulerian software for subcooled boiling modelling - comparison with experimental results in tubes and annuli

    SciTech Connect

    Briere, E.; Larrauri, D.; Olive, J.

    1995-09-01

    For about four years, Electricite de France has been developing a 3-D computer code for the Eulerian simulation of two-phase flows. This code, named ASTRID, is based on the six-equation two-fluid model. Boiling water flows, such as those encountered in nuclear reactors, are among the main applications of ASTRID. In order to provide ASTRID with closure laws and boundary conditions suitable for boiling flows, a boiling model has been developed by EDF and the Institut de Mecanique des Fluides de Toulouse. In the fluid, the heat and mass transfer between a bubble and the liquid is being modelled. At the heating wall, the incipient boiling point is determined according to Hsu`s criterion and the boiling heat flux is split into three additive terms: a convective term, a quenching term and a vaporisation term. This model uses several correlations. EDF`s program in boiling two-phase flows also includes experimental studies, some of which are performed in collaboration with other laboratories. Refrigerant subcooled boiling both in tubular (DEBORA experiment, CEN Grenoble) and in annular geometry (Arizona State University Experiment) have been computed with ASTRID. The simulations show the satisfactory results already obtained on void fraction and liquid temperature. Ways of improvement of the model are drawn especially on the dynamical part.

  17. Subcooled Flow Boiling Heat Transfer to Water and Ethylene Glycol...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Subcooled Flow Boiling Heat Transfer to Water and Ethylene GlycolWater Mixtures in a Bottom-Heated Tube Title Subcooled Flow Boiling Heat Transfer to Water and Ethylene Glycol...

  18. PNNL Enhanced Pool-Boiling Heat Transfer Using Nanostructured Surfaces

    ScienceCinema

    None

    2012-12-31

    Close-up video of boiling taking place on a nanostructured surface in a controlled laboratory experiment.

  19. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

    SciTech Connect

    Hebdon, F.J.

    1993-03-01

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

  20. Silent discharge plasma for point-of-use abatement of VOC emissions. Final report ESHCOO3(b)

    SciTech Connect

    Coogan, J.J.; Jassal, A.

    1997-02-14

    Los Alamos and SEMATECH have evaluated a silent discharge plasma (SDP) device for point-of-use (POU) control of specific semiconductor VOC emissions at the source. Destruction efficiencies were initially determined at the bench scale using controlled gas mixtures and system performance was measured for simulated emissions containing a variety of volatile organic compounds (including HMDS) and PFCs. Based on this work, a field-pilot unit was designed and tested at a SEMATECH member site using two slip-streams: (1) PGMEA and HMDS gas mixture from lithography tools and the, (2) acetone, PCE and methanol from a wet bench cleaning tool. Based on the pilot test data, CoO estimates for the SDP technology show annual operating expenses (including amortized capital and installation costs, maintenance, and utilities) are $8.3K for a single 250 scfm lithotrack tool. End-of-pipe (EOP) system costs are $33.3K per 1000 scfm as compared to about $22K per 1000 scfm for a typical EOP concentrator/thermal abatement system. LANL does not recommend replacing existing EOP systems with SDP. However SDP could be easily installed in {open_quotes}niche{close_quotes} circumstances for POU control of VOCs from lithotrack tools.

  1. Validation of the BERT Point Source Inversion Scheme Using the Joint Urban 2003 Tracer Experiment Dataset - Final Report

    SciTech Connect

    Brambilla, Sara; Brown, Michael J.

    2012-06-18

    zones. Due to a unique source inversion technique - called the upwind collector footprint approach - the tool runs fast and the source regions can be determined in a few minutes. In this report, we provide an overview of the BERT framework, followed by a description of the source inversion technique. The Joint URBAN 2003 field experiment held in Oklahoma City that was used to validate BERT is then described. Subsequent sections describe the metrics used for evaluation, the comparison of the experimental data and BERT output, and under what conditions the BERT tool succeeds and performs poorly. Results are aggregated in different ways (e.g., daytime vs. nighttime releases, 1 vs. 2 vs. 3 hit collectors) to determine if BERT shows any systematic errors. Finally, recommendations are given for how to improve the code and procedures for optimizing performance in operational mode.

  2. PACCAR CRADA: Experimental Investigation in Coolant Boiling in a

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Half-Heated Circular Tube | Department of Energy PACCAR CRADA: Experimental Investigation in Coolant Boiling in a Half-Heated Circular Tube PACCAR CRADA: Experimental Investigation in Coolant Boiling in a Half-Heated Circular Tube 2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting vss079_yu_2012_o.pdf (585.51 KB) More Documents & Publications CRADA with PACCAR Experimental Investigation in Coolant Boiling in a

  3. Enhanced Pool-Boiling Heat Transfer Using Nanostructured Surfaces...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    creates optimal surface wettability characteristics that allow better capillary flow of water on the liquid boiling surfaces often used to cool electronics. the dense...

  4. Geothermal Technology Breakthrough in Alaska: Harvesting Heat below Boiling Temperatures

    Energy.gov [DOE]

    The Energy Department is supporting geothermal exploration at lower temperatures, thanks to a technology breakthrough that allows geothermal energy to be produced at temperatures below the boiling...

  5. (Boiling water reactor (BWR) CORA experiments)

    SciTech Connect

    Ott, L.J.

    1990-10-16

    To participate in the 1990 CORA Workshop at Kernforschungszentrum Karlsruhe (KfK) GmbH, Karlsruhe, FRG, on October 1--4, and to participate in detailed discussions on October 5 with the KfK CORA Boiling Water Reactor (BWR) experiments. The traveler attended the 1990 CORA Workshop at KfK, FRG. Participation included the presentation of a paper on work performed by the Boiling Water Reactor Core Melt Progression Phenomena Program at Oak Ridge National Laboratory (ORNL) on posttest analyses of CORA BWR experiments. The Statement of Work (November 1989) for the BWR Core Melt Progression Phenomena Program provides for pretest and posttest analyses of the BWR CORA experiments performed at KfK. Additionally, it is intended that ORNL personnel participate in the planning process for future CORA BWR experiments. For these purposes, meetings were held with KfK staff to discuss such topics as (1) experimental test schedule, (2) BWR test conduct, (3) perceived BWR experimental needs, and (4) KfK operational staff needs with respect to ORNL support. 19 refs.

  6. Conversion of direct process high-boiling residue to monosilanes

    DOEpatents

    Brinson, Jonathan Ashley (Vale of Glamorgan, GB); Crum, Bruce Robert (Madison, IN); Jarvis, Jr., Robert Frank (Midland, MI)

    2000-01-01

    A process for the production of monosilanes from the high-boiling residue resulting from the reaction of hydrogen chloride with silicon metalloid in a process typically referred to as the "direct process." The process comprises contacting a high-boiling residue resulting from the reaction of hydrogen chloride and silicon metalloid, with hydrogen gas in the presence of a catalytic amount of aluminum trichloride effective in promoting conversion of the high-boiling residue to monosilanes. The present process results in conversion of the high-boiling residue to monosilanes. At least a portion of the aluminum trichloride catalyst required for conduct of the process may be formed in situ during conduct of the direct process and isolation of the high-boiling residue.

  7. L3:THM.CLS.P7.09 Advancements on Wall Boiling Modeling in CFD...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... Nanofluid Pool Boiling Phenomena," Nanoscale Research Letters, vol. 6, no. 232, 2011. 2 J. Garnier, E. Manon and G. Cubizolles, "Local Measurements on Flow Boiling of Refrigerant ...

  8. Solar powered circulation pump development. Final report

    SciTech Connect

    Johnson, A.L.

    1980-09-01

    An iterative design and evaluation process was undertaken to develop a prototype solar powered liquid circulation pump. The first effort was to review the state-of-the-art of liquid piston heat engines. Next a morphological analysis of the original concept was performed. An analysis of the pump performance from a theoretical basis was performed by deriving and solving the equations governing the cycle. The results are documented. An experimental evaluation of the condensing phenomena was performed. The design of the boiler was then undertaken. This effort showed a fundamental physical limitation imposed by the original geometry and the physics of water boiling. In an effort to resolve this problem, a number of alternate configurations were examined, with the result being that the boiler and heat pipe elements of the design were entirely eliminated. In their stead it was assumed that the boiling could be conducted in the solar panel. A number of solar panel designs were examined, and the most appropriate type of solar panel is described in the appendix. A 1/4th scale unit was fabricated and tested. The overall efficiency was approximately 1% at the design point, compared with a theoretical limit of 1.6% for the given operating conditions. The production costs of the full size pump were examined. Finally systems integration aspects were considered and the results presented.

  9. Camera Inspection Arm for Boiling Water Reactors - 13330

    SciTech Connect

    Martin, Scott; Rood, Marc

    2013-07-01

    Boiling Water Reactor (BWR) outage maintenance tasks can be time-consuming and hazardous. Reactor facilities are continuously looking for quicker, safer, and more effective methods of performing routine inspection during these outages. In 2011, S.A. Technology (SAT) was approached by Energy Northwest to provide a remote system capable of increasing efficiencies related to Reactor Pressure Vessel (RPV) internal inspection activities. The specific intent of the system discussed was to inspect recirculation jet pumps in a manner that did not require manual tooling, and could be performed independently of other ongoing inspection activities. In 2012, SAT developed a compact, remote, camera inspection arm to create a safer, more efficient outage environment. This arm incorporates a compact and lightweight design along with the innovative use of bi-stable composite tubes to provide a six-degree of freedom inspection tool capable of reducing dose uptake, reducing crew size, and reducing the overall critical path for jet pump inspections. The prototype camera inspection arm unit is scheduled for final testing in early 2013 in preparation for the Columbia Generating Station refueling outage in the spring of 2013. (authors)

  10. Analysis of the magnetic corrosion product deposits on a boiling water reactor cladding

    SciTech Connect

    Orlov, Andrey; Degueldre, Claude; Kaufmann, Wilfried

    2013-01-15

    The buildup of corrosion product deposits (CRUD) on the fuel cladding of the boiling water reactor (BWR) before and after zinc injection has been investigated by applying local experimental analytical techniques. Under the BWR water chemistry conditions, Zn addition together with the presence of Ni and Mn induce the formation of (Zn,Ni,Mn)[Fe{sub 2}O{sub 4}] spinel solid solutions. X-ray absorption spectroscopy (XAS) revealed inversion ratios of cation distribution in spinels deposited from the solid solution. Based on this information, a two-site ferrite spinel solid solution model is proposed. Electron probe microanalysis (EPMA) and extended X-ray absorption fine structure (EXAFS) findings suggest the zinc-rich ferrite spinels formation on BWR fuel cladding mainly at lower pin. - Graphical Abstract: Analysis of spinels in corrosion product deposits on boiling water reactor fuel rod. Combining EPMA and XAFS results: schematic representation of the ferrite spinels in terms of the end members and their extent of inversion. Note that the ferrites are represented as a surface between the normal (upper plane, M[Fe{sub 2}]O{sub 4}) and the inverse (lower plane, Fe[MFe]O{sub 4}). Actual compositions red Black-Small-Square for the specimen at low elevation (810 mm), blue Black-Small-Square for the specimen at mid elevation (1800 mm). The results have an impact on the properties of the CRUD material. Highlights: Black-Right-Pointing-Pointer Buildup of corrosion product deposits on fuel claddings of a boiling water reactor (BWR) are investigated. Black-Right-Pointing-Pointer Under BWR water conditions, Zn addition with Ni and Mn induced formation of (Zn,Ni,Mn)[Fe{sub 2}O{sub 4}]. Black-Right-Pointing-Pointer X-Ray Adsorption Spectroscopy (XAS) revealed inversion of cations in spinel solid solutions. Black-Right-Pointing-Pointer Zinc-rich ferrite spinels are formed on BWR fuel cladding mainly at lower pin elevations.

  11. Flow Boiling Carolyn Coyle, Jacopo Buongiorno, Thomas McKrell

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... Systems I: Thermal Hydraulic Fundamentals, Taylor & Francis 1993. 13. ... Nuclear Engineering and Design 241.3 (2011): 792-98. 17. Pan, C., Jones, B.G., "Wick Boiling ...

  12. Passive gamma analysis of the boiling-water-reactor assemblies

    DOE PAGES [OSTI]

    Vo, D.; Favalli, A.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S.; Trellue, H.; et al

    2016-06-04

    This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies from a boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden’s Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative–Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in themore » past using nondestructive assay (NDA) measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. The final objective of this project is to quantify the capability of several integrated NDA instruments to meet the aforementioned goals using the combined signatures of neutrons, gamma rays, and heat. This report presents a selection of the measured data and summarizes an analysis of the results. Specifically, trends in the count rates measured for spectral lines from the following isotopes were analyzed as a function of the declared burnup and cooling time: 137Cs, 154Eu, 134Cs, and to a lesser extent, 106Ru and 144Ce. From these measured count rates, predictive algorithms were developed to enable the estimation of the burnup and cooling time. Furthermore, these algorithms were benchmarked on a set of assemblies not included in the standard assemblies set used by this research team.« less

  13. CASL-U-2015-0040-000 Initial Boiling Water

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    40-000 Initial Boiling Water Reactor (BWR) Input Specifications Scott Palmtag Core Physics February 28, 2015 Initial Boiling Water Reactor (BWR) Input Specification Consortium for Advanced Simulation of LWRs ii CASL-U-2015-0040-000 REVISION LOG Revision Date Affected Pages Revision Description 0 02/28/2015 All Original Report for L3:PHI.VCS.P10.02 Document pages that are: Export Controlled NO IP/Proprietary/NDA Controlled NO Sensitive Controlled NO Requested Distribution: To: Copy: Initial

  14. Acoustic emission feedback control for control of boiling in a microwave oven

    DOEpatents

    White, Terry L.

    1991-01-01

    An acoustic emission based feedback system for controlling the boiling level of a liquid medium in a microwave oven is provided. The acoustic emissions from the medium correlated with surface boiling is used to generate a feedback control signal proportional to the level of boiling of the medium. This signal is applied to a power controller to automatically and continuoulsly vary the power applied to the oven to control the boiling at a selected level.

  15. Microsoft PowerPoint - WIPPRecovery

    Office of Environmental Management (EM)

    Department of Energy Tsinghua Slideshow final for distribution (2) Microsoft PowerPoint - Tsinghua Slideshow final for distribution (2) Microsoft PowerPoint - Tsinghua Slideshow final for distribution (2) (4.67 MB) More Documents & Publications Microsoft PowerPoint - Final translated version of Tsinghua Speech Idaho Operations AMWTP Fact Sheet Methane Hydrate R&D

    Innovation that Can Make a Difference Secretary Steven Chu Emirates Palace Hotel Abu Dhabi, United Arab Emirates 24

  16. Modeling acid-gas generation from boiling chloride brines

    SciTech Connect

    Zhang, Guoxiang; Spycher, Nicolas; Sonnenthal, Eric; Steefel, Carl

    2009-11-16

    This study investigates the generation of HCl and other acid gases from boiling calcium chloride dominated waters at atmospheric pressure, primarily using numerical modeling. The main focus of this investigation relates to the long-term geologic disposal of nuclear waste at Yucca Mountain, Nevada, where pore waters around waste-emplacement tunnels are expected to undergo boiling and evaporative concentration as a result of the heat released by spent nuclear fuel. Processes that are modeled include boiling of highly concentrated solutions, gas transport, and gas condensation accompanied by the dissociation of acid gases, causing low-pH condensate. Simple calculations are first carried out to evaluate condensate pH as a function of HCl gas fugacity and condensed water fraction for a vapor equilibrated with saturated calcium chloride brine at 50-150 C and 1 bar. The distillation of a calcium-chloride-dominated brine is then simulated with a reactive transport model using a brine composition representative of partially evaporated calcium-rich pore waters at Yucca Mountain. Results show a significant increase in boiling temperature from evaporative concentration, as well as low pH in condensates, particularly for dynamic systems where partial condensation takes place, which result in enrichment of HCl in condensates. These results are in qualitative agreement with experimental data from other studies. The combination of reactive transport with multicomponent brine chemistry to study evaporation, boiling, and the potential for acid gas generation at the proposed Yucca Mountain repository is seen as an improvement relative to previously applied simpler batch evaporation models. This approach allows the evaluation of thermal, hydrological, and chemical (THC) processes in a coupled manner, and modeling of settings much more relevant to actual field conditions than the distillation experiment considered. The actual and modeled distillation experiments do not represent

  17. Public health assessment for Treasure Island Naval Station, Hunters Point Annex, San Francisco, San Francisco County, California, Region 9. Cerclis No. CA1170090087. Final report

    SciTech Connect

    Not Available

    1994-09-30

    Naval Station Treasure Island, Hunters Point Annex (HPA), an inactive Naval shipyard located on a peninsula in the San Francisco Bay, San Francisco, California, was listed for base closure in 1990. Metals, pesticides, radium-226, polychlorinated biphenyls (PCBs), polycyclic aromatic hydrocarbons (PAHs), volatile organic compounds, semivolatile organic compounds, petroleum products, and asbestos have been found in various media such as soil, groundwater, surface water, air, and sediments. Navy contractors have identified 58 HPA areas where there may be contamination; investigations at these areas are ongoing.

  18. Study of hydrocarbon miscible solvent slug injection process for improved recovery of heavy oil from Schrader Bluff Pool, Milne Point Unit, Alaska. Final report

    SciTech Connect

    1995-11-01

    The National Energy Strategy Plan (NES) has called for 900,000 barrels/day production of heavy oil in the mid-1990s to meet our national needs. To achieve this goal, it is important that the Alaskan heavy oil fields be brought to production. Alaska has more than 25 billion barrels of heavy oil deposits. Conoco, and now BP Exploration have been producing from Schrader Bluff Pool, which is part of the super heavy oil field known as West Sak Field. Schrader Bluff reservoir, located in the Milne Point Unit, North Slope of Alaska, is estimated to contain up to 1.5 billion barrels of (14 to 21{degrees}API) oil in place. The field is currently under production by primary depletion; however, the primary recovery will be much smaller than expected. Hence, waterflooding will be implemented earlier than anticipated. The eventual use of enhanced oil recovery (EOR) techniques, such as hydrocarbon miscible solvent slug injection process, is vital for recovery of additional oil from this reservoir. The purpose of this research project was to determine the nature of miscible solvent slug which would be commercially feasible, to evaluate the performance of the hydrocarbon miscible solvent slug process, and to assess the feasibility of this process for improved recovery of heavy oil from Schrader Bluff reservoir. The laboratory experimental work includes: slim tube displacement experiments and coreflood experiments. The components of solvent slug includes only those which are available on the North Slope of Alaska.

  19. Environmental surveys during operation and following removal of the OTEC-1 system off Keahole Point, Hawaii. Final report, January-April 1981

    SciTech Connect

    Noda, E.K.; Bienfang, P.K.; Kimmerer, W.J.; Walsh, T.W.

    1981-09-01

    Detailed are two biological chemical cruises off Keahole Point, Hawaii, which took place during (HOTEC-11, January 1981) and immediately after cessation (HOTEC-12, April 1981) of operation of OTEC-1. The objectives of the study were to: (1) compare site specific data taken before OTEC-1 was operating to data taken after OTEC-1 left the site; and (2) perform an analysis of OTEC environmental effects to indicate areas in which future sampling efforts might be expended. Data from temperature, nutrient, phytoplankton and zooplankton analyses taken immediately after OTEC-1 left the site show only minor differences with data taken before OTEC-1 occupied the site (HOTEC-01-06, MSG-82-013). The differences were not significant, and therefore, OTEC-1 had no demonstrable post-operational impacts on these environmental variables. From temperature records the minimum /sup 0/T between surface waters (0-30 m) and 700 m water was about 18/sup 0/C. There was no demonstrable temperature effect due to operation of OTEC-1. Significant increases in near surface water (0 to 70 m) nitrate concentrations were noted at Station 1 (Control) during OTEC-1 operations; while after shut-down no effect was seen. This effect can not be directly attributed to OTEC-1. Increased chlorophyll a standing stock downstream of OTEC-1 indicated some effect of OTEC-1. No toxic effect was noted and primary productivity rates were the same at all stations. The chlorophyll a biomass in the < 5 ..mu..m size fraction was significantly higher at the downstream station. No effect on zooplankton were noted at any station. Abundance of ichthytoplankton taxa are reported but there is insufficient data to perform an analysis.

  20. Efficiency of a solar collector with internal boiling

    SciTech Connect

    Neeper, D.A.

    1986-01-01

    The behavior of a solar collector with a boiling fluid is analyzed to provide a simple algebraic model for future systems simulations, and to provide guidance for testing. The efficiency equation is developed in a form linear in the difference between inlet and saturation (boiling) temperatures, whereas the expression upon which ASHRAE Standard 109P is based utilizes the difference between inlet and ambient temperatures. The coefficient of the revised linear term is a weak function of collector parameters, weather, and subcooling of the working fluid. For a glazed flat-plate collector with metal absorber, the coefficient is effectively constant. Therefore, testing at multiple values of insolation and subcooling, as specified by ASHRAE 109P, should not be necessary for most collectors. The influences of collector properties and operating conditions on efficiency are examined.

  1. Oceanographic effects of the 1992 Point Loma sewage pipe spill

    SciTech Connect

    Casey, R.; Ciccateri, A.; Dougherty, K.; Gacek, L.; Lane, S.; Liponi, K.; Leeds, R.; Walsh, F. )

    1992-01-01

    Early in early 1992, 180 million gallons of advanced primarily treated sewage emptied into 10 meters of water from the broken Point Loma sewage pipe, San Diego. For about two months a sewage boil about the size of a football field existed at the surface and within the Point Loma kelp bed. Sampling and observations taken during the spill indicated the surface waters at the spill site were grayish and smelling of sewage. The sewage water had mixed with the marine waters reducing salinity to about one-half normal (or 15 ppt.). The sediment load of the sewage coated the blades of the giant kelp and the kelp was limp and withdrawn from the surface. At the site of the main boil the kelp appeared to have dropped to the bottom. Sediments on the bottom in the boil area were mainly coarse sands as compared to the surrounding sandy-muds. Preliminary results using laboratory analysis suggest: one month into the spill no infauna were observed in the sediments or planktons in the water of the boil area, but were in the surrounding sediments and water; the observed phytoplankton were dominated by dinoflagellates and suggested red tide conditions surrounding the boil. The site has been monitored monthly since the spill to observe further impact and recovery.

  2. SELF-REGULATING BOILING-WATER NUCLEAR REACTORS

    DOEpatents

    Ransohoff, J.A.; Plawchan, J.D.

    1960-08-16

    A boiling-water reactor was designed which comprises a pressure vessel containing a mass of water, a reactor core submerged within the water, a reflector tank disposed within the reactor, the reflector tank being open at the top to the interior of the pressure vessel, and a surge tank connected to the reflector tank. In operation the reflector level changes as a function of the pressure witoin the reactor so that the reactivity of the reactor is automatically controlled.

  3. Method for controlling boiling point distribution of coal liquefaction oil product

    DOEpatents

    Anderson, Raymond P.; Schmalzer, David K.; Wright, Charles H.

    1982-12-21

    The relative ratio of heavy distillate to light distillate produced in a coal liquefaction process is continuously controlled by automatically and continuously controlling the ratio of heavy distillate to light distillate in a liquid solvent used to form the feed slurry to the coal liquefaction zone, and varying the weight ratio of heavy distillate to light distillate in the liquid solvent inversely with respect to the desired weight ratio of heavy distillate to light distillate in the distillate fuel oil product. The concentration of light distillate and heavy distillate in the liquid solvent is controlled by recycling predetermined amounts of light distillate and heavy distillate for admixture with feed coal to the process in accordance with the foregoing relationships.

  4. Method for controlling boiling point distribution of coal liquefaction oil product

    DOEpatents

    Anderson, R.P.; Schmalzer, D.K.; Wright, C.H.

    1982-12-21

    The relative ratio of heavy distillate to light distillate produced in a coal liquefaction process is continuously controlled by automatically and continuously controlling the ratio of heavy distillate to light distillate in a liquid solvent used to form the feed slurry to the coal liquefaction zone, and varying the weight ratio of heavy distillate to light distillate in the liquid solvent inversely with respect to the desired weight ratio of heavy distillate to light distillate in the distillate fuel oil product. The concentration of light distillate and heavy distillate in the liquid solvent is controlled by recycling predetermined amounts of light distillate and heavy distillate for admixture with feed coal to the process in accordance with the foregoing relationships. 3 figs.

  5. Microsoft PowerPoint - Crozat NEAC Final

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ...2013 Recent History of U.S. Nuclear Fleet140.0 100 0 120.0 80.0 100.0 GWe Applications ... 2014 4,000 5,000 TWh 2014 2,000 3,000 T-1,000 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 EIA, ...

  6. Microsoft PowerPoint - Salishan2005FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Computer Science The Salishan Conference on High-Speed Computing - April 18-21, 2005 Challenges in Scalability of Performance Tools for Petaflops Systems Patricia J. Teller, Ph.D. University of Texas-El Paso Department of Computer Science pteller@cs.utep.edu Department of Computer Science The Salishan Conference on High-Speed Computing - April 18-21, 2005 Outline * Motivation - Why do we need performance tuning tools? * Foundational Techniques - Data Collection - Facilitating Data Analysis *

  7. Microsoft PowerPoint - shreyas-final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Grid Services at NERSC Shreyas Cholia Open Software and Programming Group NERSC Division, LBNL October 2008 2 What are Grid Services? * Set of services and tools used for remotely managing jobs and data * Useful for job workflows and data movement across sites and systems * NERSC Grid software is based on Globus toolkit * "Grid Certificate" is the common access token that lets you transparently access multiple sites and resources 3 Common Concerns * Process of acquiring and setting up

  8. Microsoft PowerPoint - Seitz HIDRA final

    Office of Environmental Management (EM)

    ... no reference to a specific basic action Adoption of the issue in the education programme High Institutional control Medium Labelling and marking Low Alteration of the ...

  9. DIRECT-CYCLE, BOILING-WATER NUCLEAR REACTOR

    DOEpatents

    Harrer, J.M.; Fromm, L.W. Jr.; Kolba, V.M.

    1962-08-14

    A direct-cycle boiling-water nuclear reactor is described that employs a closed vessel and a plurality of fuel assemblies, each comprising an outer tube closed at its lower end, an inner tube, fuel rods in the space between the tubes and within the inner tube. A body of water lying within the pressure vessel and outside the fuel assemblies is converted to saturated steam, which enters each fuel assembly at the top and is converted to superheated steam in the fuel assembly while it is passing therethrough first downward through the space between the inner and outer tubes of the fuel assembly and then upward through the inner tube. (AEC)

  10. Union job fight boiling at DOE cleanup sites

    SciTech Connect

    Setzer, S.W.

    1993-11-15

    The US DOE is facing a growing jurisdictional dispute over which unions will perform the majority of clean-up work at its facilities. Unions affiliated with the AFL-CIO Metal Trades Council representing operations employees at the sites believe they have a fundamental right to work. Unions in the AFL-CIO's Building and Construction Trades Dept. insist that they have a clear mandate under federal labor law and the Davis-Bacon Act. The issue has heated up in recent weeks at the policy level and is boiling in a contentious dispute at DOE's Fernald site in Ohio.

  11. Lattice Boltzmann Methods to Address Fundamental Boiling and Two-Phase Problems

    SciTech Connect

    Uddin, Rizwan

    2012-01-01

    This report presents the progress made during the fourth (no cost extension) year of this three-year grant aimed at the development of a consistent Lattice Boltzmann formulation for boiling and two-phase flows. During the first year, a consistent LBM formulation for the simulation of a two-phase water-steam system was developed. Results of initial model validation in a range of thermo-dynamic conditions typical for Boiling Water Reactors (BWRs) were shown. Progress was made on several fronts during the second year. Most important of these included the simulation of the coalescence of two bubbles including the surface tension effects. Work during the third year focused on the development of a new lattice Boltzmann model, called the artificial interface lattice Boltzmann model (AILB model) for the 3 simulation of two-phase dynamics. The model is based on the principle of free energy minimization and invokes the Gibbs-Duhem equation in the formulation of non-ideal forcing function. This was reported in detail in the last progress report. Part of the efforts during the last (no-cost extension) year were focused on developing a parallel capability for the 2D as well as for the 3D codes developed in this project. This will be reported in the final report. Here we report the work carried out on testing the AILB model for conditions including the thermal effects. A simplified thermal LB model, based on the thermal energy distribution approach, was developed. The simplifications are made after neglecting the viscous heat dissipation and the work done by pressure in the original thermal energy distribution model. Details of the model are presented here, followed by a discussion of the boundary conditions, and then results for some two-phase thermal problems.

  12. Knowledge and abilities catalog for nuclear power plant operators: boiling water reactors

    SciTech Connect

    Not Available

    1986-09-01

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWR) (NUREG-1123) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog and Examiners' Handbook for Developing Operator Licensing Examinations (NUREG-1121) will cover those topics listed under Title 10, Code of Federal Regulations, Part 55. The BWR Catalog contains approximately 7000 knowledge and ability (K/A) statements for ROs and SROs at boiling water reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring personnel and public health and safety. The BWR K/A Catalog is organized into five major sections: Plant-wide Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Function, Emergency and Abnormal Plant Evolutions, Components, and Theory. The BWR Catalog represents a modification of the form and content of the K/A Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG-1122). First, categories of knowledge and ability statements have been redefined. Second, the scope of the definition of emergency and abnormal plant evolutions has been revised in line with a symptom-based approach. Third, K/As related to the operational applications of theory have been incorporated into the delineations for both plant systems and emergency and abnormal plant evolutions, while K/As pertaining to theory fundamental to plant operation have been delineated in a separate theory section. Finally, the components section has been revised.

  13. EERE Success Story—Geothermal Technology Breakthrough in Alaska: Harvesting Heat below Boiling Temperatures

    Energy.gov [DOE]

    The Energy Department is supporting geothermal exploration at lower temperatures, thanks to a technology breakthrough that allows geothermal energy to be produced at temperatures below the boiling...

  14. Microsoft PowerPoint - 10 Paul Black

    Office of Environmental Management (EM)

    [Compatibility Mode] | Department of Energy 0 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] Microsoft PowerPoint - 10 Lee LCLS Lessons Learned PM Workshop Final [Compatibility Mode] (964.42 KB) More Documents & Publications LINAC Coherent Light Source Microsoft PowerPoint - 16.1045_Peer Reviews Panel_Lehman Workshop Briefing w-headings Microsoft PowerPoint - 09 Lehman final 1003 SC

  15. Water inventory management in condenser pool of boiling water reactor

    DOEpatents

    Gluntz, Douglas M.

    1996-01-01

    An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

  16. Water inventory management in condenser pool of boiling water reactor

    DOEpatents

    Gluntz, D.M.

    1996-03-12

    An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

  17. Boiling water neutronic reactor incorporating a process inherent safety design

    DOEpatents

    Forsberg, C.W.

    1985-02-19

    A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (nonborated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two water volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

  18. Boiling water neutronic reactor incorporating a process inherent safety design

    DOEpatents

    Forsberg, Charles W.

    1987-01-01

    A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

  19. Talking Points

    Energy Information Administration (EIA) (indexed site)

    Talking Points NATURAL GAS MARKET INTEGRITY: How EIA Helps Presentation by William F. Hederman Congressional Research Service at EIA 30 th Anniversary Conference April 8, 2008 ...

  20. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    9-000 CASL Program Highlights June 2015 Jess C. Gehin Oak Ridge National Laboratory June 30, 2015 1 First CASL Simulation of Departure from Nucleate Boiling Challenge Problem with VERA Completed * PWR Streamline Break (SLB) Event Simulated - Broken main steam pipe in one loop at hot zero power (HZP) - Core return to power with high peaking factor could lead to departure from nucleate boiling (DNB) on fuel rods * CASL Modeling Approach - Core boundary condition from system transient code - Core

  1. Feasibility study on the thorium fueled boiling water breeder reactor

    SciTech Connect

    PetrusTakaki, N.

    2012-07-01

    The feasibility of (Th,U)O 2 fueled, boiling water breeder reactor based on conventional BWR technology has been studied. In order to determine the potential use of water cooled thorium reactor as a competitive breeder, this study evaluated criticality, breeding and void reactivity coefficient in response to changes made in MFR and fissile enrichments. The result of the study shows that while using light water as moderator, low moderator to fuel volume ratio (MFR=0.5), it was possible to breed fissile fuel in negative void reactivity condition. However the burnup value was lower than the value of the current LWR. On the other hand, heavy water cooled reactor shows relatively wider feasible breeding region, which lead into possibility of designing a core having better neutronic and economic performance than light water with negative void reactivity coefficient. (authors)

  2. Analysis of scrams and forced outages at boiling water reactors

    SciTech Connect

    Earle, R. T.; Sullivan, W. P.; Miller, K. R.; Schwegman, W. J.

    1980-07-01

    This report documents the results of a study of scrams and forced outages at General Electric Boiling Water Reactors (BWRs) operating in the United States. This study was conducted for Sandia Laboratories under a Light Water Reactor Safety Program which it manages for the United States Department of Energy. Operating plant data were used to identify the causes of scrams and forced outages. Causes of scrams and forced outages have been summarized as a function of operating plant and plant age and also ranked according to the number of events per year, outage time per year, and outage time per event. From this ranking, identified potential improvement opportunities were evaluated to determine the associated benefits and impact on plant availability.

  3. BOILING WATER REACTOR WITH FEED WATER INJECTION NOZZLES

    DOEpatents

    Treshow, M.

    1963-04-30

    This patent covers the use of injection nozzles for pumping water into the lower ends of reactor fuel tubes in which water is converted directly to steam. Pumping water through fuel tubes of this type of boiling water reactor increases its power. The injection nozzles decrease the size of pump needed, because the pump handles only the water going through the nozzles, additional water being sucked into the tubes by the nozzles independently of the pump from the exterior body of water in which the fuel tubes are immersed. The resulting movement of exterior water along the tubes holds down steam formation, and thus maintains the moderator effectiveness, of the exterior body of water. (AEC)

  4. Nucleate boiling pressure drop in an annulus: Book 7

    SciTech Connect

    Not Available

    1992-11-01

    The application of the work described in this report is the production reactors at the Savannah River Site, and the context is nuclear reactor safety. The Loss of Coolant Accident (LOCA) scenario considered involves a double-ended break of a primary coolant pipe in the reactor. During a LOCA, the flow through portions of the reactor may reverse direction or be greatly reduced, depending upon the location of the break. The reduced flow rate of coolant (D{sub 2}O) through the fuel assembly channels of the reactor -- downflow in this situation -- can lead to boiling and to the potential for flow instabilities which may cause some of the fuel assembly channels to overheat and melt. That situation is to be avoided. The experimental approach is to provide a test annulus which simulates geometry, materials, and flow conditions in a Mark-22 fuel assembly (Coolant Channel 3) to the extent possible. The annulus has a full-scale geometry, and in fat uses SRL dummy hardware for the inner annulus wall in the ribbed geometry. The materials aluminum. The annulus is uniformly heated in the axial direction, but the circumferential heat flux can be varied to provide ``power tilt`` or asymmetric heating of the inner and outer annulus walls. The test facility uses H{sub 2}O rather than D{sub 2}O, but it includes the effects of dissolved helium gas present in the reactor. The key analysis approaches are: To compare the minima in the measured demand curves with analytical criteria, in particular the Saha-Zuber (1974) model; and to compare the pressure and temperature as a function of length in the annulus with an integral model for flow boiling in a heated channel. This document consists solely of tables of temperature measurements; minima, maxima, averages and standard deviations being measured.

  5. Nucleate boiling pressure drop in an annulus: Book 6

    SciTech Connect

    Not Available

    1992-11-01

    The application of the work described in this report is the production reactors at the Savannah River Site, and the context is nuclear reactor safety. The Loss of Coolant Accident (LOCA) scenario considered involves a double-ended break of a primary coolant pipe in the reactor. During a LOCA, the flow through portions of the reactor may reverse direction or be greatly reduced, depending upon the location of the break. The reduced flow rate of coolant (D{sub 2}O) through the fuel assembly channels of the reactor -- downflow in this situation -- can lead to boiling and to the potential for flow instabilities which may cause some of the fuel assembly channels to overheat and melt. That situation is to be avoided. The experimental approach is to provide a test annulus which simulates geometry, materials, and flow conditions in a Mark-22 fuel assembly (Coolant Channel 3) to the extent possible. The annulus has a full-scale geometry, and in fat uses SRL dummy hardware for the inner annulus wall in the ribbed geometry. The materials aluminum. The annulus is uniformly heated in the axial direction, but the circumferential heat flux can be varied to provide ``power tilt`` or asymmetric heating of the inner and outer annulus walls. The test facility uses H{sub 2}O rather than D{sub 2}O, but it includes the effects of dissolved helium gas present in the reactor. The key analysis approaches are: To compare the minima in the measured demand curves with analytical criteria, in particular the Saha-Zuber (1974) model; and to compare the pressure and temperature as a function of length in the annulus with an integral model for flow boiling in a heated channel. This document consists of a summary of temperature measurements to include recorded minima, maxima, averages and standard deviations.

  6. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1

    SciTech Connect

    1995-08-01

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

  7. Effect of surface roughness and polymeric additive on nucleate pool boiling at subatmospheric pressures

    SciTech Connect

    Tewari, P.K.; Verma, R.K.; Ramani, M.P.S.; Mahajan, S.P.

    1986-09-01

    This investigation pertains to boiling heat transfer from a submerged flat surface at subatmospheric and atmospheric pressures in the presence of hydroxy ethyl cellulose (HEC) as a polymeric additive in small doses. Boiling was carried out in presence of the additive on smooth and rough aluminium surfaces having effective cavity size within the range as predicted by Hsu model and the pressure was kept in the range of 8 - 100 KN/sq.m (abs). Effects of surface roughness, saturation pressure and polymer concentration on boiling heat transfer were studied and the results were compared with Rohsenow's correlation.

  8. New flow boiling heat transfer model for hydrocarbons evaporating inside horizontal tubes

    SciTech Connect

    Chen, G. F.; Gong, M. Q.; Wu, J. F.; Zou, X.; Wang, S.

    2014-01-29

    Hydrocarbons have high thermodynamic performances, belong to the group of natural refrigerants, and they are the main components in mixture Joule-Thomson low temperature refrigerators (MJTR). New evaluations of nucleate boiling contribution and nucleate boiling suppression factor in flow boiling heat transfer have been proposed for hydrocarbons. A forced convection heat transfer enhancement factor correlation incorporating liquid velocity has also been proposed. In addition, the comparisons of the new model and other classic models were made to evaluate its accuracy in heat transfer prediction.

  9. Improvements of fuel failure detection in boiling water reactors using helium measurements

    SciTech Connect

    Larsson, I.; Sihver, L.; Grundin, A.; Helmersson, J. O.

    2012-07-01

    To certify a continuous and safe operation of a boiling water reactor, careful surveillance of fuel integrity is of high importance. The detection of fuel failures can be performed by off-line gamma spectroscopy of off-gas samples and/or by on-line nuclide specific monitoring of gamma emitting noble gases. To establish the location of a leaking fuel rod, power suppression testing can be used. The accuracy of power suppression testing is dependent on the information of the delay time and the spreading of the released fission gases through the systems before reaching the sampling point. This paper presents a method to improve the accuracy of power suppression testing by determining the delay time and gas spreading profile. To estimate the delay time and examine the spreading of the gas in case of a fuel failure, helium was injected in the feed water system at Forsmark 3 nuclear power plant. The measurements were performed by using a helium detector system based on a mass spectrometer installed in the off-gas system. The helium detection system and the results of the experiment are presented in this paper. (authors)

  10. Multi-cycle boiling water reactor fuel cycle optimization

    SciTech Connect

    Ottinger, K.; Maldonado, G.I.

    2013-07-01

    In this work a new computer code, BWROPT (Boiling Water Reactor Optimization), is presented. BWROPT uses the Parallel Simulated Annealing (PSA) algorithm to solve the out-of-core optimization problem coupled with an in-core optimization that determines the optimum fuel loading pattern. However it uses a Haling power profile for the depletion instead of optimizing the operating strategy. The result of this optimization is the optimum new fuel inventory and the core loading pattern for the first cycle considered in the optimization. Several changes were made to the optimization algorithm with respect to other nuclear fuel cycle optimization codes that use PSA. Instead of using constant sampling probabilities for the solution perturbation types throughout the optimization as is usually done in PSA optimizations the sampling probabilities are varied to get a better solution and/or decrease runtime. The new fuel types available for use can be sorted into an array based on any number of parameters so that each parameter can be incremented or decremented, which allows for more precise fuel type selection compared to random sampling. Also, the results are sorted by the new fuel inventory of the first cycle for ease of comparing alternative solutions. (authors)

  11. Pebble Bed Boiling Water Reactor Concept With Superheated Steam

    SciTech Connect

    Tsiklauri, G.; Newman, D.; Meriwether, G.; Korolev, V. [Pacific Northwest National Laboratory, P.O. Box 999 Richland, WA 99352 (United States)

    2002-07-01

    An Advanced Nuclear Reactor concept is presented which extends Boiling Water Reactor technology with micro-fuel elements (MFE) and produces superheated steam. A nuclear plant with MFE is highly efficient and safe, due to ceramic-clad nuclear fuel. Water is used as both moderator and coolant. The fuel consists of spheres of about 1.5 mm diameter of UO{sub 2} with several external coatings of different carbonaceous materials. The outer coating of the particles is SiC, manufactured with chemical vapor disposition (CVD) technology. Endurance of the integrity of the SiC coating in water, air and steam has been demonstrated experimentally in Germany, Russia and Japan. This paper describes a result of a preliminary design and analysis of 3750 MWt (1500 MWe) plant with standard pressure of 16 MPa, which is widely achieved in the vessel of pressurized-water type reactors. The superheated steam outlet temperature of 550 deg. C elevates the steam cycle to high thermal efficiency of 42%. (authors)

  12. Aging study of boiling water reactor high pressure injection systems

    SciTech Connect

    Conley, D.A.; Edson, J.L.; Fineman, C.F.

    1995-03-01

    The purpose of high pressure injection systems is to maintain an adequate coolant level in reactor pressure vessels, so that the fuel cladding temperature does not exceed 1,200{degrees}C (2,200{degrees}F), and to permit plant shutdown during a variety of design basis loss-of-coolant accidents. This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging degradation. Guidelines from the United States Nuclear Regulatory Commission`s Nuclear Plant Aging Research Program were used in performing the aging study. Review and analysis of the failures reported in databases such as Nuclear Power Experience, Licensee Event Reports, and the Nuclear Plant Reliability Data System, along with plant-specific maintenance records databases, are included in this report to provide the information required to identify aging stressors, failure modes, and failure causes. Several probabilistic risk assessments were reviewed to identify risk-significant components in high pressure injection systems. Testing, maintenance, specific safety issues, and codes and standards are also discussed.

  13. Boiling-Water Reactor internals aging degradation study. Phase 1

    SciTech Connect

    Luk, K.H.

    1993-09-01

    This report documents the results of an aging assessment study for boiling water reactor (BWR) internals. Major stressors for BWR internals are related to unsteady hydrodynamic forces generated by the primary coolant flow in the reactor vessel. Welding and cold-working, dissolved oxygen and impurities in the coolant, applied loads and exposures to fast neutron fluxes are other important stressors. Based on results of a component failure information survey, stress corrosion cracking (SCC) and fatigue are identified as the two major aging-related degradation mechanisms for BWR internals. Significant reported failures include SCC in jet-pump holddown beams, in-core neutron flux monitor dry tubes and core spray spargers. Fatigue failures were detected in feedwater spargers. The implementation of a plant Hydrogen Water Chemistry (HWC) program is considered as a promising method for controlling SCC problems in BWR. More operating data are needed to evaluate its effectiveness for internal components. Long-term fast neutron irradiation effects and high-cycle fatigue in a corrosive environment are uncertainty factors in the aging assessment process. BWR internals are examined by visual inspections and the method is access limited. The presence of a large water gap and an absence of ex-core neutron flux monitors may handicap the use of advanced inspection methods, such as neutron noise vibration measurements, for BWR.

  14. Development of 1000 MWe Advanced Boiling Water Reactor

    SciTech Connect

    Kazuo Hisajima; Ken Uchida; Keiji Matsumoto; Koichi Kondo; Shigeki Yokoyama; Takuya Miyagawa [Toshiba Corporation (Japan)

    2006-07-01

    1000 MWe Advanced Boiling Water Reactor has only two main steam lines and six reactor internal pumps, whereas 1350 MWe ABWR has four main steam lines and ten reactor internal pumps. In order to confirm how the differences affect hydrodynamic conditions in the dome and lower plenum of the reactor pressure vessel, fluid analyses have been performed. The results indicate that there is not substantial difference between 1000 MWe ABWR and 1350 MWe ABWR. The primary containment vessel of the ABWR consists of the drywell and suppression chamber. The suppression chamber stores water to suppress pressure increase in the primary containment vessel and to be used as the source of water for the emergency core cooling system following a loss-of-coolant accident. Because the reactor pressure vessel of 1000 MWe ABWR is smaller than that of 1350 MWe ABWR, there is room to reduce the size of the primary containment vessel. It has been confirmed feasible to reduce inner diameter of the primary containment vessel from 29 m of 1350 MWe ABWR to 26.5 m. From an economic viewpoint, a shorter outage that results in higher availability of the plant is preferable. In order to achieve 20-day outage that results in 97% of availability, improvement of the systems for removal of decay heat is introduced that enables to stop all the safety-related decay heat removal systems except at the beginning of an outage. (authors)

  15. An experimental study of pool boiling heat transfer in reduced gravity

    SciTech Connect

    Shatto, D.P.; Renzi, K.I.; Peterson, G.P.; Morris, T.K.; Aaron, J.W.

    1996-12-31

    Experiments were performed in which pool boiling of pure water at reduced pressures was observed for behavior of the critical heatflux (CHF) and nucleate boiling heat transfer coefficients in a reduced gravitational environment. The experiments took place while alternating between microgravity and g/g{sub o} = 1.8 during parabolic flights aboard the NASA 930 (KC-135A). Heat transfer data were also obtained at Martian gravity levels (g/g{sub o} = 1/3). Parts of the test chamber were constructed of transparent materials to allow viewing and recording of the various boiling regimes encountered during the experiments. Results indicate that the onset of nucleate boiling occurred at lower heat fluxes in reduced gravity, resulting in higher two-phase heat transfer coefficients for g/g{sub o} < 1 than for g/g{sub o} = 1.8. In addition, the results indicate a significant reduction in the critical heat flux under reduced gravity conditions.

  16. CASL - Initial Modeling and Analysis of the Departure from Nucleate Boiling

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Challenge Problem Initial Modeling and Analysis of the Departure from Nucleate Boiling Challenge Problem Yixing Sung, Jin Yan, Zeses E. Karoutas of Westinghouse Electric Company LLC Anh V. Bui, Hongbin Zhang of Idaho National Laboratories Nam Dinh of North Carolina State University Departure from Nucleate Boiling (DNB) is one of the safety-related Challenge Problems (CP) that CASL is addressing in support of Pressurized Water Reactor (PWR) power uprate, high fuel burnup and plant lifetime

  17. MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

    SciTech Connect

    M. Ishii; S. T. Revankar; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; U. S. Rohatgi

    2003-06-16

    OAK B204 The overall goal of this three-year research project was to develop a new scientific design of a compact modular 200 MWe and a full size 1200 MWe simplified boiling water reactors (SBWR). Specific objectives of this research were: (1) to perform scientific designs of the core neutronics and core thermal-hydraulics for a small capacity and full size simplified boiling water reactor, (2) to develop a passive safety system design, (3) improve and validate safety analysis code, (4) demonstrate experimentally and analytically all design functions of the safety systems for the design basis accidents (DBA) and (5) to develop the final scientific design of both SBWR systems, 200 MWe (SBWR-200) and 1200 MWe (SBWR-1200). The SBWR combines the advantages of design simplicity and completely passive safety systems. These advantages fit well within the objectives of NERI and the Department of Energy's focus on the development of Generation III and IV nuclear power. The 3-year research program was structured around seven tasks. Task 1 was to perform the preliminary thermal-hydraulic design. Task 2 was to perform the core neutronic design analysis. Task 3 was to perform a detailed scaling study and obtain corresponding PUMA conditions from an integral test. Task 4 was to perform integral tests and code evaluation for the DBA. Task 5 was to perform a safety analysis for the DBA. Task 6 was to perform a BWR stability analysis. Task 7 was to perform a final scientific design of the compact modular SBWR-200 and the full size SBWR-1200. A no cost extension for the third year was requested and the request was granted and all the project tasks were completed by April 2003. The design activities in tasks 1, 2, and 3 were completed as planned. The existing thermal-hydraulic information, core physics, and fuel lattice information was collected on the existing design of the simplified boiling water reactor. The thermal-hydraulic design were developed. Based on a detailed integral

  18. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    SciTech Connect

    Aksan, S.N.; Stierli, F.; Analytis, G.T.

    1992-03-01

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended.

  19. Design and Testing of Vacuum Breaker Check Valve for Simplified Boiling Water Reactor

    SciTech Connect

    Ishii, M.; Xu, Y.; Revankar, S.T.

    2002-07-01

    A new design of the vacuum breaker check valve was developed to replace the mechanical valve in a simplified boiling water reactor. Scaling and design calculations were performed to obtain the geometry of new passive hydraulic vacuum breaker check valve. In order to check the valve performance, a RELAP5 model of the simplified boiling water reactor system with the new valve was developed. The valve was implemented in an integral facility, PUMA and was tested for large break loss of coolant accident. (authors)

  20. IWARS Final

    Energy Saver

    Appendices 1. Objective, Scope, and Methodology ......Finally, management felt that an expanded audit scope could have provided a more complete ...

  1. Final Optics

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    final optics Final Optics Schematic layout of NIF's final optics assembly (FOA). The suite of optics for one beamline is on the right. The final optics assemblies (FOAs) are the last element of the main laser system and the first of the target area systems. Each FOA contains four integrated optics modules (IOMs) that incorporate beam conditioning, frequency conversion, focusing, diagnostic sampling, and debris shielding capabilities into a single compact assembly. These optics are shown in the

  2. Natural Convection and Boiling for Cooling SRP Reactors During Loss of Circulation Conditions

    SciTech Connect

    Buckner, M.R.

    2001-06-26

    This study investigated natural convection and boiling as a means of cooling SRP reactors in the event of a loss of circulation accident. These studies show that single phase natural convection cooling of SRP reactors in shutdown conditions with the present piping geometry is probably not feasible.

  3. Explosive boiling of metals upon irradiation by a nanosecond laser pulse

    SciTech Connect

    Mazhukin, V I; Demin, M M; Shapranov, A V; Samokhin, A A

    2014-04-28

    A repeated effect of explosive boiling has been found in metals exposed to a nanosecond laser pulse in the framework of molecular dynamic simulations combined with a continuum description of a conduction band electrons system. This effect can be used, in particular, as a marker of approaching critical parameters of the region in the irradiated matter. (letters)

  4. Modeling the onset of flow instability for subcooled boiling in downflow

    SciTech Connect

    Qureshi, Z. ); Barry, J.J.; Crowley, C.J. )

    1990-01-01

    A postulated loss-of-coolant accident (LOCA) scenario for the Savannah River Plant (SRP) production reactors involves a double-ended break of a reactor primary coolant pipe. The flow of coolant (D{sub 2}O) in the reactor may decrease in such an event. As the flow into the reactor decreases, boiling may occur, followed by dryout and failure of the fuel due to overheating. A typical SRP fuel assembly consists of multiple concentric tubes containing the fuel and target materials. Coolant passes through the annular passages in the assembly in downflow. Under normal operating conditions, the flow rate is maintained high enough to suppress or minimize subcooled boiling, i.e. the flow remains essentially single phase throughout. At high coolant flow rates, the flow is single phase or partially developed subcooled boiling, and the pressure drop decreases with decreasing flow rate. Here friction dominates the pressure gradient, and the flow is stable. Below a certain flow rate, however, pressure drop may increase with decreasing flow rate. This occurs when significant voids are produced by boiling, resulting in a large acceleration component to the pressure drop. The negative slope of the curve leads to an instability because the pressure drop cannot adjust to compensate -- the flow is driven to a lower value. Overheating of the channel may result. 15 refs., 14 figs.

  5. Final EA

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment 1 In cooperation with the Bureau of Land Management Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment DEPARTMENT OF ENERGY Bonneville Power Administration DOE/EA-1952 April 2016 This document is the final Environmental Assessment (EA) for the proposed Lane-Wendson No. 1 Transmission Line Rebuild Project. Bonneville Power Administration (BPA) prepared this document as an

  6. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public ... Information 4 Background 5 Stormwater Pollution 5 Erosion and Sediment Control Workshop ...

  7. EA-1394: Final Environmental Assessment

    Office of Energy Efficiency and Renewable Energy (EERE)

    Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico

  8. Modeling and numerical simulation of oscillatory two-phase flows, with application to boiling water nuclear reactors

    SciTech Connect

    Rosa, M.P.; Podowski, M.Z.

    1995-09-01

    This paper is concerned with the analysis of dynamics and stability of boiling channels and systems. The specific objectives are two-fold. One of them is to present the results of a study aimed at analyzing the effects of various modeling concepts and numerical approaches on the transient response and stability of parallel boiling channels. The other objective is to investigate the effect of closed-loop feedback on stability of a boiling water reactor (BWR). Various modeling and computational issues for parallel boiling channels are discussed, such as: the impact of the numerical discretization scheme for the node containing the moving boiling boundary on the convergence and accuracy of computations, and the effects of subcooled boiling and other two-phase flow phenomena on the predictions of marginal stability conditions. Furthermore, the effects are analyzed of local loss coefficients around the recirculation loop of a boiling water reactor on stability of the reactor system. An apparent paradox is explained concerning the impact of changing single-phase losses on loop stability. The calculations have been performed using the DYNOBOSS computer code. The results of DYNOBOSS validation against other computer codes and experimental data are shown.

  9. FINAL RELEASE

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RELEASE AWARDEE: ____________________________________________________ The work under Award No. DE-__________________________, dated ______________, between the United States of America (represented by the Department of Energy, National Energy Technology Laboratory, and the undersigned awardee, having been completed and finally accepted , and in consideration of Final Payment thereunder, the United States of America, its officers, agents and employees are hereby released from all liabilities,

  10. Pressure suppression containment system for boiling water reactor

    DOEpatents

    Gluntz, Douglas M.; Nesbitt, Loyd B.

    1997-01-01

    A system for suppressing the pressure inside the containment of a BWR following a postulated accident. A piping subsystem is provided which features a main process pipe that communicates the wetwell airspace to a connection point downstream of the guard charcoal bed in an offgas system and upstream of the main bank of delay charcoal beds which give extensive holdup to offgases. The main process pipe is fitted with both inboard and outboard containment isolation valves. Also incorporated in the main process pipe is a low-differential-pressure rupture disk which prevents any gas outflow in this piping whatsoever until or unless rupture occurs by virtue of pressure inside this main process pipe on the wetwell airspace side of the disk exceeding the design opening (rupture) pressure differential. The charcoal holds up the radioactive species in the noncondensable gas from the wetwell plenum by adsorption, allowing time for radioactive decay before the gas is vented to the environs.

  11. Pressure suppression containment system for boiling water reactor

    DOEpatents

    Gluntz, D.M.; Nesbitt, L.B.

    1997-01-21

    A system is disclosed for suppressing the pressure inside the containment of a BWR following a postulated accident. A piping subsystem is provided which features a main process pipe that communicates the wetwell airspace to a connection point downstream of the guard charcoal bed in an offgas system and upstream of the main bank of delay charcoal beds which give extensive holdup to offgases. The main process pipe is fitted with both inboard and outboard containment isolation valves. Also incorporated in the main process pipe is a low-differential-pressure rupture disk which prevents any gas outflow in this piping whatsoever until or unless rupture occurs by virtue of pressure inside this main process pipe on the wetwell airspace side of the disk exceeding the design opening (rupture) pressure differential. The charcoal holds up the radioactive species in the noncondensable gas from the wetwell plenum by adsorption, allowing time for radioactive decay before the gas is vented to the environs. 3 figs.

  12. Critical Point Finder

    Energy Science and Technology Software Center

    2007-03-15

    The program robustly finds the critical points in the electric field generated by a specified collection of point charges.

  13. Final Report

    SciTech Connect

    Gurney, Kevin R

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  14. Final Report

    SciTech Connect

    Biros, George

    2014-08-18

    This the final report for the project "Large-Scale Optimization for Bayesian Inference in Complex Systems," for the work in the group of the co-PI George Biros.

  15. Final Report

    SciTech Connect

    DeTar, Carleton

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  16. Final Agenda

    Office of Environmental Management (EM)

    Abuse Programs at DOE Sites | Department of Energy Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites January 23, 2008 The Department of Energy (DOE) today published a final rule to amend the Department's regulations to decrease the random drug testing rate of DOE contractor employees in testing designated positions (TDP). Today's final rule

  17. Paducah Gaseous Diffusion Plant Final Environmental Assessment...

    Energy Saver

    Point of contact for more information: Robert Smith, Department of Energy-Paducah Paducah Gaseous Diffusion Plant Final Environmental Assessment for Potential Land and Facilities ...

  18. Explosive boiling of a metallic glass superheated by nanosecond pulse laser ablation

    SciTech Connect

    Jiang, M. Q. E-mail: lhdai@lnm.imech.ac.cn; Wei, Y. P.; Wilde, G.; Dai, L. H. E-mail: lhdai@lnm.imech.ac.cn

    2015-01-12

    We report an explosive boiling in a Zr-based (Vitreloy 1) bulk metallic glass irradiated by a nanosecond pulse laser with a single shot. This critical phenomenon is accompanied by the ejection of high-temperature matter from the target and the formation of a liquid-gas spinodal pattern on the irradiated area. An analytical model reveals that the glassy target experiences the normal heating (melting) and significant superheating, eventually culminating in explosive boiling near the spinodal limit. Furthermore, the time lag of nucleation and the critical radius of vapor bubbles are theoretically predicted, which are in agreement with the experimental observations. This study provides the investigation on the instability of a metallic glass liquid near the thermodynamic critical temperature.

  19. Multi-scale Control and Enhancement of Reactor Boiling Heat Flux by Reagents and Nanoparticles

    SciTech Connect

    Manglik, R M; Athavale, A; Kalaikadal, D S; Deodhar, A; Verma, U

    2011-09-02

    The phenomenological characterization of the use of non-invasive and passive techniques to enhance the boiling heat transfer in water has been carried out in this extended study. It provides fundamental enhanced heat transfer data for nucleate boiling and discusses the associated physics with the aim of addressing future and next-generation reactor thermal-hydraulic management. It essentially addresses the hypothesis that in phase-change processes during boiling, the primary mechanisms can be related to the liquid-vapor interfacial tension and surface wetting at the solidliquid interface. These interfacial characteristics can be significantly altered and decoupled by introducing small quantities of additives in water, such as surface-active polymers, surfactants, and nanoparticles. The changes are fundamentally caused at a molecular-scale by the relative bulk molecular dynamics and adsorption-desorption of the additive at the liquid-vapor interface, and its physisorption and electrokinetics at the liquid-solid interface. At the micro-scale, the transient transport mechanisms at the solid-liquid-vapor interface during nucleation and bubblegrowth can be attributed to thin-film spreading, surface-micro-cavity activation, and micro-layer evaporation. Furthermore at the macro-scale, the heat transport is in turn governed by the bubble growth and distribution, macro-layer heat transfer, bubble dynamics (bubble coalescence, collapse, break-up, and translation), and liquid rheology. Some of these behaviors and processes are measured and characterized in this study, the outcomes of which advance the concomitant fundamental physics, as well as provide insights for developing control strategies for the molecular-scale manipulation of interfacial tension and surface wetting in boiling by means of polymeric reagents, surfactants, and other soluble surface-active additives.

  20. Boiling Water Reactor Fuel Cycle Optimization for Prevention of Channel-Blade Interference

    SciTech Connect

    Kropaczek, David J.; Karve, Atul A.; Oyarzun, Christian C.; Asgari, Mehdi

    2006-07-01

    A formal optimization method for eliminating the potential of Boiling Water Reactor channel-blade interference is presented within the context of fuel cycle design. The method is based on the use of threshold constraints on blade force as penalty terms within an objective function that are employed as part of a search algorithm. Results demonstrate the effectiveness of the constraint formulation in eliminating channel-blade interference as part of the design of the core loading and operational strategy. (authors)

  1. Test Plan for the Boiling Water Reactor Dry Cask Simulator

    SciTech Connect

    Durbin, Samuel; Lindgren, Eric R.

    2015-11-01

    canister. The symmetric single assembly geometry with well-controlled boundary conditions simplifies interpretation of results. Various configurations of outer concentric ducting will be used to mimic conditions for above and below-ground storage configurations of vertical, dry cask systems with canisters. Radial and axial temperature profiles will be measured for a wide range of decay power and helium cask pressures. Of particular interest is the evaluation of the effect of increased helium pressure on allowable heat load and the effect of simulated wind on a simplified below ground vent configuration. While incorporating the best available information, this test plan is subject to changes due to improved understanding from modeling or from as-built deviations to designs. As-built conditions and actual procedures will be documented in the final test report.

  2. Experiment and RELAP5 Analysis for the Downcomer Boiling of APR1400 under LBLOCA

    SciTech Connect

    Dong Won Lee; Hee Cheon No; Eu Hwak Lee; Seung Jong Oh; Chul-Hwa Song

    2004-07-01

    The direct vessel injection (DVI) mode of a safety injection system is adopted instead of a conventional cold leg injection (CLI) mode as one of the advanced design features of the APR1400 (Advanced Power Reactor 1400 MW). From the calculation results of RELAP5 with full plant, it is found out that the sudden boiling happens in the downcomer due to heat transfer from the reactor vessel wall and it can affect the reactor safety. In the present study, experimental tests are carried out to observe the actual boiling phenomena in the downcomer and to validate RELAP5. The heated wall of test section has its thickness of 8.2 cm and the same material as the prototype (APR1400) with chrome coating against rusting. From the experiment, we visually observe the vapor jetting near the heated wall with small bubble migration to the bulk region and liquid circulation. The data shows a rapid wall temperature drop generating a large amount of vapor initially. The calculation results of RELAP5 using the three nodal schemes are compared with experimental ones in aspects of water level, void fraction, wall temperatures and phase velocities. It turns out that the double nodal scheme with circulation produces better results than the nodal scheme without circulation to simulate the boiling phenomena in the downcomer. (authors)

  3. Effect of subcooling and wall thickness on pool boiling from downward-facing curved surfaces in water

    SciTech Connect

    El-Genk, M.S.; Glebov, A.G.

    1995-09-01

    Quenching experiments were performed to investigate the effects of water subcooling and wall thickness on pool boiling from a downward-facing curved surface. Experiments used three copper sections of the same diameter (50.8 mm) and surface radius (148 mm), but different thickness (12.8, 20 and 30 mm). Local and average pool boiling curves were obtained at saturation and 5 K, 10 K, and 14 K subcooling. Water subcooling increased the maximum heat flux, but decreased the corresponding wall superheat. The minimum film boiling heat flux and the corresponding wall superheat, however, increased with increased subcooling. The maximum and minimum film boiling heat fluxes were independent of wall thickness above 20 mm and Biot Number > 0.8, indicating that boiling curves for the 20 and 30 thick sections were representative of quasi steady-state, but not those for the 12.8 mm thick section. When compared with that for a flat surface section of the same thickness, the data for the 12.8 mm thick section showed significant increases in both the maximum heat flux (from 0.21 to 0.41 MW/m{sup 2}) and the minimum film boiling heat flux (from 2 to 13 kW/m{sup 2}) and about 11.5 K and 60 K increase in the corresponding wall superheats, respectively.

  4. A Compilation of Boiling Water Reactor Operational Experience for the United Kingdom's Office for Nuclear Regulation's Advanced Boiling Water Reactor Generic Design Assessment

    SciTech Connect

    Wheeler, Timothy A.; Liao, Huafei

    2014-12-01

    United States nuclear power plant Licensee Event Reports (LERs), submitted to the United States Nuclear Regulatory Commission (NRC) under law as required by 10 CFR 50.72 and 50.73 were evaluated for reliance to the United Kingdom’s Health and Safety Executive – Office for Nuclear Regulation’s (ONR) general design assessment of the Advanced Boiling Water Reactor (ABWR) design. An NRC compendium of LERs, compiled by Idaho National Laboratory over the time period January 1, 2000 through March 31, 2014, were sorted by BWR safety system and sorted into two categories: those events leading to a SCRAM, and those events which constituted a safety system failure. The LERs were then evaluated as to the relevance of the operational experience to the ABWR design.

  5. Floating Point Control Library

    Energy Science and Technology Software Center

    2007-08-02

    Floating Point Control is a Library that allows for the manipulation of floating point unit exception masking funtions control exceptions in both the Streaming "Single Instruction, Multiple Data" Extension 2 (SSE2) unit and the floating point unit simultaneously. FPC also provides macros to set floating point rounding and precision control.

  6. Village of Rouses Point, New York (Utility Company) | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    @rousespoint Facebook: https:www.facebook.compagesRouses-Point184314958261895?vwall Outage Hotline: (518) 297-5502, ext. 314 References: EIA Form EIA-861 Final Data File...

  7. Final Report

    SciTech Connect

    Marchant, Gary E.

    2013-04-23

    This is the final report of a two year project entitled "Governing Nanotechnology Risks and Benefits in the Transition to Regulation: Innovative Public and Private Approaches." This project examined the role of new governance or "soft law" mechanisms such as codes of conduct, voluntary programs and partnership agreements to manage the risks of emerging technologies such as nanotechnology. A series of published or in publication papers and book chapters are attached.

  8. Microsoft PowerPoint - M Rourk Presentation FINAL.pptx

    Energy Information Administration (EIA) (indexed site)

    424 and other standard forms with CFDA number, description of the program, to save you time - status available for application - documents are automatically uploaded into STRIPES...

  9. Microsoft PowerPoint - ZERH Lighting Efficiency - FINAL w bios

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    READY HOME: LIGHTING EFFICIENCY Presented by: Brooke Silber, LC, IES, LEED AP - Jan & Brooke Luminae David Brignati, AIA, LEED AP - Newport Ventures High Efficacy Lighting in DOE ...

  10. Microsoft PowerPoint - Chairs - Topics and Achievements (FINAL...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... DOE's path forward for D&D * Multiple educational outreach initiatives that benefit ... * Thereby increasing the risk to the environment & workers and increasing the life cycle ...

  11. Microsoft PowerPoint - Hydropower conf SDOX June 2008 final ...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Southwestern Federal Hydropower Conference June 12, 2008 ... WWTP How Does the Technology Provide Advantages? ... Bad for shallow systems (tailrace) as bubble leave ...

  12. Microsoft PowerPoint - SWL HPConf2009 (final).ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    REFUGE AUGUSTA STUTTGART HELENA WHITE RIVER NATIONAL0 WILDLIFE REFUGE GREERS FERRY RESERVOIR N Little Rock District, Southwestern Division *Watershed Comprises -...

  13. Microsoft PowerPoint - Goldner - NEAC Presentation (FINAL)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... loss of active cooling in the reactor core for a considerably longer time period ... Improved Cladding Properties -Clad fracture -Geometric stability -Thermal shock resistance ...

  14. Microsoft PowerPoint - conti_conference_Final.ppt

    Energy Information Administration (EIA) (indexed site)

    ethanol by 2022 1 billion gallon of biodiesel by 2012 * Other Efficiency Standards ... Energy Independence and Security Act of 2007 Frozen Includes ethanol, biodiesel, and ...

  15. Microsoft PowerPoint - ACposter_final2.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Cialella 1 , R. Wagener 1 , R. Jundt 2 , and C. Bates 2 1 Brookhaven National Laboratory, Upton, NY 2 Pacific Northwest Laboratory, Richland, WA Give it a try... http://www.arm.gov/sites (Best viewed in Firefox) Comments and suggestions welcomed (cialella@bnl.gov) KEY FEATURES FUTURE WORK Continue adding Instrument maps for each ACRF facility Add next China AMF site Add aerial photos for each site, when/if available Ultimately link all site maps through the ARM Google Maps site

  16. Microsoft PowerPoint - FNALgeorgiak_final_nobackup

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    e Appearance Results Georgia Karagiorgi, MIT FNAL - December 11, 2008 12/11/2008 FNAL W&C Outline 1. Motivation for e appearance search 2. MiniBooNE Experiment 3. MiniBooNE e analysis 4. Results * Oscillation fits * Implications for low energy excess observed in neutrino mode 5. Future prospects and conclusions Y.Liu, D.Perevalov, I.Stancu University of Alabama S.Koutsoliotas Bucknell University E.Hawker, R.A.Johnson, J.L.Raaf University of Cincinnati T. L. Hart, R.H.Nelson, M.Tzanov,

  17. Microsoft PowerPoint - HAB 2012 Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    fe a n d E ff e c ti v e C le a n u p th a t P ro te c ts th e C o lu m b ia R iv e r Re du ce s th e Ac tiv e Sit e Fo ot pr int of Cl ea nu p to 75 Sq ua re Mi les (5 86 to 75 ) Sig ni fic an tly Re du ce s Lo ng -T erm Mo rtg ag e Co st s At Co m pl eti on , Sh ift s Em ph as is an d Re so ur ce s to Fu ll of th e Ce nt ra l Pla tea u (7 5 sq ua re m ile s) Re du ce s Co st s by "R i Mi ss io Ri ch la nd O pe ra tio ns Of fic e B & C Ar ea Inte rim Saf e Sto rag e f N Ar ea Inte rim

  18. Microsoft PowerPoint - News Flash_FINAL_073009_vvb

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    July 30, 2009 Moab Steps Up the Pace of Mill Tailings Shipments U.S. Department of Energy For more information on EM Recovery Act, visit: www.em.doe.gov/emrecovery Recovery Act funds ($108 million) are being used to accelerate the frequency of uranium mill tailings shipments from the Moab Uranium Mill Tailings Remedial Action (UMTRA) Project site to a disposal site near Crescent Junction, Utah. Mill tailings are a byproduct of uranium mining and processing. Located northwest of Moab in Grand

  19. Microsoft PowerPoint - WIPP Recovery Workshop_Final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    WIPP Recovery Workshop U.S. Department of Energy Waste Isolation Pilot Plant January 14, 2015 1 Agenda * Introduction and Workshop Objective * WIPP Recovery Approach * Interim Performance Measurement Baseline * WIPP Recovery Project Summary Level Schedule * Questions and Answers 2 Introductions and Workshop Objective * Introductions * The objective of this workshop is to provide a forum for a detailed discussion of the WIPP Recovery Project Interim Baseline and to address stakeholder questions

  20. Microsoft PowerPoint - cldclass_final_v.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase A Value Added Product for Cloud Type and Cloud Phase Classification Classification Classification Classification Classification

  1. Microsoft PowerPoint - Materials Workshop at ORNL - FINAL - refined...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Next Generation Components 16 * The future grid will have more advanced components and systems across transmission and distribution - HVDCMVDC Networks - Power Flow Controllers - ...

  2. Microsoft PowerPoint - 1st Quarter 2009 Presentation - Final...

    Office of Legacy Management (LM)

    ... standard for Walnut Creek and Woman Creek (Big Dry Creek segments 4a, 4b, and 5), ... Water below MCL (based on 85th percentile of data) is considered in attainment with ...

  3. Microsoft PowerPoint - FinalModule5.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... you have installed 12 mainframes, which means you are 30% complete with the total job. ... not required. Disadvantages: Customer Satisfaction maybe low due to the subjectiveness ...

  4. Microsoft PowerPoint - SWPA Transformer Oil Spill Risk Final...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    to the issue of secondary containment of oil for transformers in service at Corps ... Scope Scope 397,000 Gallons of Oil 397,000 Gallons of Oil 69 Transformers 69 Transformers ...

  5. Microsoft PowerPoint - CY12 Annual Report Presentation - final...

    Office of Legacy Management (LM)

    Protection of Surface Water 9 Groundwater Analytical Data, 2012 89 wells sampled once to four times each Over 6000 analytical records 10 11 11 Highlights from 2012 ...

  6. Microsoft PowerPoint - SWL HPConf2010 (final).pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... WHITE RIVER NATIONAL0 WILDLIFE REFUGE Lock and Dam No 1 Little Rock District, Southwestern ... Pine Mountain Dam * Authorized in 1965 and reevaluated in 1980 * Authorized plan includes ...

  7. Microsoft PowerPoint - SWPA Transformer Oil Spill Risk Final...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    a system wide response to the issue of secondary containment of oil for transformers in service at Corps powerhouses and dam switchyards within Southwestern's marketing area. ...

  8. Microsoft PowerPoint - Final Presenattion - Ferrigno-Papay.EM...

    Office of Environmental Management (EM)

    1A: Modeling for Life Cycle Cost Analysis (LCCA) Charge 1A: Modeling for Life Cycle Cost ... that includes a operations- -focused software tool to be used focused software tool to ...

  9. Microsoft PowerPoint - Final CLWR SEIS PUBLIC SCOPING PRESENTATION...

    National Nuclear Security Administration (NNSA)

    Impact Statement for the Impact Statement for the Production of Tritium in a Commercial Light Water Commercial Light Water Reactor Public Scoping Meeting October 20 2011 October ...

  10. Microsoft PowerPoint - FinalModule7.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    7: Integrated Baseline Review and Change Control Prepared by: Module 7 - Integrated Baseline Review and Change Control 1 Prepared by: Booz Allen Hamilton Module 7: Integrated ...

  11. Microsoft PowerPoint - FinalModule8.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Prepared by: Booz Allen Hamilton Module 8: Government Required Reports Welcome to Module ... Prepared by: Booz Allen Hamilton Review of Previous Modules In the previous seven modules, ...

  12. Microsoft PowerPoint - Chairs - Topics and Achievements (FINAL)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    September 17, 2014 www.energy.gov/EM 2 Hanford Advisory Board Achievements : * With the decommissioning of the Plutonium Finishing Plant's "McCluskey Room," the Hanford Nuclear Reservation has added a significant and dramatic episode to its complex and demanding cleanup narrative. * In 1976 Harold McCluskey was exposed to a massive dose of radioactive americium following a reaction explosion that occurred in a glove box where he was working. McCluskey survived, and the room was placed

  13. Microsoft PowerPoint - Flohr - Budget Update (FINAL)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Connie Flohr Acting Deputy Assistant Secretary for Program Planning and Budget EM Budget Update September 17, 2014 Click to edit Master title style Click to edit Master subtitle style www.energy.gov/EM 2 Oct. Jan. 17 th : EM funding level at $5.8 B for FY 2014, $209 M above request Oct. 1-16, 2013: Lapse in Appropriations March 4 th : President releases FY 2015 budget request, $5.622 B for EM Oct. 17 tH : Congress passes Continuing Resolution, ending lapse in appropriations Sep. 30 th - Deadline

  14. Microsoft PowerPoint - Johnson - How EM Does Business (FINAL)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    How EM Does Business Thomas Johnson, Jr. Associate Deputy Assistant Secretary for Acquisition and Project Management Environmental Management Site-Specific Advisory Board Chairs Meeting September 17, 2014 www.energy.gov/EM 2 Procurement Policy Implementation * Ensure contracts align with taxpayer interests and structure contracts so contractors bear responsibility * Hold contractors accountable for overruns due to negligence * Share savings due to better-than-promised performance * Improve

  15. Microsoft PowerPoint - ZERH Lighting Efficiency - FINAL w bios

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    READY HOME: LIGHTING EFFICIENCY Presented by: Brooke Silber, LC, IES, LEED AP - Jan & Brooke Luminae David Brignati, AIA, LEED AP - Newport Ventures High Efficacy Lighting in DOE Zero Energy Ready Home LEDs in High Performance Homes ... - Practical Experience * LEDs are increasingly used in DOE ZERHs * Design can be different... * Building integration can be different... * User experience should be different! BROOKE SILBER C. Brooke Silber, IES, LC, LEEDAP Principal, Jan & Brooke,

  16. Microsoft PowerPoint - wiser naruc rps final 304.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Technologies Division * Energy Analysis Department Renewables Portfolio Standards: What Are We Learning? Ryan H. Wiser Lawrence Berkeley National Laboratory rhwiser@lbl.gov; 510-486-5474 NARUC Winter Conference Washington, D.C. March 9, 2004 Environmental Energy Technologies Division * Energy Analysis Department Presentation Outline Overview of the RPS Where have RPS policies been implemented in the United States? What positive impacts have been generated by these policies? What pitfalls

  17. Microsoft PowerPoint - FinalModule6.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... There are multiple ways to develop an EAC. The technique selected is based upon the dollar value of the project, the risk, accounting system available and the accuracy of the ...

  18. Microsoft PowerPoint - Final Presentation - EMAB EM-1 Presentation...

    Office of Environmental Management (EM)

    vitality of our communities and the nation and positions our Sites for future missions and use Our mission is not discretionary - it is a congressional mandate to D&D the ...

  19. Microsoft PowerPoint - CY09 Annual Report Presentation - final...

    Office of Legacy Management (LM)

    ... Selected Highlights From 2009: SPPTS Solar Ponds Plume * Source area not sampled in 2009 * ... of Phases II (uranium treatment cell) and III (pilot- scale nitrate cells) ...

  20. Microsoft PowerPoint - Improving Data Integrity final draft_072412...

    Energy Information Administration (EIA) (indexed site)

    been reported over the past three weeks within a State, select the option circled in red 18 David Dudley, Improving Data Quality EIA, August 14, 2012 19 David Dudley, Improving...

  1. Microsoft PowerPoint - HPC - Operations and Monitoring_Final...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    to send log data while providing a plug and play architecture for any new analysis ... RabbitMQ. * Splunk is our main data analysis tool, providing easy to use dashboards. ...

  2. Microsoft PowerPoint - Final 2015 Annual Report presentation...

    Office of Legacy Management (LM)

    ... * Wetlands continue to establish 33 Wildlife Monitoring Prairie dog monitoring * No active prairie dog towns within the COU Nest boxes * 14 of 21 boxes used in 2015 ...

  3. Microsoft PowerPoint - Final Presentation - Surash.021611 EMAB...

    Office of Environmental Management (EM)

    and Contract Management U.S. Department of Energy Bill Murphie Site Manager Portsmouth and Paducah Project Office U.S. Department of Energy February 24, 2011 Improve contract and ...

  4. Microsoft PowerPoint - Borak - EM SSAB 20 Years (FINAL)

    Office of Environmental Management (EM)

    What is the EM SSAB? * Chartered under FACA to provide input regarding the cleanup of Cold War legacy sites in the U.S. * Comprised of as many as 11 local boards at one time. * ...

  5. Microsoft PowerPoint - Final Presentation - Olinger.EMAB Presentation...

    Office of Environmental Management (EM)

    ... concrete 257,000 cubic yards concrete 34,600 tons structural steel 34,600 tons structural steel Complete the three major tank waste Complete the three major tank waste ...

  6. Microsoft PowerPoint - MO Orientation Final 6 4 07

    Energy.gov [DOE] (indexed site)

    beforeon schedule Department of Energy 4 What is GFPR (cont) *Philosophy whereby work is performed with minimal contract focus on process *Focus is on Results with...

  7. Microsoft PowerPoint - SSAB Chairs Spring 2015 Marcinowski final...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    - Soot cleaning of electrical panels * Expedite mine stability * Initial ... Handled RH - Remote Handled SNF - Spent Nuclear Fuel SNF IDAHO SITE NR SNF DOECommercial ...

  8. Microsoft PowerPoint - Marcinowski - Waste Management (FINAL...

    Office of Environmental Management (EM)

    WIPP, Tank Waste and Other Waste Disposition Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Fall Meeting - ...

  9. Microsoft PowerPoint - SSAB Presentation - April 2015_OMB Final...

    Office of Environmental Management (EM)

    ... EM identifies request for programmatic requirements including all environmental compliance requirements in official OMB budget justification document (OMBJ) OMB funding decision ...

  10. Microsoft PowerPoint - FinalModule2.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Management Book, the work is broken down into all the discrete elements of work, the total sum of which represents all the work and products necessary to produce the book. dynamic ...

  11. Microsoft PowerPoint - FinalModule3.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Scheduling * Define and Illustrate Basic Scheduling Concepts * Define Logic Relationships ... Scheduling is: ...Forming a network of activities and event relationships that portrays ...

  12. Microsoft PowerPoint - FinalModule4.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... used to facilitate the requirement for integrating these ... by Control Accounts, Work Packages, and Planning Packages. ... (hours andor dollars), material, other direct costs and ...

  13. Microsoft PowerPoint - ORP's Agency Update (Final).pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Kevin Smith, Manager U.S. Department of Energy - Office of River Protection September 9, 2015 Hanford Advisory Board Annual Agency Update for the Office of River Protection 2 ...

  14. Method of and apparatus for determining deposition-point temperature

    DOEpatents

    Mansure, A.J.; Spates, J.J.; Martin, S.J.

    1998-10-27

    Acoustic-wave sensor apparatus and method are disclosed for analyzing a normally liquid petroleum-based composition for monitoring deposition-point temperature. The apparatus includes at least one acoustic-wave device such as SAW, QCM, FPM, TSM or APM type devices in contact with the petroleum-based composition for sensing or detecting the surface temperature at which deposition occurs and/or rate of deposition as a function of temperature by sensing an accompanying change in frequency, phase shift, damping voltage or damping current of an electrical oscillator to a known calibrated condition. The acoustic wave device is actively cooled to monitor the deposition of constituents such as paraffins by determining the point at which solids from the liquid composition begin to form on the acoustic wave device. The acoustic wave device can be heated to melt or boil off the deposits to reset the monitor and the process can be repeated. 5 figs.

  15. Method of and apparatus for determining deposition-point temperature

    DOEpatents

    Mansure, Arthur J.; Spates, James J.; Martin, Stephen J.

    1998-01-01

    Acoustic-wave sensor apparatus and method for analyzing a normally liquid petroleum-based composition for monitoring deposition-point temperature. The apparatus includes at least one acoustic-wave device such as SAW, QCM, FPM, TSM or APM type devices in contact with the petroleum-based composition for sensing or detecting the surface temperature at which deposition occurs and/or rate of deposition as a function of temperature by sensing an accompanying change in frequency, phase shift, damping voltage or damping current of an electrical oscillator to a known calibrated condition. The acoustic wave device is actively cooled to monitor the deposition of constituents such as paraffins by determining the point at which solids from the liquid composition begin to form on the acoustic wave device. The acoustic wave device can be heated to melt or boil off the deposits to reset the monitor and the process can be repeated.

  16. Modeling Single-Phase and Boiling Liquid Jet Impingement Cooling in Power Electronics

    SciTech Connect

    Narumanchi, S. V. J.; Hassani, V.; Bharathan, D.

    2005-12-01

    Jet impingement has been an attractive cooling option in a number of industries over the past few decades. Over the past 15 years, jet impingement has been explored as a cooling option in microelectronics. Recently, interest has been expressed by the automotive industry in exploring jet impingement for cooling power electronics components. This technical report explores, from a modeling perspective, both single-phase and boiling jet impingement cooling in power electronics, primarily from a heat transfer viewpoint. The discussion is from the viewpoint of the cooling of IGBTs (insulated-gate bipolar transistors), which are found in hybrid automobile inverters.

  17. A study of out-of-phase power instabilities in boiling water reactors

    SciTech Connect

    March-Leuba, J.; Blakeman, E.D.

    1988-06-20

    This paper presents a study of the stability of subcritical neutronic modes in boiling water reactors that can result in out-of-phase power oscillations. A mechanism has been identified for this type of oscillation, and LAPUR code has been modified to account for it. Numerical results show that there is a region in the power-flow operating map where an out-or-phase stability mode is likely even if the core-wide mode is stable. 4 refs., 7 figs.

  18. Local pressure gradients due to incipience of boiling in subcooled flows

    SciTech Connect

    Ruggles, A.E.; McDuffee, J.L.

    1995-09-01

    Models for vapor bubble behavior and nucleation site density during subcooled boiling are integrated with boundary layer theory in order to predict the local pressure gradient and heat transfer coefficient. Models for bubble growth rate and bubble departure diameter are used to scale the movement of displaced liquid in the laminar sublayer. An added shear stress, analogous to a turbulent shear stress, is derived by considering the liquid movement normal to the heated surface. The resulting mechanistic model has plausible functional dependence on wall superheat, mass flow, and heat flux and agrees well with data available in the literature.

  19. CASL-U-2015-0248-000 Modeling Boiling Water Reactor

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    8-000 Modeling Boiling Water Reactor Designs using MPACT Andrew P. Fitzgerald Brendan Kochunas Daniel Jabaay Thomas Downar University of Michigan July 7, 2015 CASL-U-2015-0248-000 ATRIUM TM 10: K-inf vs burn-up for the ATRIUM TM 10 lattice from various transport codes. MPACT is shown to have the ability to model some BWR features such as (square) channel boxes, water rods, and water channels with reasonable accuracy. The ATRIUM TM 10 comparison has shown MPACT can predict k-inf with similar

  20. Final Report

    SciTech Connect

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  1. Resistivity During Boiling in the SB-15-D Core from the Geysers Geothermal Field: The Effects of Capillarity

    SciTech Connect

    Roberts, J.; Duba, A.; Bonner, B.; Kasameyer, P.

    1997-01-01

    In a laboratory study of cores from borehole SB-15-D in The Geysers geothermal area, we measured the electrical resistivity of metashale with and without pore-pressure control, with confining pressures up to 100 bars and temperatures between 20 and 150 C, to determine how the pore-size distribution and capillarity affected boiling. We observed a gradual increase in resistivity when the downstream pore pressure or confining pressure decreased below the phase boundary of free water. For the conditions of this experiment, boiling, as indicated by an increase in resistivity, is initiated at pore pressures of approximately 0.5 to 1 bar (0.05 to 0.1 MPa) below the free-water boiling curve, and it continues to increase gradually as pressure is lowered to atmospheric. A simple model of the effects of capillarity suggests that at 145 C, less than 15% of the pore water can boil in these rocks. If subsequent experiments bear out these preliminary observations, then boiling within a geothermal reservoir is controlled not just by pressure and temperature but also by pore-size distribution. Thus, it may be possible to determine reservoir characteristics by monitoring changes in electrical resistivity as reservoir conditions change.

  2. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    surveys sampling * Evaluate results * Perform independent verification * Finalize clearance documents Key Requirements Affecting DOE Land Conveyance Activities Steps in the ...

  3. End Points Specification Methods

    Energy.gov [DOE]

    Two methods to develop end point specifications are presented. These have evolved from use in the field for deactivation projects.

  4. Pool boiling of R-114/oil mixtures from single tubes and tube bundles. Master's thesis

    SciTech Connect

    Murphy, T.J.

    1987-09-01

    An apparatus was designed, fabricated, and operated for the testing of horizontal tube bundles for boiling of R-114 with various concentrations of oil. Preliminary data were taken on the top tube in the bundle, with and without the other tubes in operation. Results showed up to a 37% increase in the boiling heat-transfer coefficient as a result of the favorable bundle effect. In a separate single-tube apparatus, three enhanced tubes were tested at a saturation temperature of 2.2 C with oil mass concentrations of 0, 1, 2, 3, 6 and 10%. The tubes were: 1) a finned tube with 1024 fins per meter, 2) a finned tube with 1575 fins per meter and 3) a Turbo-B tube. These tubes resulted in enhancement ratios in pure refrigerant of 2.8, 3.8 and 5.2, respectively, at a practical heat flux of 30 kW/sq. meter. With 3% oil, these ratios were decreased to 2.6, 3.5 and 5, while with 10% oil, these ratios were further reduced to 2.6, 3.2 and 4.7, respectively. Based on these results, the use of Turbo-B tubes is expected to result in significant savings in weight and size of evaporators over the finned tubes presently in use on board some naval vessels.

  5. Performance of Charcoal Cookstoves for Haiti Part 1: Results from the Water Boiling Test

    SciTech Connect

    Booker, Kayje; Han, Tae Won; Granderson, Jessica; Jones, Jennifer; Lsk, Kathleen; Yang, Nina; Gadgil, Ashok

    2011-06-01

    In April 2010, a team of scientists and engineers from Lawrence Berkeley National Lab (LBNL) and UC Berkeley, with support from the Darfur Stoves Project (DSP), undertook a fact-finding mission to Haiti in order to assess needs and opportunities for cookstove intervention. Based on data collected from informal interviews with Haitians and NGOs, the team, Scott Sadlon, Robert Cheng, and Kayje Booker, identified and recommended stove testing and comparison as a high priority need that could be filled by LBNL. In response to that recommendation, five charcoal stoves were tested at the LBNL stove testing facility using a modified form of version 3 of the Shell Foundation Household Energy Project Water Boiling Test (WBT). The original protocol is available online. Stoves were tested for time to boil, thermal efficiency, specific fuel consumption, and emissions of CO, CO{sub 2}, and the ratio of CO/CO{sub 2}. In addition, Haitian user feedback and field observations over a subset of the stoves were combined with the experiences of the laboratory testing technicians to evaluate the usability of the stoves and their appropriateness for Haitian cooking. The laboratory results from emissions and efficiency testing and conclusions regarding usability of the stoves are presented in this report.

  6. Magnetic thaw-down and boil-off due to magneto acceptors in 2DEG

    SciTech Connect

    Chaubet, C.; Raymond, A.; Bisotto, I.; Harmand, J. C.; Kubisa, M.; Zawadzki, W.

    2013-12-04

    The Quantum Hall Effect (QHE) and Shubnikov-de Haas effect are investigated experimentally using n type modulation-doped GaAs/GaAlAs quantum wells (QWs) additionally doped in the well with beryllium acceptor atoms. It is presently shown that the localized magneto-acceptor (MA) states which possess discrete energies above the corresponding Landau levels (LLs) lead to two observable effects in magneto-transport: magnetic thaw-down and magnetic boil-off of 2D electrons. Both effects are related to the fact that electrons occupying the localized MA states cannot conduct. Thus in the thaw-down effect the electrons fall down from the MA states to the free Landau states. This leads to a shift of the Hall plateau towards higher magnetic fields as a consequence of an increase of the 2D electron density N{sub S}. In the boil-off effect the electrons are pushed from the free Landau states to the empty MA states under high enough Hall electric field. This process has an avalanche character leading to a dramatic increase of magneto-resistance, consequence of a decrease of N{sub S}.

  7. Waves on the surface of a boiling liquid at various medium stratifications

    SciTech Connect

    Sinkevich, O. A.

    2015-08-15

    The stability of relatively small perturbations of the stationary state consisting of a plane liquid layer and a vapor film is studied when no liquid evaporation or vapor condensation occurs in the stationary state. In this case, heat from a hot to cold wall is removed through a vapor–liquid layer via heat conduction. The boundary conditions that take into account liquid evaporation (appearance of a mass flux) at the vapor–liquid phase surface and the temperature dependence of the saturation pressure are derived. Dispersion equations are obtained. The wave processes for the stable (light vapor under a liquid layer) and unstable stratifications of the phases at rest and during their relative motion are studied. The deformation of the phase boundary results in liquid evaporation, changes in the boiling temperature and the saturation pressure, and generation of weakly damped low-amplitude waves of a new type. These waves ensure the stability of a vapor film under a liquid layer at rest or a liquid layer moving at a constant velocity in the gravity field. The velocities of these waves are much higher than the gravity wave velocities. The critical heat flows and wavelengths at which wave boiling regimes at normal pressure can exist are determined, and the calculated and experimental data are compared.

  8. Modeling the Thermal Mechanical Behavior of a 300 K Vacuum Vesselthat is Cooled by Liquid Hydrogen in Film Boiling

    SciTech Connect

    Yang, S.Q.; Green, M.A.; Lau, W.

    2004-05-07

    This report discusses the results from the rupture of a thin window that is part of a 20-liter liquid hydrogen vessel. This rupture will spill liquid hydrogen onto the walls and bottom of a 300 K cylindrical vacuum vessel. The spilled hydrogen goes into film boiling, which removes the thermal energy from the vacuum vessel wall. This report analyzes the transient heat transfer in the vessel and calculates the thermal deflection and stress that will result from the boiling liquid in contact with the vessel walls. This analysis was applied to aluminum and stainless steel vessels.

  9. A Study of the Role of Adjoint-Equipped CFD in VUQ Analysis of Channel Boiling Simulations -Slides

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Study of the Role of Adjoint- Equipped CFD in VUQ Analysis of Channel Boiling Simulations Krzysztof Fidkowski University of Michigan Milestone L3:THM.CFD.P7.08 November 21, 2013 CASL-U-2013-0192-000-b L3-THM-CFD-P7-08 A Study of the Role of Adjoint-Equipped CFD in VUQ Analysis of Channel Boiling Simulations Milestone owner: Krzysztof Fidkowski, U. Michigan Additional personnel: Isaac Asher, U. Michigan 2 CASL-U-2013-0192-000-b Milestone Execution Responsibility & Personnel * Contact:

  10. Final Report

    SciTech Connect

    Webb, Robert C.; Kamon, Teruki; Toback, David; Safonov, Alexei; Dutta, Bhaskar; Dimitri, Nanopoulos; Pope, Christopher; White, James

    2013-11-18

    Overview The High Energy Physics Group at Texas A&M University is submitting this final report for our grant number DE-FG02-95ER40917. This grant has supported our wide range of research activities for over a decade. The reports contained here summarize the latest work done by our research team. Task A (Collider Physics Program): CMS & CDF Profs. T. Kamon, A. Safonov, and D. Toback co-lead the Texas A&M (TAMU) collider program focusing on CDF and CMS experiments. Task D: Particle Physics Theory Our particle physics theory task is the combined effort of Profs. B. Dutta, D. Nanopoulos, and C. Pope. Task E (Underground Physics): LUX & NEXT Profs. R. Webb and J. White(deceased) lead the Xenon-based underground research program consisting of two main thrusts: the first, participation in the LUX two-phase xenon dark matter search experiment and the second, detector R&D primarily aimed at developing future detectors for underground physics (e.g. NEXT and LZ).

  11. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Policies Plans In Progress Recent Results * QSSI Policies approved by Sponsors * 2016 Strategy finalizing - UES evaluation focus * "Why Evaluation" brownbag * Simple Steps *...

  12. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    optic links will replace many hardwire connections - Remotely programmable set-points and monitoring for each klystron cart - Klystron collector over-temperature protection will...

  13. PowerPoint Presentation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Smart meters and national BMS for 200 most energy intensive facilities Big data: GSA Link logs 15 million data points day Opportunities and Drivers Program ...

  14. Replacement of outboard main steam isolation valves in a boiling water reactor plant

    SciTech Connect

    Schlereth, J.R.; Pennington, D.

    1996-12-01

    Most Boiling Water Reactor plants utilize wye pattern globe valves for main steam isolation valves for both inboard and outboard isolation. These valves have required a high degree of maintenance attention in order to pass the plant local leakage rate testing (LLRT) requirements at each outage. Northern States Power made a decision in 1993 to replace the outboard valves at it`s Monticello plant with double disc gate valves. The replacement of the outboard valves was completed during the fall outage in 1994. During the spring outage in April of 1996 the first LLRT testing was performed with excellent results. This presentation will address the decision process, time requirements and planning necessary to accomplish the task as well as the performance results and cost effectiveness of replacing these components.

  15. Effect of nonuniformity of subcooled boiling flow on the onset of thermoacoustic vibrations

    SciTech Connect

    Gerliga, V.A.; Skalozubov, V.I.; Lesin, V.Y. )

    1991-01-01

    This paper develops the hypothesis that the factor responsible for the onset of thermoacoustic vibrations in two-phase bubble flow is positive work by bubbles condensing in the flow core. It is shown that the predicted threshold of generation of these vibrations depends strongly on the accuracy of description of the steady-state distribution of parameters of bubbles and the liquid. The results predicted on the basis of a two-zone nonequilibrium polydisperse model are compared with those given by the uniform-flow model and an equation representing the condition of applicability of one-dimensional models for predicting the steady-state parameters of nonequilibrium boiling flows is derived.

  16. LIQUID PROPANE GAS (LPG) STORAGE AREA BOILING LIQUID EXPANDING VAPOR EXPLOSION (BLEVE) ANALYSIS

    SciTech Connect

    PACE, M.E.

    2004-01-13

    The PHA and the FHAs for the SWOC MDSA (HNF-14741) identified multiple accident scenarios in which vehicles powered by flammable gases (e.g., propane), or combustible or flammable liquids (e.g., gasoline, LPG) are involved in accidents that result in an unconfined vapor cloud explosion (UVCE) or in a boiling liquid expanding vapor explosion (BLEVE), respectively. These accident scenarios are binned in the Bridge document as FIR-9 scenarios. They are postulated to occur in any of the MDSA facilities. The LPG storage area will be in the southeast corner of CWC that is relatively remote from store distaged MAR. The location is approximately 30 feet south of MO-289 and 250 feet east of 2401-W by CWC Gate 10 in a large staging area for unused pallets and equipment.

  17. Statistical modeling support for calibration of a multiphysics model of subcooled boiling flows

    SciTech Connect

    Bui, A. V.; Dinh, N. T.; Nourgaliev, R. R.; Williams, B. J.

    2013-07-01

    Nuclear reactor system analyses rely on multiple complex models which describe the physics of reactor neutronics, thermal hydraulics, structural mechanics, coolant physico-chemistry, etc. Such coupled multiphysics models require extensive calibration and validation before they can be used in practical system safety study and/or design/technology optimization. This paper presents an application of statistical modeling and Bayesian inference in calibrating an example multiphysics model of subcooled boiling flows which is widely used in reactor thermal hydraulic analysis. The presence of complex coupling of physics in such a model together with the large number of model inputs, parameters and multidimensional outputs poses significant challenge to the model calibration method. However, the method proposed in this work is shown to be able to overcome these difficulties while allowing data (observation) uncertainty and model inadequacy to be taken into consideration. (authors)

  18. Passive containment cooling system with drywell pressure regulation for boiling water reactor

    DOEpatents

    Hill, Paul R.

    1994-01-01

    A boiling water reactor having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit.

  19. Passive containment cooling system with drywell pressure regulation for boiling water reactor

    DOEpatents

    Hill, P.R.

    1994-12-27

    A boiling water reactor is described having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit. 4 figures.

  20. Transient pool boiling heat transfer due to increasing heat inputs in subcooled water at high pressures

    SciTech Connect

    Fukuda, K.; Shiotsu, M.; Sakurai, A.

    1995-09-01

    Understanding of transient boiling phenomenon caused by increasing heat inputs in subcooled water at high pressures is necessary to predict correctly a severe accident due to a power burst in a water-cooled nuclear reactor. Transient maximum heat fluxes, q{sub max}, on a 1.2 mm diameter horizontal cylinder in a pool of saturated and subcooled water for exponential heat inputs, q{sub o}e{sup t/T}, with periods, {tau}, ranging from about 2 ms to 20 s at pressures from atmospheric up to 2063 kPa for water subcoolings from 0 to about 80 K were measured to obtain the extended data base to investigate the effect of high subcoolings on steady-state and transient maximum heat fluxes, q{sub max}. Two main mechanisms of q{sub max} exist depending on the exponential periods at low subcoolings. One is due to the time lag of the hydrodynamic instability which starts at steady-state maximum heat flux on fully developed nucleate boiling (FDNB), and the other is due to the heterogenous spontaneous nucleations (HSN) in flooded cavities which coexist with vapor bubbles growing up from active cavities. The shortest period corresponding to the maximum q{sub max} for long period range belonging to the former mechanism becomes longer and the q{sub max}mechanism for long period range shifts to that due the HSN on FDNB with the increase of subcooling and pressure. The longest period corresponding to the minimum q{sub max} for the short period range belonging to the latter mechanism becomes shorter with the increase in saturated pressure. On the contrary, the longest period becomes longer with the increase in subcooling at high pressures. Correlations for steady-state and transient maximum heat fluxes were presented for a wide range of pressure and subcooling.

  1. Final Surplus Plutonium Disposition Supplemental Environmental...

    Energy Saver

    ... and new information based in part on comments ... and Integrated Extraction System BWR boiling water reactor CAM continuous ... for further examination in an offsite hot cell. ...

  2. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Agency Brand Marketing BPA EISA Messaging Matrix -FINAL 03.15.12 1 Liquid Agency Brand Marketing EISA Messaging and Copy Library Liquid Agency Brand Marketing BPA EISA Messaging...

  3. ARM - Point Reyes News

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    News Campaign Images Point Reyes News From Coastal Clouds to Desert Dust: ARM Mobile Facility Headed to Africa September 30, 2005 New Data Streams Available for ARM Mobile Facility ...

  4. Material Point Methods

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Material Point Methods and Multiphysics for Fracture and Multiphase Problems Joseph Teran, UCLA and Alice Koniges, LBL Contact: jteran@math.ucla.edu Material point methods (MPM) provide an intriguing new path for the design of algorithms that are poised to scale to billions of cores [4]. These methods are particularly important for simulating various phases in the presence of extreme deformation and topological change. This brings about the possibility of new simulations enabled at the exascale

  5. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Microneedles for medical point of care diagnostics and drug delivery Ronen Polsky Department of Biosensors and Nanomaterials February 25, 2015 Sandia MedTech Showcase Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. SAND2015-1388C Brief Technology Overview Wearable Point of

  6. Points of Contact - Hanford Site

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Points of Contact About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Tools Points of Contact Points of Contact Email Email Page...

  7. EIS-0374: Final Environmental Impact Statement | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Impact Statement EIS-0374: Final Environmental Impact Statement Klondike IIIBiglow Canyon Wind Integration Project This summary covers the major points of the draft...

  8. Design of a boiling water reactor equilibrium core using thorium-uranium fuel

    SciTech Connect

    Francois, J-L.; Nunez-Carrera, A.; Espinosa-Paredes, G.; Martin-del-Campo, C.

    2004-10-06

    In this paper the design of a Boiling Water Reactor (BWR) equilibrium core using thorium is presented; a heterogeneous blanket-seed core arrangement concept was adopted. The design was developed in three steps: in the first step two different assemblies were designed based on the integrated blanket-seed concept, they are the blanket-dummy assembly and the blanket-seed assembly. The integrated blanketseed concept comes from the fact that the blanket and the seed rods are located in the same assembly, and are burned-out in a once-through cycle. In the second step, a core design was developed to achieve an equilibrium cycle of 365 effective full power days in a standard BWR with a reload of 104 fuel assemblies designed with an average 235U enrichment of 7.5 w/o in the seed sub-lattice. The main operating parameters, like power, linear heat generation rate and void distributions were obtained as well as the shutdown margin. It was observed that the analyzed parameters behave like those obtained in a standard BWR. The shutdown margin design criterion was fulfilled by addition of a burnable poison region in the assembly. In the third step an in-house code was developed to evaluate the thorium equilibrium core under transient conditions. A stability analysis was also performed. Regarding the stability analysis, five operational states were analyzed; four of them define the traditional instability region corner of the power-flow map and the fifth one is the operational state for the full power condition. The frequency and the boiling length were calculated for each operational state. The frequency of the analyzed operational states was similar to that reported for BWRs; these are close to the unstable region that occurs due to the density wave oscillation phenomena in some nuclear power plants. Four transient analyses were also performed: manual SCRAM, recirculation pumps trip, main steam isolation valves closure and loss of feed water. The results of these transients are

  9. Precision Pointing System Development

    SciTech Connect

    BUGOS, ROBERT M.

    2003-03-01

    The development of precision pointing systems has been underway in Sandia's Electronic Systems Center for over thirty years. Important areas of emphasis are synthetic aperture radars and optical reconnaissance systems. Most applications are in the aerospace arena, with host vehicles including rockets, satellites, and manned and unmanned aircraft. Systems have been used on defense-related missions throughout the world. Presently in development are pointing systems with accuracy goals in the nanoradian regime. Future activity will include efforts to dramatically reduce system size and weight through measures such as the incorporation of advanced materials and MEMS inertial sensors.

  10. Appendix B - Control Points

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    B Control Points B.1 Injector Control Points Qty Type Device 2 Magnet Bend magnet - DL1 bend 9 Magnet Quad magnet 10 Magnet X-Y Corrector Pair 2 Magnet Solenoid 2 Magnet Spectrometer 1 RF Gun 2 RF Accelerating Structure 1 RF Transverse RF Structure 1 TIMING Timing/Trigger System 1 Laser Gun Laser 1 Laser Alignment Laser 13 DIAG BPM 4 DIAG Wire Scanner 11 DIAG Profile Monitor 3 DIAG Toroid 1 DIAG Transverse RF BL Monitor 3 DIAG Faraday Cup 1 DIAG Energy Collimator 1 DIAG Tune-up Dump 1 VAC Vacuum

  11. Thermal-hydraulic instabilities in pressure tube graphite - moderated boiling water reactors

    SciTech Connect

    Tsiklauri, G.; Schmitt, B.

    1995-09-01

    Thermally induced two-phase instabilities in non-uniformly heated boiling channels in RBMK-1000 reactor have been analyzed using RELAP5/MOD3 code. The RELAP5 model of a RBMK-1000 reactor was developed to investigate low flow in a distribution group header (DGH) supplying 44 fuel pressure tubes. The model was evaluated against experimental data. The results of the calculations indicate that the period of oscillation for the high power tube varied from 3.1s to 2.6s, over the power range of 2.0 MW to 3.0 MW, respectively. The amplitude of the flow oscillation for the high powered tube varied from +100% to -150% of the tube average flow. Reverse flow did not occur in the lower power tubes. The amplitude of oscillation in the subcooled region at the inlet to the fuel region is higher than in the saturated region at the outlet. In the upper fuel region and outlet connectors the flow oscillations are dissipated. The threshold of flow instability for the high powered tubes of a RBMK reactor is compared to Japanese data and appears to be in good agreement.

  12. Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation

    SciTech Connect

    Jessee, Matthew Anderson

    2011-01-01

    Computational capability has been developed to adjust multigroup neutron cross sections, including self-shielding correction factors, to improve the fidelity of boiling water reactor (BWR) core modeling and simulation. The method involves propagating multigroup neutron cross-section uncertainties through various BWR computational models to evaluate uncertainties in key core attributes such as core k{sub eff}, nodal power distributions, thermal margins, and in-core detector readings. Uncertainty-based inverse theory methods are then employed to adjust multigroup cross sections to minimize the disagreement between BWR core modeling predictions and observed (i.e., measured) plant data. For this paper, observed plant data are virtually simulated in the form of perturbed three-dimensional nodal power distributions with the perturbations sized to represent actual discrepancies between predictions and real plant data. The major focus of this work is to efficiently propagate multigroup neutron cross-section uncertainty through BWR lattice physics and core simulator calculations. The data adjustment equations are developed using a subspace approach that exploits the ill-conditioning of the multigroup cross-section covariance matrix to minimize computation and storage burden. Tikhonov regularization is also employed to improve the conditioning of the data adjustment equations. Expressions are also provided for posterior covariance matrices of both the multigroup cross-section and core attributes uncertainties.

  13. Advanced fuel assembly characterization capabilities based on gamma tomography at the Halden boiling water reactor

    SciTech Connect

    Holcombe, S.; Eitrheim, K.; Svaerd, S. J.; Hallstadius, L.; Willman, C.

    2012-07-01

    Characterization of individual fuel rods using gamma spectroscopy is a standard part of the Post Irradiation Examinations performed on experimental fuel at the Halden Boiling Water Reactor. However, due to handling and radiological safety concerns, these measurements are presently carried out only at the end of life of the fuel, and not earlier than several days or weeks after its removal from the reactor core. In order to enhance the fuel characterization capabilities at the Halden facilities, a gamma tomography measurement system is now being constructed, capable of characterizing fuel assemblies on a rod-by-rod basis in a more timely and efficient manner. Gamma tomography for measuring nuclear fuel is based on gamma spectroscopy measurements and tomographic reconstruction techniques. The technique, previously demonstrated on irradiated commercial fuel assemblies, is capable of determining rod-by-rod information without the need to dismantle the fuel. The new gamma tomography system will be stationed close to the Halden reactor in order to limit the need for fuel transport, and it will significantly reduce the time required to perform fuel characterization measurements. Furthermore, it will allow rod-by-rod fuel characterization to occur between irradiation cycles, thus allowing for measurement of experimental fuel repeatedly during its irradiation lifetime. The development of the gamma tomography measurement system is a joint project between the Inst. for Energy Technology - OECD Halden Reactor Project, Westinghouse (Sweden), and Uppsala Univ.. (authors)

  14. Thermalhydraulic calculation for boiling water reactor and its natural circulation component

    SciTech Connect

    Trianti, Nuri Nurjanah,; Su’ud, Zaki; Arif, Idam; Permana, Sidik

    2015-09-30

    Thermalhydraulic of reactor core is the thermal study on fluids within the core reactor, i.e. analysis of the thermal energy transfer process produced by fission reaction from fuel to the reactor coolant. This study include of coolant temperature and reactor power density distribution. The purposes of this analysis in the design of nuclear power plant are to calculate the coolant temperature distribution and the chimney height so natural circulation could be occurred. This study was used boiling water reactor (BWR) with cylinder type reactor core. Several reactor core properties such as linear power density, mass flow rate, coolant density and inlet temperature has been took into account to obtain distribution of coolant density, flow rate and pressure drop. The results of calculation are as follows. Thermal hydraulic calculations provide the uniform pressure drop of 1.1 bar for each channels. The optimum mass flow rate to obtain the uniform pressure drop is 217g/s. Furthermore, from the calculation it could be known that outlet temperature is 288°C which is the saturated fluid’s temperature within the system. The optimum chimney height for natural circulation within the system is 14.88 m.

  15. Enhancement of Heat Transfer with Pool and Spray Impingement Boiling on Microporous and Nanowire Surface Coatings

    SciTech Connect

    Thiagarajan, S. J.; Wang, W.; Yang, R.; Narumanchi, S.; King, C.

    2010-09-01

    The DOE National Renewable Energy Laboratory (NREL) is leading a national effort to develop next-generation cooling technologies for hybrid vehicle electronics. The goal is to reduce the size, weight, and cost of power electronic modules that convert direct current from batteries to alternating current for the motor, and vice versa. Aggressive thermal management techniques help to increase power density and reduce weight and volume, while keeping chip temperatures within acceptable limits. The viability of aggressive cooling schemes such as spray and jet impingement in conjunction with enhanced surfaces is being explored. Here, we present results from a series of experiments with pool and spray boiling on enhanced surfaces, such as a microporous layer of copper and copper nanowires, using HFE-7100 as the working fluid. Spray impingement on the microporous coated surface showed an enhancement of 100%-300% in the heat transfer coefficient at a given wall superheat with respect to spray impingement on a plain surface under similar operating conditions. Critical heat flux also increased by 7%-20%, depending on flow rates.

  16. Study of plutonium disposition using existing GE advanced Boiling Water Reactors

    SciTech Connect

    Not Available

    1994-06-01

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

  17. Metallurgical failure analysis of a propane tank boiling liquid expanding vapor explosion (BLEVE).

    SciTech Connect

    Kilgo, Alice C.; Eckelmeyer, Kenneth Hall; Susan, Donald Francis

    2005-01-01

    A severe fire and explosion occurred at a propane storage yard in Truth or Consequences, N.M., when a truck ran into the pumping and plumbing system beneath a large propane tank. The storage tank emptied when the liquid-phase excess flow valve tore out of the tank. The ensuing fire engulfed several propane delivery trucks, causing one of them to explode. A series of elevated-temperature stress-rupture tears developed along the top of a 9800 L (2600 gal) truck-mounted tank as it was heated by the fire. Unstable fracture then occurred suddenly along the length of the tank and around both end caps, along the girth welds connecting the end caps to the center portion of the tank. The remaining contents of the tank were suddenly released, aerosolized, and combusted, creating a powerful boiling liquid expanding vapor explosion (BLEVE). Based on metallography of the tank pieces, the approximate tank temperature at the onset of the BLEVE was determined. Metallurgical analysis of the ruptured tank also permitted several hypotheses regarding BLEVE mechanisms to be evaluated. Suggestions are made for additional work that could provide improved predictive capabilities regarding BLEVEs and for methods to decrease the susceptibility of propane tanks to BLEVEs.

  18. Hydrogen water chemistry for BWRs (boiling water reactors): Materials behavior: Interim report

    SciTech Connect

    Gordon, B.M.; Jewett, C.W.; Pickett, A.E.; Walker, W.L.; Indig, M.E.; Andresen, P.L.; Niedrach, L.W.; Davis, R.B.

    1987-03-01

    The objective of this research program is to provide test data to guide future actions by boiling water reactor (BWR) owners regarding the use of hydrogen additions to the feedwater to mitigate pipe cracking during power operation. Numerous laboratory testing methods and approaches are being utilized in this program to evaluate and quantify the effects of this hydrogen water chemistry (HWC) on the corrosion performance of reactor materials, including full-scale pipe testing, fatigue crack initiation and growth studies, constant load tests, electrochemical potential (ECP) measurements, constant extension rate technique (CERT) testing, straining electrode tests (SET), oxide film analysis, fracture mechanics studies, general corrosion investigations and bent beam tests. The results to date are summarized in this report and indicate that HWC (which implies an ECP of Type-304 stainless steel below -230 mV/sub SHE/ coupled with a low water conductivity) generally has a beneficial effect on the corrosion performance of BWR structural materials. Specifically, HWC mitigates intergranular stress corrosion cracking (IGSCC) initiation and propagation in piping, provides an improved margin against environmental cracking in carbon steel and low alloy steel, and does not promote environmental cracking in other materials. A measurable, but acceptable, increase in the initial general corrosion kinetics of carbon and low alloy steel also accompanies the use of HWC. The laboratory data, together with the in-reactor test results, clearly indicate that HWC is an effective method of reducing the likelihood and rate of BWR pipe cracking.

  19. Experimental investigation on the flow instability behavior of a multi-channel boiling natural circulation loop at low-pressures

    SciTech Connect

    Jain, Vikas; Nayak, A.K.; Vijayan, P.K.; Saha, D.; Sinha, R.K.

    2010-09-15

    Natural circulation as a mode of heat removal is being considered as a prominent passive feature in the innovative nuclear reactor designs, particularly in boiling-water-reactors, due to its simplicity and economy. However, boiling natural circulation system poses many challenges to designer due to occurrence of various kinds of instabilities such as excursive instability, density wave oscillations, flow pattern transition instability, geysering and metastable states in parallel channels. This problem assumes greater significance particularly at low-pressures i.e. during startup, where there is great difference in the properties of two phases. In light of this, a parallel channel loop has been designed and installed that has a geometrical resemblance to the pressure-tube-type boiling-water-reactor, to investigate into the behavior of boiling natural circulation. The loop comprises of four identical parallel channels connected between two common plenums i.e. steam drum and header. The recirculation path is provided by a single downcomer connected between steam drum and header. Experiments have been conducted over a wide range of power and pressures (1-10 bar). Two distinct unstable zones are observed with respect to power i.e. corresponding to low power (Type-I) and high power (Type-II) with a stable zone at intermediate powers. The nature of oscillations in terms of their amplitude and frequency and their evolution for Type-I and Type-II instabilities are studied with respect to the effect of heater power and pressure. This paper discusses the evolution of unstable and stable behavior along with the nature of flow oscillation in the channels and the effect of pressure on it. (author)

  20. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    SciTech Connect

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  1. EndPoints 2000

    Energy Science and Technology Software Center

    2009-08-13

    The application leads the user through a logical framework to determine the minimum effort and cost necessary to reach the desired end state for each space, system, and facility. Endpoints are used to plan the project work, track and manage the determination, management, verification, and closure of D&D endpoints, consistent with DOE End Point guidance documents.

  2. MountPointAttributes

    Energy Science and Technology Software Center

    2001-06-16

    MountPointAttributes is a software component that provides client code with a technique to raise the local namespace of a file to a global namespace. Its abstractions and mechanisms allow the client code to gather global properties of a file and to use them in devising an effective storage access strategy on this file.

  3. Effect of surface oxidation on the onset of nucleate boiling in a materials test reactor coolant channel

    DOE PAGES [OSTI]

    Forrest, Eric C.; Don, Sarah M.; Hu, Lin -Wen; Buongiorno, Jacopo; McKrell, Thomas J.

    2016-02-29

    The onset of nucleate boiling (ONB) serves as the thermal-hydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been well-characterized in narrow channel geometries or for oxidized surface conditions. This study presents experimental data for the ONB in vertical upflow of deionized (DI) water in a simulated materials test reactor (MTR) coolant channel. The channel gap thickness and aspect ratio were 1.96 mm and 29:1, respectively. Boiling surface conditions were carefully controlled and characterized, with both heavily oxidized and native oxide surfaces tested. Measurements were performed for mass fluxes ranging from 750more » to 3000 kg/m2s and for subcoolings ranging from 10 to 45°C. ONB was identified using a combination of high-speed visual observation, surface temperature measurements, and channel pressure drop measurements. Surface temperature measurements were found to be most reliable in identifying the ONB. For the nominal (native oxide) surface, results indicate that the correlation of Bergles and Rohsenow, when paired with the appropriate single-phase heat transfer correlation, adequately predicts the ONB heat flux. Furthermore, incipience on the oxidized surface occurred at a higher heat flux and superheat than on the plain surface.« less

  4. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Simulations of Clouds and Boundary Layer Processes Image courtesy of Bjorn Stevens Yaosheng Chen, Pennsylvania State University Tobias Marke, University of Cologne Robert Schrom, Pennsylvania State University Hee-Jung Yang, University of Illinois Jianhao Zhang, University of Miami ARM Summer Training Final Presentation 24 July 2015 Motivation and Outline * What domains are needed to realistically simulate shallow cumulus? * What are the properties of the simulated cloud field? * What is the

  5. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    June 8, 2016 Bill Hamel, Assistant Manager, WTP Project U.S. Department of Energy, Office of River Protection Hanford Advisory Board Agency Update for the Office of River Protection 2 Our Mission and Vision Our Mission To safeguard the nuclear waste stored in Hanford's 177 underground tanks, and to manage the waste safely and responsibly until it can be treated in the Waste Treatment and Immobilization Plant for final disposition. Vision To be a high-performing, innovative organization that is

  6. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    April 13, 2016 Jonathan "JD" Dowell, Deputy Manager U.S. Department of Energy, Office of River Protection Hanford Advisory Board Agency Update for the Office of River Protection 2 Our Mission and Vision Our Mission To safeguard the nuclear waste stored in Hanford's 177 underground tanks, and to manage the waste safely and responsibly until it can be treated in the Waste Treatment and Immobilization Plant for final disposition. Vision To be a high-performing, innovative organization

  7. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Closure Project Overview and Project Status October 2016 2 3 * Final internal hazard reduction * Demolition zone preparations * Employee transition planning * Employee training * Employee communication effort * Demolition preparations Plutonium Finishing Plant (PFP) Current Status We don't proceed until we are certain we can do it safely 4 PFP DOE-RL Project Key Risks RL-EMP-001.01 Bump and Roll of Bargaining Unit Employees * If a significant number of bargaining unit employees at PFP are

  8. PowerPoint Presentation

    Energy Information Administration (EIA) (indexed site)

    Notes: For 2016, natural gas production represents monthly natural gas gross withdrawals estimated from data collected on the EIA-914 survey. Volumes through 2015 reflect EIA's final reported state data. Data for Arkansas, California, Colorado, Kansas, Louisiana, Montana, New Mexico, North Dakota, Ohio, Oklahoma, Pennsylvania, Texas, Utah, West Virginia, Wyoming, and Federal Offshore Gulf of Mexico are individually collected on the EIA-914 survey. The "other states" category comprises

  9. PowerPoint Presentation

    Energy Information Administration (EIA) (indexed site)

    Utica Shale Update Scott Kell Assistant Chief, Division of Oil & Gas Resources Management Ohio Department of Natural Resources Horizontal Well Activity Activity Trends Agency Progress Emerging Issues Horizontal Well Permitting 0 200 400 600 800 1000 1200 1400 1600 '06 '07 '08 '09 '10 '11 '12 '13 '14 '15 Year Utica Permits Permits Issued Well Drilling Horizontal Well Drilling by Year: 2011 - 64 2012 - 135 2013 - 526 2014 - 764 Horizontal Rig Count Horizontal Utica - Point Pleasant Well

  10. PowerPoint Presentation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    John Nangle, National Renewable Energy Laboratory (NREL) Tribal Leader Forum, Phoenix, AZ - May 30 - 31, 2013 State Incentives and Project Impacts Main Points - Market Context * State Renewable Portfolio Standards (RPS) - What are they? - How can they help your project? - Potential gap means more market demand for RE projects Starting a Renewable Energy Project * What renewable resources exist? * What sites with resources do you own? * To whom will you sell the electricity? * How will federal

  11. PowerPoint Presentation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    as needed to clarify and/or address request DOE receives Japanese Request for Information or Technical Collaboration Regarding EM/NE Topics Forward to National Laboratory Coordinators (LCs) LCs share request with National Laboratory Points of Contact (POCs) for consideration Japanese organization follows up with Laboratory(s) POC(s) via mutually agreed mechanism for support LCs coordinate follow- up telecon/ VTC with relevant parties DOE/LCs Share National Laboratory Input with Japanese

  12. PowerPoint Presentation

    Office of Environmental Management (EM)

    John Nangle, National Renewable Energy Laboratory (NREL) Tribal Leader Forum, Phoenix, AZ - May 30 - 31, 2013 State Incentives and Project Impacts Main Points - Market Context * State Renewable Portfolio Standards (RPS) - What are they? - How can they help your project? - Potential gap means more market demand for RE projects Starting a Renewable Energy Project * What renewable resources exist? * What sites with resources do you own? * To whom will you sell the electricity? * How will federal

  13. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    CLOUD RADARS A Year in Review and a Look to the Future Kevin Widener (a), Karen Johnson (b) Pacific Northwest National Laboratory (a), Brookhaven National Laboratory (b) Summary A total of 7 zenith pointing Doppler cloud radars are in operation 24/7 at the ARM sites. We successfully addressed many hardware problems on all of the radars. Antenna refurbishment and procurement of a new digital transceiver are currently underway. We are also working on the next version of the signal processor to

  14. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Balance of Facilities Federal Project Director August 10, 2016 Effluent Management Facility Permitting Update Hanford Advisory Board Tank Waste Committee 2 Effluent Management Facility Overview Initial excavation and preparation activities for the Effluent Management Facility mudmat. EMF provides 4 key services to support DFLAW * Provides a low point drain for waste transfer line flushing * Concentrates fluids containing low levels of radioactive material from the LAW off-gas treatment system

  15. PowerPoint Presentation

    Energy Saver

    as needed to clarify and/or address request DOE receives Japanese Request for Information or Technical Collaboration Regarding EM/NE Topics Forward to National Laboratory Coordinators (LCs) LCs share request with National Laboratory Points of Contact (POCs) for consideration Japanese organization follows up with Laboratory(s) POC(s) via mutually agreed mechanism for support LCs coordinate follow- up telecon/ VTC with relevant parties DOE/LCs Share National Laboratory Input with Japanese

  16. Strategic Focus Points

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Focus Points June 2011 1. Establish the human capital and organizational foundation to create a high-performing organization. 2. Implement a cyber risk-management and incident response program that ensures effective security of Federal and M&O networks, provides appropriate flexibility, and meets legal requirements and OMB expectations. 3. Improve IT Services (EITS) into a best-in-class provider from both a technical and business perspective. 4. Implement and institutionalize a reformed,

  17. END POINTS MANAGEMENT End Points Management The Need for End Point Specifications

    Office of Environmental Management (EM)

    MANAGEMENT End Points Management The Need for End Point Specifications The Need for a Method to Derive End Points Guiding Principles for Specifying End Points Tailored Approach Headquarters, Field Office, and Contractor Roles End Points Approvals Contractor Organization Functions for End Points Implementation Training and Walkdown Guidance for the Facility Engineers The Need for End Point Specifications The policy of the EM is that a formal project management approach be used for the planning,

  18. Stress and Fracture Mechanics Analyses of Boiling Water Reactor and Pressurized Water Reactor Pressure Vessel Nozzles

    SciTech Connect

    Yin, Shengjun; Bass, Bennett Richard; Stevens, Gary; Kirk, Mark

    2011-01-01

    This paper describes stress analysis and fracture mechanics work performed to assess boiling water reactor (BWR) and pressurized water reactor (PWR) nozzles located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Various RPV nozzle geometries were investigated: 1. BWR recirculation outlet nozzle; 2. BWR core spray nozzle3 3. PWR inlet nozzle; ; 4. PWR outlet nozzle; and 5. BWR partial penetration instrument nozzle. The above nozzle designs were selected based on their proximity to the core beltline region, i.e., those nozzle configurations that are located close enough to the core region such that they may receive sufficient fluence prior to end-of-license (EOL) to require evaluation as part of establishing the allowed limits on heatup, cooldown, and hydrotest (leak test) conditions. These nozzles analyzed represent one each of the nozzle types potentially requiring evaluation. The purpose of the analyses performed on these nozzle designs was as follows: To model and understand differences in pressure and thermal stress results using a two-dimensional (2-D) axi-symmetric finite element model (FEM) versus a three-dimensional (3-D) FEM for all nozzle types. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated; To verify the accuracy of a selected linear elastic fracture mechanics (LEFM) hand solution for stress intensity factor for a postulated nozzle corner crack for both thermal and pressure loading for all nozzle types; To assess the significance of attached piping loads on the stresses in the nozzle corner region; and To assess the significance of applying pressure on the crack face with respect to the stress intensity factor for a postulated nozzle corner crack.

  19. Effect of rolling motion on critical heat flux for subcooled flow boiling in vertical tube

    SciTech Connect

    Hwang, J. S.; Park, I. U.; Park, M. Y.; Park, G. C.

    2012-07-01

    This paper presents defining characteristics of the critical heat flux (CHF) for the boiling of R-134a in vertical tube operation under rolling motion in marine reactor. It is important to predict CHF of marine reactor having the rolling motion in order to increase the safety of the reactor. Marine Reactor Moving Simulator (MARMS) tests are conducted to measure the critical heat flux using R-134a flowing upward in a uniformly heated vertical tube under rolling motion. MARMS was rotated by motor and mechanical power transmission gear. The CHF tests were performed in a 9.5 mm I.D. test section with heated length of 1 m. Mass fluxes range from 285 to 1300 kg m{sup -2}s{sup -1}, inlet subcooling from 3 to 38 deg. C and outlet pressures from 13 to 24 bar. Amplitudes of rolling range from 15 to 40 degrees and periods from 6 to 12 sec. To convert the test conditions of CHF test using R-134a in water, Katto's fluid-to-fluid modeling was used in present investigation. A CHF correlation is presented which accounts for the effects of pressure, mass flux, inlet subcooling and rolling angle over all conditions tested. Unlike existing transient CHF experiments, CHF ratio of certain mass flux and pressure are different in rolling motion. For the mass fluxes below 500 kg m{sup -2}s{sup -1} at 13, 16 (region of relative low mass flux), CHF ratio was decreased but was increased above that mass flux (region of relative high mass flux). Moreover, CHF tend to enhance in entire mass flux at 24 bar. (authors)

  20. Nondestructive assay of spent boiling water reactor fuel by active neutron interrogation

    SciTech Connect

    Blakeman, E.D.; Ricker, C.W.; Ragan, G.L.; Difilippo, F.C.; Slaughter, G.G.

    1981-01-01

    Spent boiling water reactor (BWR) fuel from Dresden I was assayed for total fissile mass, using the active neutron interrogation method. The nondestructive assay (NDA) system used has four Sb-Be sources for interrogation of the fuels; the induced fission neutrons from the fuel are counted by four lead-shielded methane-filled proportional counters biased above the energy of the source neutrons. Spent fuel rods containing 9 kg of heavy metal were chopped into 5-cm segments and loaded into three 1-liter cans. The three cans were assayed in seven combinations of one, two, or three cans, enabling an evaluation of the precision and accuracy of the NDA system for different amounts of fissile material. The fissile mass in each combination was determined by comparing the induced-fission-neutron counts with the counts obtained from a known standard comprising chopped segments of unirradiated Dresden fuel. These masses were compared to the masses determined by chemical analyses of the spent fuel. The results from the nondestructive assays agreed with results from the chemical analyses to within 2 to 3%. Similar agreement was obtained when two combinations of canned spent fuel were used as standards for the nondesctuctive assays. The assay of BWR spent fuel served as a test of the NDA system which was developed at the Oak Ridge National Laboratory for the assay of spent liquid metal fast breeder reactor (LMFBR) fuel subassemblies at the heat-end of a reprocessing plant. Results of previous experiments and calculations reported earlier using simulated LMFBR fuel subassemblies indicated that the NDA system can measure the fissile masses of spent fuel subassemblies to within an accuracy of 3%. Results of the assays of spent BWR fuel reported herein support this conclusion.

  1. Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)

    SciTech Connect

    1994-04-30

    The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

  2. PowerPoint Presentation

    Energy Information Administration (EIA) (indexed site)

    OIL SUPPLY AND TECHNOLOGY 2016 EIA/DOE ENERGY CONFERENCE Michael C. Lynch lynch@energyseer.com THE BOOK IS FINALLY HERE! (WELL, END JULY) 2014 DOE PRICE FORECAST SURVEY 0 20 40 60 80 100 120 140 160 180 2010 2015 2020 2025 2030 2035 2040 ACTUAL DOE Series3 Series4 Series5 Series6 IEA SEER ...IN HISTORICAL CONTEXT $0 $20 $40 $60 $80 $100 $120 $140 $160 $180 1900 1910 1920 1930 1940 1950 1960 1970 1980 1990 2000 2010 2020 2030 2040 PRICE FORECASTING  SHORT-TERM ALL BUT IMPOSSIBLE  WEATHER,

  3. PowerPoint Presentation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    True-up Projections Current Rate Schedules  New Rate Schedules were effective October 1, 2015.  The Rate Schedules have been approved on an interim basis through September 30, 2020.  Final action by FERC is pending. 2 Current Rate Schedules  Rate schedules include an automatic adjustment, or "true-up", for transfers to plant-in-service.  Under the RIOP, the adjustment per $1 million investment is:  $0.001 /kW/Month to Capacity  0.02 mills per kWh to Energy 

  4. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RapiDx Victoria VanderNoot, Ph.D. February 25, 2015 Sandia MedTech Showcase Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. SAND2015-1392C Brief Technology Overview - RapiDx Rapid, Automated Point-of-Care System (RapiDx) * Portable microfluidic in vitro diagnostic instrument

  5. PowerPoint Presentation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Automated Prep of Nucleic Acids from Blood for Point-of-Care Applications Steven S. Branda Principal Member of Technical Staff February 25, 2015 Sandia MedTech Showcase Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. SAND2015-1389C Technology Overview * Platform for automated

  6. Capital Point | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Point Jump to: navigation, search Name: Capital Point Place: Israel Sector: Services Product: General Financial & Legal Services ( Joint Venture Consortium ) References: Capital...

  7. Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb22_2010PB...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    BOSCO Feb222010PB final rcvd 5 Mar Compatibility Mode Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb222010PB final rcvd 5 Mar Compatibility Mode PDF icon ...

  8. SEMI-ANNUAL REPORTS FOR DOMINION COVE POINT, LP - DK. NO. 11...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOMINION COVE POINT, LP - DK. NO. 11-128-LNG - ORDER 3331 (Conditional Order) and Order 3331-A Final Order SEMI-ANNUAL REPORTS FOR DOMINION COVE POINT, LP - DK. NO. 11-128-LNG - ...

  9. Microsoft PowerPoint -Risk_Portfolio_Manager(RPM)_overview_Under...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    PowerPoint - RiskPortfolioManager(RPM)overviewUnderSecDOE2011V4 Final 3-22-2011.ppt Read-Only Compatibili Microsoft PowerPoint - RiskPortfolioManager(RPM)overviewUn...

  10. Application of the Isotope Ratio Method to a Boiling Water Reactor

    SciTech Connect

    Frank, Douglas P.; Gerlach, David C.; Gesh, Christopher J.; Hurley, David E.; Meriwether, George H.; Mitchell, Mark R.; Reid, Bruce D.

    2010-08-11

    production in a boiling water reactor fuel bundle based on measurements taken from the corresponding fuel assembly channel. Our preliminary results are in good agreement with the actual operating history of the reactor during the cycle that the fuel bundle was resident in the core.

  11. Comparing Simulation Results with Traditional PRA Model on a Boiling Water Reactor Station Blackout Case Study

    SciTech Connect

    Zhegang Ma; Diego Mandelli; Curtis Smith

    2011-07-01

    A previous study used RELAP and RAVEN to conduct a boiling water reactor station black-out (SBO) case study in a simulation based environment to show the capabilities of the risk-informed safety margin characterization methodology. This report compares the RELAP/RAVEN simulation results with traditional PRA model results. The RELAP/RAVEN simulation run results were reviewed for their input parameters and output results. The input parameters for each simulation run include various timing information such as diesel generator or offsite power recovery time, Safety Relief Valve stuck open time, High Pressure Core Injection or Reactor Core Isolation Cooling fail to run time, extended core cooling operation time, depressurization delay time, and firewater injection time. The output results include the maximum fuel clad temperature, the outcome, and the simulation end time. A traditional SBO PRA model in this report contains four event trees that are linked together with the transferring feature in SAPHIRE software. Unlike the usual Level 1 PRA quantification process in which only core damage sequences are quantified, this report quantifies all SBO sequences, whether they are core damage sequences or success (i.e., non core damage) sequences, in order to provide a full comparison with the simulation results. Three different approaches were used to solve event tree top events and quantify the SBO sequences: W process flag, default process flag without proper adjustment, and default process flag with adjustment to account for the success branch probabilities. Without post-processing, the first two approaches yield incorrect results with a total conditional probability greater than 1.0. The last approach accounts for the success branch probabilities and provides correct conditional sequence probabilities that are to be used for comparison. To better compare the results from the PRA model and the simulation runs, a simplified SBO event tree was developed with only four top

  12. Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study

    SciTech Connect

    Anh Bui; Nam Dinh; Brian Williams

    2013-09-01

    In addition to validation data plan, development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a main objective of the CASL VUQ plan. Advanced modeling of LWR systems normally involves a range of physico-chemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions is determined by the correctness of various sub-models, which are not conservation-laws based, but empirically derived from measurement data. Such sub-models normally require extensive calibration before the models can be applied to analysis of real reactor problems. This work demonstrates a case study of calibration of a common model of subcooled flow boiling, which is an important multiscale, multiphysics phenomenon in LWR thermal hydraulics. The calibration process is based on a new strategy of model-data integration, in which, all sub-models are simultaneously analyzed and calibrated using multiple sets of data of different types. Specifically, both data on large-scale distributions of void fraction and fluid temperature and data on small-scale physics of wall evaporation were simultaneously used in this works calibration. In a departure from traditional (or common-sense) practice of tuning/calibrating complex models, a modern calibration technique based on statistical modeling and Bayesian inference was employed, which allowed simultaneous calibration of multiple sub-models (and related parameters) using different datasets. Quality of data (relevancy, scalability, and uncertainty) could be taken into consideration in the calibration process. This work presents a step forward in the development and realization of the CIPS Validation Data Plan at the Consortium for Advanced Simulation of LWRs to enable

  13. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    SciTech Connect

    Boing, L.E.; Henley, D.R. ); Manion, W.J.; Gordon, J.W. )

    1989-12-01

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

  14. Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions

    SciTech Connect

    Schultis, J., Kenneth; Fenton, Donald, L.

    2006-10-20

    Increasing demand for energy necessitates nuclear power units to increase power limits. This implies significant changes in the design of the core of the nuclear power units, therefore providing better performance and safety in operations. A major hindrance to the increase of nuclear reactor performance especially in Pressurized Deionized water Reactors (PWR) is Axial Offset Anomaly (AOA)--the unexpected change in the core axial power distribution during operation from the predicted distribution. This problem is thought to be occur because of precipitation and deposition of lithiated compounds like boric acid (H{sub 2}BO{sub 3}) and lithium metaborate (LiBO{sub 2}) on the fuel rod cladding. Deposited boron absorbs neutrons thereby affecting the total power distribution inside the reactor. AOA is thought to occur when there is sufficient build-up of crud deposits on the cladding during subcooled nucleate boiling. Predicting AOA is difficult as there is very little information regarding the heat and mass transfer during subcooled nucleate boiling. An experimental investigation was conducted to study the heat transfer characteristics during subcooled nucleate boiling at prototypical PWR conditions. Pool boiling tests were conducted with varying concentrations of lithium metaborate (LiBO{sub 2}) and boric acid (H{sub 2}BO{sub 3}) solutions in deionized water. The experimental data collected includes the effect of coolant concentration, subcooling, system pressure and heat flux on pool the boiling heat transfer coefficient. The analysis of particulate deposits formed on the fuel cladding surface during subcooled nucleate boiling was also performed. The results indicate that the pool boiling heat transfer coefficient degrades in the presence of boric acid and lithium metaborate compared to pure deionized water due to lesser nucleation. The pool boiling heat transfer coefficients decreased by about 24% for 5000 ppm concentrated boric acid solution and by 27% for 5000 ppm

  15. Microsoft Word - 504_FinalPaper.doc

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... boiling and two-phase flow models in the Eulerian Multiphase CFD code STAR-CD 7. ... a sequence of three mesh resolutions. 2. CFD Two Phase Models and Constitutive Relations ...

  16. Full Final Report

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    REPOR FULL FINAL REPOR T T SECTION III SECTION III FULL FINAL REPORT SECTION III Individual Project Summaries Table of Contents Algal Biology ..................................................................................................3 Cultivation ...................................................................................................41 Harvesting and Extraction .............................................................................65 Fuel Conversion

  17. Final EIS Volume 3

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Volume 3 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site Comment Response Document Final Environmental Impact Statement for AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final

  18. END POINTS SPECIFICATION METHODS End Points Specification Methods

    Office of Environmental Management (EM)

    SPECIFICATION METHODS End Points Specification Methods Hierarchical End-Points Method Checklist End-Points Method Two methods to develop end point specifications are presented. These have evolved from use in the field for deactivation projects.  The hierarchical method is systematic, comprehensive, and completely defensible as to the basis for each specification. This method may appear complex to the uninitiated, but it is a straightforward application of a systematic engineering approach. It

  19. Reflooding and boil-off experiments in a VVER-440 like rod bundle and analyses with the CATHARE code

    SciTech Connect

    Korteniemi, V.; Haapalehto, T.; Puustinen, M.

    1995-09-01

    Several experiments were performed with the VEERA facility to simulate reflooding and boil-off phenomena in a VVER-440 like rod bundle. The objective of these experiments was to get experience of a full-scale bundle behavior and to create a database for verification of VVER type core models used with modern thermal-hydraulic codes. The VEERA facility used in the experiments is a scaled-down model of the Russian VVER-440 type pressurized water reactors used in Loviisa, Finland. The test section of the facility consists of one full-scale copy of a VVER-440 reactor rod bundle with 126 full-length electrically heated rod simulators. Bottom and top-down reflooding, different modes of emergency core cooling (ECC) injection and the effect of heating power on the heat-up of the rods was studied. In this paper the results of calculations simulating two reflood and one boil-off experiment with the French CATHARE2 thermal-hydraulic code are also presented. Especially the performance of the recently implemented top-down reflood model of the code was studied.

  20. Final Technical Report

    SciTech Connect

    Aristos Aristidou Natureworks); Robert Kean; Tom Schechinger; Stuart Birrell; Jill Euken

    2007-10-01

    /storage/transportation equipment and the processor would build and operate the plant. Pilot fermentation studies demonstrated dramatic improvements in yields and rates with optimization of batch fermentor parameters. Demonstrated yields and rates are approaching those necessary for profitable commercial operation for production of ethanol or lactic acid. The ability of the biocatalyst to adapt to biomass hydrolysate (both biomass sugars and toxins in the hydrolysate) was demonstrated and points towards ultimate successful commercialization of the technology. However, some of this work will need to be repeated and possibly extended to adapt the final selected biocatalyst for the specific commercial hydrolysate composition. The path from corn stover in the farm field to final products, involves a number of steps. Each of these steps has options, problems, and uncertainties; thus creating a very complex multidimensional obstacle to successful commercial development. Through the tasks of this project, the technical and commercial uncertainties of many of these steps have been addressed; thus providing for a clearer understanding of paths forward and commercial viability of a corn stover-based biorefinery.

  1. SWR 1000: An Advanced, Medium-Sized Boiling Water Reactor, Ready for Deployment

    SciTech Connect

    Brettschuh, Werner

    2006-07-01

    The latest developments in nuclear power generation technology mainly concern large-capacity plants in the 1550 -1600 MW range, or very small plants (100 - 350 MW). The SWR 1000 boiling water reactor (BWR), by contrast, offers all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation costs, in the medium-capacity range (1000 - 1250 MW). The SWR 1000 is particularly suitable for countries whose power systems are not designed for large-capacity generating facilities. The economic efficiency of this medium-sized plant in comparison with large-capacity designs is achieved by deploying very simple passive safety equipment, simplified systems for plant operation, and a very simple plant configuration in which systems engineering is optimized and dependence on electrical and instrumentation and control (I and C) systems is reduced. In addition, systems and components that require protection against natural and external man-made hazards are accommodated in such a way that as few buildings as possible have to be designed to withstand the loads from such events. The fuel assemblies to be deployed in the SWR 1000 core, meanwhile, have been enlarged from a 10 x 10 rod array to a 12 x 12 array. This reduces the total number of fuel assemblies in the core and thus also the number of control rods and control rod drives, as well as in-core neutron flux monitors. The design owes its competitiveness to the fact that investment costs, maintenance costs and fuel cycle costs are all lower. In addition, refueling outages are shorter, thanks to the reduced scope of outage activities. The larger fuel assemblies have been extensively and successfully tested, as have all of the other new components and systems incorporated into the plant design. As in existing plants, the forced coolant circulation method is deployed, ensuring problem-free startup, and enabling plant operators to adjust power rapidly in the high power range (70

  2. Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons. [PWR; BWR

    SciTech Connect

    Yoder, G. L.; Morris, D. G.; Mullins, C. B.; Ott, L. J.; Reed, D. A.

    1982-03-01

    Assessment of six film boiling correlations and one single-phase vapor correlation has been made using data from 22 steady state upflow rod bundle tests (series 3.07.9). Bundle fluid conditions were calculated using energy and mass conservation considerations. Results of the steady state film boiling tests support the conclusions reached in the analysis of prior transient tests 3.03.6AR, 3.06.6B, and 3.08.6C. Comparisons between experimentally determined and correlation-predicted heat transfer coefficients, are presented.

  3. Microsoft PowerPoint - Interface_Levin

    Office of Environmental Management (EM)

    Adam H. Levin AHL Consulting May 14, 2014 BWR - Boiling Water Reactor DOE - Department of Energy DSC - Dry Storage Canister ISF - Interim Storage Facility ISFSI - Independent Spent Fuel Storage Installation PWR - Pressurized Water Reactor SNF - Spent Nuclear Fuel 2 5/16/2014 2 The status of spent fuel storage across industry - what's out there and what is industry likely to turn over to DOE? Near-term spent fuel management at operating reactor sites - will industry change to meet DOE needs as

  4. Point Bio Energy LLC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Point Bio Energy LLC Jump to: navigation, search Name: Point Bio Energy LLC Place: La Pointe, Wisconsin Product: Wisconsin-based wood fuel pellet producer. References: Point Bio...

  5. Final Project Report

    SciTech Connect

    Wang, Qiang; Dandy, David S.

    2015-05-15

    This is the final technical report of the DOE project DE-FG02-07ER46448 awarded to Colorado State University.

  6. National Science Bowl Finals

    ScienceCinema

    None

    2016-07-12

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  7. DOE Final Report

    SciTech Connect

    Hinzman, Larry D.; Long, James; Newby, Greg B.

    2014-01-08

    This final report contains a summary of work accomplished in the establishment of a Climate Data Center at the International Arctic Research Center, University of Alaska Fairbanks.

  8. Influence of lubricant oil on heat transfer performance of refrigerant flow boiling inside small diameter tubes. Part II: Correlations

    SciTech Connect

    Wei, Wenjian; Ding, Guoliang; Hu, Haitao; Wang, Kaijian

    2007-10-15

    The predictive ability of the available state-of-the-art heat transfer correlations of refrigerant-oil mixture is evaluated with the present experiment data of small tubes with inside diameter of 6.34 mm and 2.50 mm. Most of these correlations can be used to predict the heat transfer coefficient of 6.34 mm tube, but none of them can predict heat transfer coefficient of 2.50 mm tube satisfactorily. A new correlation of two-phase heat transfer multiplier with local properties of refrigerant-oil mixture is developed. This correlation approaches the actual physical mechanism of flow boiling heat transfer of refrigerant-oil mixture and can reflect the actual co-existing conditions of refrigerant and lubricant oil. More than 90% of the experiment data of both test tubes have less than {+-}20% deviation from the prediction values of the new correlations. (author)

  9. Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

    SciTech Connect

    McCormack, K.E.; Gallaher, R.B.

    1982-03-01

    This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

  10. Experimental and Thermalhydraulic Code Assessment of the Transient Behavior of the Passive Condenser System in an Advanced Boiling Water Reactor

    SciTech Connect

    S.T. Revankar; W. Zhou; Gavin Henderson

    2008-07-08

    The main goal of the project was to study analytically and experimentally the condensation heat transfer for the passive condenser system such as GE Economic Simplified Boiling Water Reactor (ESBWR). The effect of noncondensable gas in condenser tube and the reduction of secondary pool water level to the condensation heat transfer coefficient was the main focus in this research. The objectives of this research were to : 1) obtain experimental data on the local and tube averaged condensation heat transfer rates for the PCCS with non-condensable and with change in the secondary pool water, 2) assess the RELAP5 and TRACE computer code against the experimental data, and 3) develop mathematical model and ehat transfer correlation for the condensation phenomena for system code application. The project involves experimentation, theoretical model development and verification, and thermal- hydraulic codes assessment.

  11. Study of Pu consumption in advanced light water reactors: Evaluation of GE advanced boiling water reactor plants - compilation of Phase 1B task reports

    SciTech Connect

    1993-09-15

    This report contains an extensive evaluation of GE advanced boiling water reactor plants prepared for United State Department of Energy. The general areas covered in this report are: core and system performance; fuel cycle; infrastructure and deployment; and safety and environmental approval.

  12. Investigation of the physical and numerical foundations of two-fluid representation of sodium boiling with applications to LMFBR experiments

    SciTech Connect

    No, H.C.; Kazimi, M.S.

    1983-03-01

    This work involves the development of physical models for the constitutive relations of a two-fluid, three-dimensional sodium boiling code, THERMIT-6S. The code is equipped with a fluid conduction model, a fuel pin model, and a subassembly wall model suitable for stimulating LMFBR transient events. Mathematically rigorous derivations of time-volume averaged conservation equations are used to establish the differential equations of THERMIT-6S. These equations are then discretized in a manner identical to the original THERMIT code. A virtual mass term is incorporated in THERMIT-6S to solve the ill-posed problem. Based on a simplified flow regime, namely cocurrent annular flow, constitutive relations for two-phase flow of sodium are derived. The wall heat transfer coefficient is based on momentum-heat transfer analogy and a logarithmic law for liquid film velocity distribution. A broad literature review is given for two-phase friction factors. It is concluded that entrainment can account for some of the discrepancies in the literature. Mass and energy exchanges are modelled by generalization of the turbulent flux concept. Interfacial drag coefficients are derived for annular flows with entrainment. Code assessment is performed by simulating three experiments for low flow-high power accidents and one experiment for low flow/low power accidents in the LMFBR. While the numerical results for pre-dryout are in good agreement with the data, those for post-dryout reveal the need for improvement of the physical models. The benefits of two-dimensional non-equilibrium representation of sodium boiling are studied.

  13. Microsoft PowerPoint - Garcia-Diaz - LiT Electrolysis Projects Summary V3

    Office of Environmental Management (EM)

    Department of Energy Final translated version of Tsinghua Speech Microsoft PowerPoint - Final translated version of Tsinghua Speech Microsoft PowerPoint - Final translated version of Tsinghua Speech (4.8 MB) More Documents & Publications Heating Ventilation and Air Conditioning Efficiency GNEP Element:Expand Domestic Use of Nuclear Power Greenpower Trap Mufflerl System

    Tutorial Module 1: Introduction to Earned Value Management Prepared by: Module 1 - Introduction 1 Prepared by: Booz

  14. EA-1942: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    with the public interest. DOE adopted FERC's EA as DOE's Final EA. PDF icon EA-1942-FEA-2014.pdf More Documents & Publications Order 3331-A: Dominion Cove Point LNG, LP - Dk....

  15. EIS-0121: Final Environmental Impact Statement | Department of Energy

    Energy Saver

    02: Final Environmental Impact Statement EIS-0002: Final Environmental Impact Statement Allocation of Petroleum Feedstock, Baltimore Gas & Electric Co., Sollers Point SNG Plant, Sollers Point, Baltimore County, Maryland The Economic Regulatory Administration (ERA) developed this EIS to evaluate the social, economic and environmental impacts which may occur within the Baltimore Gas and Electric Company (BG&E) service area as a result of the ERA' s proposed decision to allocate up to

  16. EIS-0002: Final Environmental Impact Statement | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    02: Final Environmental Impact Statement EIS-0002: Final Environmental Impact Statement Allocation of Petroleum Feedstock, Baltimore Gas & Electric Co., Sollers Point SNG Plant, Sollers Point, Baltimore County, Maryland The Economic Regulatory Administration (ERA) developed this EIS to evaluate the social, economic and environmental impacts which may occur within the Baltimore Gas and Electric Company (BG&E) service area as a result of the ERA' s proposed decision to allocate up to

  17. An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance

    SciTech Connect

    Kelly, D.L.; Jones, K.R.; Dallman, R.J. ); Wagner, K.C. )

    1990-07-01

    This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents. Also assessed are some potential improvements that could prevent core damage or containment failure, or could mitigate the consequences of such failure by reducing the release of fission products to the environment. These challenges and improvements are analyzed via a limited quantitative risk/benefit analysis of a generic BWR/4 reactor with Mark II containment. Point estimate frequencies of the dominant core damage sequences are obtained and simple containment event trees are constructed to evaluate the response of the containment to these severe accident sequences. The resulting containment release modes are then binned into source term release categories, which provide inputs to the consequence analysis. The output of the consequences analysis is used to construct an overall base case risk profile. Potential improvements and sensitivities are evaluated by modifying the event tree spilt fractions, thus generating a revised risk profile. Several important sensitivity cases are examined to evaluate the impact of phenomenological uncertainties on the final results. 75 refs., 25 figs., 65 tabs.

  18. Approximate Model for Turbulent Stagnation Point Flow.

    SciTech Connect

    Dechant, Lawrence

    2016-01-01

    Here we derive an approximate turbulent self-similar model for a class of favorable pressure gradient wedge-like flows, focusing on the stagnation point limit. While the self-similar model provides a useful gross flow field estimate this approach must be combined with a near wall model is to determine skin friction and by Reynolds analogy the heat transfer coefficient. The combined approach is developed in detail for the stagnation point flow problem where turbulent skin friction and Nusselt number results are obtained. Comparison to the classical Van Driest (1958) result suggests overall reasonable agreement. Though the model is only valid near the stagnation region of cylinders and spheres it nonetheless provides a reasonable model for overall cylinder and sphere heat transfer. The enhancement effect of free stream turbulence upon the laminar flow is used to derive a similar expression which is valid for turbulent flow. Examination of free stream enhanced laminar flow suggests that the rather than enhancement of a laminar flow behavior free stream disturbance results in early transition to turbulent stagnation point behavior. Excellent agreement is shown between enhanced laminar flow and turbulent flow behavior for high levels, e.g. 5% of free stream turbulence. Finally the blunt body turbulent stagnation results are shown to provide realistic heat transfer results for turbulent jet impingement problems.

  19. Final EIS Volume 2

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Volume 2 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site (Appendices A through R) AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final EIS, or to request a copy of the EIS or

  20. Aurora final report

    SciTech Connect

    Robert, Dross; Amedeo, Conti

    2013-12-06

    Final Technical report detailing the work done by Nuvera and its partners to fulfill the goals of the program "Transport Studies Enabling Efficiency Optimization of Cost-Competitive Fuel Cell Stacks" (a.k.a. AURORA)

  1. CFC Charity Fair Finale

    Energy.gov [DOE]

    Finish out the 2012 CFC with the Charity Fair Finale! Buy cookies, participate in a putt-putt golf game, eat some popcorn, and meet and talk with CFC charity representatives.

  2. CX-100 Final Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    SAND2008-4648 Unlimited Release Printed July 2008 Blade System Design Studies Phase II: Final Project Report Derek S. Berry TPI Composites, Inc. 373 Market Street Warren, RI 02885...

  3. Microsoft Word - Final Report

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    J. Michael Doster NCSU September 30, 2013 CASL-8-2013-0201-000 Final Report L3.THM.CFD.P7.07 Dr. J. Michael Doster Nuclear Engineering Department North Carolina State University ...

  4. Final EIS Available

    Energy.gov [DOE]

    DOE has published a Final Environmental Impact Statement (EIS) that considers all timely public comments on the Draft EIS and identifies DOE’s preferred project alternative(s). The U.S....

  5. Final focus test beam

    SciTech Connect

    Not Available

    1991-03-01

    This report discusses the following: the Final Focus Test Beam Project; optical design; magnets; instrumentation; magnetic measurement and BPM calibration; mechanical alignment and stabilization; vacuum system; power supplies; control system; radiation shielding and personnel protection; infrastructure; and administration.

  6. Blackout Final Implementation Report

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force Natural Resources Canada U.S. Department of Energy September 2006 Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force September 2006 Natural Resources Canada U.S. Department of Energy Acknowledgments This document was prepared by staff of Natural Resources Canada and the U.S. Department of Energy. The principal contributors

  7. Final - Gasbuggy S

    Office of Legacy Management (LM)

    Gasbuggy S i t e Environmental Management End State Vision - January 2005 U.S. DEPARTMENT OF ENERGY Gasbuggy Site ENVIRONMENTAL MANAGEMENT END STATE VISION Final Final - Gasbuggy Site Environmental Management End State Vhion - fanuaty 2005 Executive Summary The Environmental Management End State Vision is to be used as the primary tool for communicating the individual site end state to the involved parties (e.g., U.S. Department of Energy [DOE], regulators, public stakeholders, Tribal Nations).

  8. Final Environmental Impact Statement

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    EIS - 0097-F c f ` f= �c J m s= Final Environmental Impact Statement BONNEVILLE POWER ADMINISTRATION TRANSMISSION FACILITIES VEGETATION MANAGEMENT PROGRAM U.S. Department of Energy August 1983 Appendices albLbfp= J MMVTJc= Responsible Official: tfiif^j= ^K= s^rde^k= Assistant Secretary for Environmental Protection. Safety, and Emergency Prepafedness Final Environmental Impact Statement BONNEVILLE POWER ADM IN ISTRA TION TRANSMISSION FACILITIES VEGETATION MANAGEMENT PROGRAM U.S. Department of

  9. RPSEA FINAL TECHNICAL REPORT

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RPSEA FINAL TECHNICAL REPORT 12122.52.FINAL Hugh Daigle, Nicholas W. Hayman, Kyle Spikes, Julia Gale, Peter Eichhubl, Kitty L. Milliken University of Texas at Austin Connectivity between Fractures and Pores in Hydrocarbon-Rich Mudrocks Contract Number 12122-52 June 24, 2016 Principal Investigator: Hugh Daigle Assistant Professor Department of Petroleum and Geosystems Engineering University of Texas at Austin 200 E Dean Keeton St., Stop C0300, Austin, TX 78712-1585 2 LEGAL NOTICE This report was

  10. Caspary Thesis Final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    DENSITY AND BETA LIMITS IN THE MADISON SYMMETRIC TORUS REVERSED-FIELD PINCH by KYLE JONATHAN CASPARY A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (PHYSICS) at the UNIVERSITY OF WISCONSIN-MADISON 2014 Date of final oral examination: March 24th, 2014 The dissertation is under review by the following members of the Final Oral Committee: Brett Chapman, Senior Scientist, Physics John Sarff, Professor, Physics Paul Terry, Professor, Physics

  11. Steam Line Break and Station Blackout Transients for Proliferation-Resistant Hexagonal Tight Lattice Boiling Water Reactor

    SciTech Connect

    Rohatgi, Upendra S. [Brookhaven National Laboratory (United States); Jo, Jae H. [Brookhaven National Laboratory (United States); Chung, Bub Dong [Brookhaven National Laboratory (United States); Takahashi, Hiroshi [Brookhaven National Laboratory (United States); Downar, Thomas J. [Purdue University (United States)

    2004-01-15

    Safety analyses of a proliferation-resistant, economically competitive, high-conversion boiling water reactor (HCBWR) fueled with fissile plutonium and fertile thorium oxide fuel elements, and with passive safety systems, are presented here. The HCBWR developed here is characterized by a very tight lattice with a relatively small water volume fraction in the core that therefore operates with a fast reactor neutron spectrum and a considerably improved neutron economy compared to the current generation of light water reactors. The tight lattice core has a very narrow flow channel with a hydraulic diameter less than half of the regular boiling water reactor (BWR) core and, thus, presents a special challenge to core cooling because of reduced water inventory and high friction in the core. The primary safety concern when reducing the moderator-to-fuel ratio and when using a tightly packed lattice arrangement is to maintain adequate cooling of the core during both normal operation and accident scenarios.In the preliminary HCBWR design, the core is placed in a vessel with a large chimney section, and the vessel is connected to the isolation condenser system (ICS). The vessel is placed in containment with the gravity driven cooling system (GDCS) and passive containment cooling system (PCCS) in a configuration similar to General Electric's simplified BWR (SBWR). The safety systems are similar to those of the SBWR; the ICS and PCCS are scaled with power. An internal recirculation pump is placed in the downcomer to augment the buoyancy head provided by the chimney since the buoyancy provided by the chimney alone could not generate sufficient recirculation in the vessel as the tight lattice configuration results in much larger friction in the core than with the SBWR.The constitutive relationships for RELAP5 are assessed for narrow channels, and as a result the heat transfer package is modified. The modified RELAP5 is used to simulate and analyze two of the most limiting events

  12. Star Point Wind Farm | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Point Wind Farm Jump to: navigation, search Name Star Point Wind Farm Facility Star Point Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status In...

  13. Cedar Point Wind Farm | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Cedar Point Wind Farm Jump to: navigation, search Name Cedar Point Wind Farm Facility Cedar Point Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status...

  14. PowerPoint Presentation | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    PowerPoint Presentation PowerPoint Presentation PDF icon PowerPoint Presentation More Documents & Publications 2012 Quality Assurance Improvement Project Plan EM QA Working Group...

  15. Apparatus for draining lower drywell pool water into suppresion pool in boiling water reactor

    DOEpatents

    Gluntz, Douglas M.

    1996-01-01

    An apparatus which mitigates temperature stratification in the suppression pool water caused by hot water drained into the suppression pool from the lower drywell pool. The outlet of a spillover hole formed in the inner bounding wall of the suppression pool is connected to and in flow communication with one end of piping. The inlet end of the piping is above the water level in the suppression pool. The piping is routed down the vertical downcomer duct and through a hole formed in the thin wall separating the downcomer duct from the suppression pool water. The piping discharge end preferably has an elevation at or near the bottom of the suppression pool and has a location in the horizontal plane which is removed from the point where the piping first emerges on the suppression pool side of the inner bounding wall of the suppression pool. This enables water at the surface of the lower drywell pool to flow into and be discharged at the bottom of the suppression pool.

  16. Microsoft PowerPoint - OTT RFI Summary of Input_Public_Oct 2015

    Energy Saver

    Energy FY11 budget rollout 2-1-10 final Microsoft PowerPoint - FY11 budget rollout 2-1-10 final Microsoft PowerPoint - FY11 budget rollout 2-1-10 final (823.93 KB) More Documents & Publications FY 2010 Budget Roll-Out Presentation Department of Energy FY 2007 Budget Microsoft PowerPoint - FY 2007 DOE Budget Rollout--Printer Version.ppt

    Executive Service (SES) Performance Management Training Table of Contents * Overview * Planning Performance * Monitoring and Developing Performance *

  17. Final Report Full-Scale Test of DWPF Advanced Liquid-Level and Density Measurement Bubblers

    SciTech Connect

    Duignan, M.R.; Weeks, G.E.

    1999-07-01

    As requested by the Technical Task Request (1), a full-scale test was carried out on several different liquid-level measurement bubblers as recommended from previous testing (2). This final report incorporates photographic evidence (Appendix B) of the bubblers at different stages of testing, along with the preliminary results (Appendix C) which were previously reported (3), and instrument calibration data (Appendix D); while this report contains more detailed information than previously reported (3) the conclusions remain the same. The test was performed under highly prototypic conditions from November 26, 1996 to January 23, 1997 using the full-scale SRAT/SME tank test facilities located in the 672-T building at TNX. Two different types of advanced bubblers were subjected to approximately 58 days of slurry operation; 14 days of which the slurry was brought to boiling temperatures.The test showed that the large diameter tube bubbler (2.64 inches inside diameter) operated successfully throughout the2-month test by not plugging with the glass-frit ladened slurry which was maintained at a minimum temperature of 50 deg Cand several days of boiling temperatures. However, a weekly blow-down with air or water is recommended to minimize the slurry which builds up.The small diameter porous tube bubbler (0.62 inch inside diameter; water flow {gt} 4 milliliters/hour = 1.5 gallons/day) operated successfully on a daily basis in the glass-frit ladened slurry which was maintained at a minimum temperature of 50 degrees C and several days of boiling temperatures. However, a daily blow-down with air, or air and water, is necessary to maintain accurate readings.For the small diameter porous tube bubbler (0.62 inch inside diameter; water flow {gt} 4 milliliters/hour = 1.5 gallons/day) there were varying levels of success with the lower water-flow tubes and these tubes would have to be cleaned by blowing with air, or air and water, several times a day to maintain them plug free. This

  18. Explosive boiling of Ge{sub 35}Sb{sub 10}S{sub 55} glass induced by a CW laser

    SciTech Connect

    Knotek, P.; Tichy, L.

    2013-09-01

    Graphical abstract: - Highlights: Interaction of the CW 785 nm laser with chalcogenide GeSbS glass. First demonstration of the explosive boiling induced by CW laser in glass. Different processes as photo-induced oxidation, expansion, and viscosity-flow observed. Applied diagnostics SEM, DHM, AFM, force spectroscopy, and micro-Raman spectroscopy. Damage threshold determined at 1.2 10{sup 24}s{sup ?1} cm{sup ?3} of absorbed photons. - Abstract: The response of bulk Ge{sub 35}Sb{sub 10}S{sub 55} glass to illumination by a continuous wave (CW) laser, sub-band-gap photons, was studied specifically with an atomic force microscopy including a force spectroscopy, with a digital holographic microscopy and with a scanning electron microscopy. Depending on the number of photons absorbed, photo-expansion, photo-oxidation and explosive boiling were observed.

  19. Study of Pu consumption in Advanced Light Water Reactors. Evaluation of GE Advanced Boiling Water Reactor plants

    SciTech Connect

    Not Available

    1993-05-13

    Timely disposal of the weapons plutonium is of paramount importance to permanently safeguarding this material. GE`s 1300 MWe Advanced Boiling Water Reactor (ABWR) has been designed to utilize fill] core loading of mixed uranium-plutonium oxide fuel. Because of its large core size, a single ABWR reactor is capable of disposing 100 metric tons of plutonium within 15 years of project inception in the spiking mode. The same amount of material could be disposed of in 25 years after the start of the project as spent fuel, again using a single reactor, while operating at 75 percent capacity factor. In either case, the design permits reuse of the stored spent fuel assemblies for electrical energy generation for the remaining life of the plant for another 40 years. Up to 40 percent of the initial plutonium can also be completely destroyed using ABWRS, without reprocessing, either by utilizing six ABWRs over 25 years or by expanding the disposition time to 60 years, the design life of the plants and using two ABWRS. More complete destruction would require the development and testing of a plutonium-base fuel with a non-fertile matrix for an ABWR or use of an Advanced Liquid Metal Reactor (ALMR). The ABWR, in addition, is fully capable of meeting the tritium target production goals with already developed target technology.

  20. Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel

    SciTech Connect

    Trianti, Nuri E-mail: szaki@fi.itba.c.id; Su'ud, Zaki E-mail: szaki@fi.itba.c.id; Arif, Idam E-mail: szaki@fi.itba.c.id; Riyana, EkaSapta

    2014-09-30

    Neutronic performance of small long-life boiling water reactors (BWR) with thorium nitride based fuel has been performed. A recent study conducted on BWR in tight lattice environments (with a lower moderator percentage) produces small power reactor which has some specifications, i.e. 10 years operation time, power density of 19.1 watt/cc and maximum excess reactivity of about 4%. This excess reactivity value is smaller than standard reactivity of conventional BWR. The use of hexagonal geometry on the fuel cell of BWR provides a substantial effect on the criticality of the reactor to obtain a longer operating time. Supported by a tight concept lattice where the volume fraction of the fuel is greater than the moderator and fuel, Thorium Nitride give good results for fuel cell design on small long life BWR. The excess reactivity of the reactor can be reduced with the addition of gadolinium as burnable poisons. Therefore the hexagonal tight lattice fuel cell design of small long life BWR that has a criticality more than 20 years of operating time has been obtained.

  1. Influence of lubricant oil on heat transfer performance of refrigerant flow boiling inside small diameter tubes. Part I: Experimental study

    SciTech Connect

    Wei, Wenjian; Ding, Guoliang; Hu, Haitao; Wang, Kaijian

    2007-10-15

    Two-phase flow pattern and heat transfer characteristics of refrigerant-oil mixture flow boiling inside small tubes with inside diameters of 6.34 mm and 2.50 mm are investigated experimentally. The test condition of nominal oil concentration is from 0% to 5%, mass flux from 200 to 400 kg m{sup -2} s{sup -1}, heat flux from 3.2 to 14 kW m{sup -2}, evaporation temperature of 5 C, inlet quality from 0.1 to 0.8, and quality change from 0.1 to 0.2. Wavy, wavy-annular, annular and mist-annular flow pattern in 6.34 mm tube are observed, while only slug-annular and annular flow pattern are observed in 2.50 mm tube. Oil presence can make annular flow to form early and to retard to diminish in quality direction at nominal oil concentration {>=}3%. Augmentation effect of oil on heat transfer coefficient becomes weakened or even diminishes for small diameter tube while detrimental effect of oil on small tube performance becomes more significant than large tube. For both test tubes, variation of heat transfer coefficient and enhanced factor with oil concentration is irregular. Two-phase heat transfer multiplier with refrigerant-oil mixture properties increases consistently and monotonically with local oil concentration at different vapor quality. (author)

  2. Simulation of in-core neutron noise measurements for axial void profile reconstruction in boiling water reactors

    SciTech Connect

    Dykin, V.; Pazsit, I.

    2012-07-01

    A possibility to reconstruct the axial void profile from the simulated in-core neutron noise which is caused by density fluctuations in a Boiling Water Reactor (BWR) heated channel is considered. For this purpose, a self-contained model of the two-phase flow regime is constructed which has quantitatively and qualitatively similar properties to those observed in real BWRs. The model is subsequently used to simulate the signals of neutron detectors induced by the corresponding perturbations in the flow density. The bubbles are generated randomly in both space and time using Monte-Carlo techniques. The axial distribution of the bubble production is chosen such that the mean axial void fraction and void velocity follow the actual values of BWRs. The induced neutron noise signals are calculated and then processed by the standard signal analysis methods such as Auto-Power Spectral Density (APSD) and Cross-Power Spectral Density (CPSD). Two methods for axial void and velocity profiles reconstruction are discussed: the first one is based on the change of the break frequency of the neutron auto-power spectrum with axial core elevation, while the second refers to the estimation of transit times of propagating steam fluctuations between different axial detector positions. This paper summarizes the principles of the model and presents a numerical testing of the qualitative applicability to estimate the required parameters for the reconstruction of the void fraction profile from the neutron noise measurements. (authors)

  3. Development, implementation and assessment of specific, two-fluid closure laws for inverted-annular film-boiling

    SciTech Connect

    Cachard, F. de

    1995-09-01

    Inverted-Annular Film-Boiling (IAFB) is one of the post-burnout heat transfer modes taking place during the reflooding phase of the loss-of-coolant accident, when the liquid at the quench front is subcooled. Under IAFB conditions, a continuous, liquid core is separated from the wall by a superheated vapour film. the heat transfer rate in IAFB is influenced by the flooding rate, liquid subcooling, pressure, and the wall geometry and temperature. These influences can be accounted by a two-fluid model with physically sound closure laws for mass, momentum and heat transfers between the wall, the vapour film, the vapour-liquid interface, and the liquid core. Such closure laws have been developed and adjusted using IAFB-relevant experimental results, including heat flux, wall temperature and void fraction data. The model is extensively assessed against data from three independent sources. A total of 46 experiments have been analyzed. The overall predictions are good. The IAFB-specific closure laws proposed have also intrinsic value, and may be used in other two-fluid models. They should allow to improve the description of post-dryout, low quality heat transfer by the safety codes.

  4. Boiling water reactor fuel behavior at burnup of 26 GWd/tonne U under reactivity-initiated accident conditions

    SciTech Connect

    Nakamura, Takehiko; Yoshinaga, Makio . Dept. of Reactor Safety Research); Sobajima, Makoto ); Ishijima, Kiyomi; Fujishiro, Toshio . Dept. of Reactor Safety Research)

    1994-10-01

    Irradiated boiling water reactor (BWR) fuel behavior under reactivity-initiated accident (RIA) conditions was investigated in the Nuclear Safety Research Reactor (NSRR) of the Japan Atomic Energy Research Institute. Short test fuel rods, refabricated from a commercial 7 x 7 type BWR fuel rod at a burnup of 26 GWd/ tonne U, were pulse irradiated in the NSRR under simulated cooled startup RIA conditions of the BWRs. Thermal energy from 230 J/g fuel (55 cal/g fuel) to 410 J/g fuel (98 cal/g fuel) was promptly subjected to the test fuel rods by pulse irradiation within [approximately] 10 ms. The peak fuel enthalpies are believed to be the same as the prompt energy depositions. The test fuel rods demonstrated characteristic behavior of the irradiated fuel rods under the accident conditions, such as enhanced pellet cladding mechanical interaction (PCMI) and fission gas release. However, all the fuel rods survived the accident conditions with considerable margins. Simulations by the FRAP-T6 code and fresh fuel rod tests under the same RIA conditions highlighted the burnup effects on the accident fuel performance. The tests and the simulation suggested that the BWR fuel would possibly fail by a cladding burst due to fission gas release during the cladding temperature escalation rather than the PCMI under the cold startup RIA conditions of a severe power burst.

  5. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    SciTech Connect

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  6. Final Technical Report

    SciTech Connect

    Gilbert, Chris

    2014-11-13

    The project, Capital Investment to Fund Equipment Purchases and Facility Modifications to Create a Sustainable Future for EnergyXchange served to replace landfill gas energy with alternative energy resources, primarily solar and wood waste. This is the final project closeout report.

  7. Continuous Learning Points: Earn CLPs!

    Energy.gov [DOE]

    Attendees at the PM Workshop can earn Continuing Learning Points (CLPs) for both days in addition to earning CLPs for the optional half-day training sessions on Earned Value Management and Federal Acquisition Institute Training Application System. Click on this CLP form for instructions.

  8. Microsoft PowerPoint - 7_LAUREN_GIBSON_NMMSS Presentation Gibson...

    National Nuclear Security Administration (NNSA)

    Venting System Applies to boiling water reactors with certain designs (Mark III) ... Requires installation of water level instrumentation to indicate: 1 - Normal fuel pool ...

  9. Final Technical Report

    SciTech Connect

    Maxwell, Mike, J., P.E.

    2012-08-30

    The STI product is the Final Technical Report from ReliOn, Inc. for contract award DE-EE0000487: Recovery Act PEM Fuel Cell Systems Providing Emergency Reserve and Backup Power. The program covered the turnkey deployment of 431 ReliOn fuel cell systems at 189 individual sites for AT&T and PG&E with ReliOn functioning as the primary equipment supplier and the project manager. The Final Technical Report provides an executive level summary, a comparison of the actual accomplishments vs. the goals and objectives of the project, as well as a summary of the project activity from the contract award date of August 1, 2009 through the contract expiration date of December 31, 2011. Two photos are included in the body of the report which show hydrogen storage and bulk hydrogen refueling technologies developed as a result of this program.

  10. Flatsheet_Final

    Office of Environmental Management (EM)

    Department of Energy First Solar AVSR Solar Ranch Technical Eligibility Re-Evaluation Memo First Solar AVSR Solar Ranch Technical Eligibility Re-Evaluation Memo First_Solar_AVSR_Solar_Ranch_One_Technical_Eligibility_Re-Evaluation.pdf (81.63 KB) More Documents & Publications ANTELOPE VALLEY SOLAR RANCH EA-1826: Final Environmental Assessment REEE Solicitation Public Meeting Presentation Department of Energy

    First Step to Spur U.S. Manufacturing of Small Modular Nuclear Reactors

  11. CenterPoint_COMMENTS.pdf

    Energy Saver

    Categorical Exclusion Determinations: A1 Existing Regulations A1: Routine DOE business actions Routine actions necessary to support the normal conduct of DOE business limited to administrative, financial, and personnel actions. Previous Regulations Categorical Exclusion Determinations dated before November 14th, 2011 were issued under previous DOE NEPA regulations. See the Notice of Final Rulemaking (76 FR 63763, 10/13/2011) for information changes to this categorical exclusion. DOCUMENTS

  12. An Updated Point Design for Heavy Ion Fusion

    SciTech Connect

    Yu, S S; Meier, W R; Abbott, R B; Barnard, J J; Brown, t; Callahan, D A; Heitzenroeder, P; Latkowski, J F; Logan, B G; Pemberton, S J; Peterson, P F; Rose, D V; Sabbi, G -L; Sharp, W M; Welch, D R

    2002-12-16

    An updated, self-consistent point design for a heavy ion fusion (HIF) power plant based on an induction linac driver, indirect-drive targets, and a thick liquid wall chamber has been completed. Conservative parameters were selected to allow each design area to meet its functional requirements in a robust manner, and thus this design is referred to as the Robust Point Design (RPD-2002). This paper provides a top-level summary of the major characteristics and design parameters for the target, driver, final focus magnet layout and shielding, chamber, beam propagation to the target, and overall power plant.

  13. An Updated Point Design for Heavy Ion Fusion

    SciTech Connect

    Meier, W R; Yu, S S; Abbott, R P; Barnard, J J; Brown, T; Callahan, D A; Heitzenroeder, P; Latkowski, J F; Logan B G; Pemberton, S J; Peterson, P F; Rose, D V; Sabbi, G-L; Sharp, W M; Welch, D R

    2002-11-12

    An updated, self-consistent point design for a heavy ion fusion (HIF) power plant based on an induction linac driver, indirect-drive targets, and a thick liquid wall chamber has been completed. Conservative parameters were selected to allow each design area to meet its functional requirements in a robust manner, and thus this design is referred to as the Robust Point Design (RPD-2002). This paper provides a top-level summary of the major characteristics and design parameters for the target, driver, final focus magnet layout and shielding, chamber, beam propagation to the target, and overall power plant.

  14. An updated point design for heavy ion fusion

    SciTech Connect

    Yu, S.S.; Meier, W.R.; Abbott, R.P.; Barnard, J.J.; Brown, T.; Callahan, D.A.; Heitzenroeder, P.; Latkowski, J.F.; Logan, B.G.; Pemberton, S.J.; Peterson, P.F.; Rose, D.V.; Sabbi, G-L.; Sharp, W.M.; Welch, D.R.

    2002-11-01

    An updated, self-consistent point design for a heavy ion fusion (HIF) power plant based on an induction linac driver, indirect-drive targets, and a thick liquid wall chamber has been completed. Conservative parameters were selected to allow each design area to meet its functional requirements in a robust manner, and thus this design is referred to as the Robust Point Design (RPD-2002). This paper provides a top-level summary of the major characteristics and design parameters for the target, driver, final focus magnet layout and shielding, chamber, beam propagation to the target, and overall power plant.

  15. On the nature of unstable equilibrium points in power systems

    SciTech Connect

    Berggren, B.; Andersson, G. . Dept. of Electric Power Systems)

    1993-05-01

    This paper concerns the application of direct methods for transient stability analysis of stressed power systems. One of the most important issues in this area is to find the controlling unstable equilibrium point for the disturbance under consideration. This paper provides a conceptual framework for discussing stable and unstable equilibrium points in power systems based on simple topological arguments. It is for instance shown that every conceivable case of system separation can be related to a specific unstable equilibrium point (u.e.p) in an unloaded system. This result can be seen as a verification of the soundness of the often used corrected corner point approximation and ray point approximation, since these two approximations would give the same unstable equilibrium points in an unloaded system. Moreover, it is shown, by an example, that some of these unstable equilibrium points can disappear when the loading of the system increases. The implications of the findings of this paper are discussed for the so-called MOD method of finding the controlling u.e.p., which is used in some software packages. Finally, a method based on a combination of MOD method and the BCU method is outlined and proposed as the subject of future investigation.

  16. Final Scientific/Technical Report

    SciTech Connect

    Troxell, W; Batchelor, A

    2012-11-28

    Final report for the formation of faculty and education establishing Colorado State's Smart Grid Integration Center

  17. Point contacts in encapsulated graphene

    SciTech Connect

    Handschin, Clevin; Fülöp, Bálint; Csonka, Szabolcs; Makk, Péter; Blanter, Sofya; Weiss, Markus; Schönenberger, Christian; Watanabe, Kenji; Taniguchi, Takashi

    2015-11-02

    We present a method to establish inner point contacts with dimensions as small as 100 nm on hexagonal boron nitride (hBN) encapsulated graphene heterostructures by pre-patterning the top-hBN in a separate step prior to dry-stacking. 2- and 4-terminal field effect measurements between different lead combinations are in qualitative agreement with an electrostatic model assuming point-like contacts. The measured contact resistances are 0.5–1.5 kΩ per contact, which is quite low for such small contacts. By applying a perpendicular magnetic field, an insulating behaviour in the quantum Hall regime was observed, as expected for inner contacts. The fabricated contacts are compatible with high mobility graphene structures and open up the field for the realization of several electron optical proposals.

  18. Femtosecond photoelectron point projection microscope

    SciTech Connect

    Quinonez, Erik; Handali, Jonathan; Barwick, Brett

    2013-10-15

    By utilizing a nanometer ultrafast electron source in a point projection microscope we demonstrate that images of nanoparticles with spatial resolutions of the order of 100 nanometers can be obtained. The duration of the emission process of the photoemitted electrons used to make images is shown to be of the order of 100 fs using an autocorrelation technique. The compact geometry of this photoelectron point projection microscope does not preclude its use as a simple ultrafast electron microscope, and we use simple analytic models to estimate temporal resolutions that can be expected when using it as a pump-probe ultrafast electron microscope. These models show a significant increase in temporal resolution when comparing to ultrafast electron microscopes based on conventional designs. We also model the microscopes spectroscopic abilities to capture ultrafast phenomena such as the photon induced near field effect.

  19. Turning points in reactor design

    SciTech Connect

    Beckjord, E.S.

    1995-09-01

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems.

  20. Final Technical Report

    SciTech Connect

    Sobecky, Patricia A; Taillefert, Martial

    2013-03-29

    This final technical report describes results and findings from a research project to examine the role of microbial phosphohydrolase enzymes in naturally occurring subsurface microorganisms for the purpose of promoting the immobilization of the radionuclide uranium through the production of insoluble uranium phosphate minerals. The research project investigated the microbial mechanisms and the physical and chemical processes promoting uranium biomineralization and sequestration in oxygenated subsurface soils. Uranium biomineralization under aerobic conditions can provide a secondary biobarrier strategy to immobilize radionuclides should the metal precipitates formed by microbial dissimilatory mechanisms remobilize due to a change in redox state.

  1. Near-Final Agenda

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    09 26 2014 Near-Final Agenda Workshop on Estimating the Benefits and Costs of Distributed Energy Technologies September 30 - October 1, 2014 Washington, DC September 30 - Day One 8:00 a.m. Coffee and Registration 8:30 Welcome and Opening Remarks * Overview and purpose of the workshop o Comments by senior DOE Officials o Q&A (time permitting) * Around-the-room introductions 9:00 Framing the Issues * Three presentations on key issues * Facilitated discussion 10:15 BREAK 10:30 Estimating the

  2. Microsoft PowerPoint - 16.1330_Rimando 110316 rev3 [Compatibility Mode] |

    Office of Environmental Management (EM)

    Department of Energy 16.1330_Rimando 110316 rev3 [Compatibility Mode] Microsoft PowerPoint - 16.1330_Rimando 110316 rev3 [Compatibility Mode] Microsoft PowerPoint - 16.1330_Rimando 110316 rev3 [Compatibility Mode] (8.01 MB) More Documents & Publications Microsoft PowerPoint - 01 Bosco PM Workshop BOSCO Feb22_2010PB final rcvd 5 Mar [Compatibility Mode] Microsoft PowerPoint - 16.0805_Tom Fox [Compatibility Mode] Microsoft PowerPoint - 15.1500_Michael Deane [Compatibility Mo

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    California Point Reyes Deployment AMF Home Point Reyes Home Data Plots and Baseline Instruments Experiment Planning MASRAD Proposal Abstract and Related Campaigns Outreach Posters Climate Research at Point Reyes National Seashore (horizontal) Climate Research at Point Reyes National Seashore (vertical) News Campaign Images AMF Deployment, Point Reyes National Seashore, California Point Reyes National Seashore, on the California coast north of San Francisco. Shelters: 38° 5' 30.51" N, 122°

  4. Florida Nuclear Profile - Turkey Point

    Energy Information Administration (EIA) (indexed site)

    Turkey Point" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 3,693,"5,356",88.2,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" 4,693,"5,950",98.0,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  5. TEPP Points of Contact | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Transportation Emergency Preparedness Program TEPP Points of Contact TEPP Points of Contact TEPP is a national program managed at a headquarters level and implemented through...

  6. Field's Point Wastewater Treatment Facility (Narragansett Bay...

    OpenEI (Open Energy Information) [EERE & EIA]

    Field's Point Wastewater Treatment Facility (Narragansett Bay Commission) Jump to: navigation, search Name Field's Point Wastewater Treatment Facility (Narragansett Bay Commission)...

  7. Microsoft PowerPoint - Meeting Materials rev 7 (final)[1].ppt

    Energy Saver

    ... inside the low voltage compartment. * Distribution transformers that fall outside the range of units covered by the ruling may look similar to others that are covered products. ...

  8. Microsoft PowerPoint - NTER deck (external)-12-6-2012 Final to Post.pptx

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    | 1 NTER The National Training & Education Resource www.nterlearning.org * Dr. Michelle Fox * Alex Cohen Energy Efficiency & Renewable Energy | 2 * Identifying the problems in online learning * NTER overview * Innovative Features of NTER - Open Source - Distributed search - Interactive and immersive training - 3D in browser assessments - Authoring: empowering all to create and learn - Social reviews * NTER Demo * How to get involved * Future Development - Expert reviews - E-Commerce -

  9. Microsoft PowerPoint - 06-13-13 NEAC (Final) - Lyons.pptx

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Cooperation Center in Prague R&D on advanced reactors that might utilize molten ... University of Milan, University of Cambridge, Westinghouse, Southern Nuclear, INL ...

  10. Microsoft PowerPoint - Guidance May DOE PA CoP Meeting_final...

    Office of Environmental Management (EM)

    Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards christopher.grossman@nrc.gov 301-415-0140 Interagency Performance ...

  11. Microsoft PowerPoint - Sykes - EM-4 EMAB 3-31-10 FINAL [Compatibility...

    Office of Environmental Management (EM)

    posture in the EM complex * Radioactive tank waste ... five decades of nuclear weapons development, production, ... and use measures to monitor progress 15 Operations ...

  12. Microsoft PowerPoint - NEGTN02-#212490-FINAL-NEAC_UFD_MONICA...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Recycled Alternative geologies Innovative approaches - U Seawater LWR fuel - Accident tolerance ... emphasis on decommission sites fuel, emphasis on ...

  13. Microsoft PowerPoint - ARPA-EM SEAB 7-14e - FINAL

    Office of Environmental Management (EM)

    * Coupled hydrogeologicanalytical data models to predict contaminant behavior * Virtualgaming environment to train workers and plan decommissioning * Remote and robotic...

  14. Microsoft PowerPoint - ARRA workscope slides Jun 15 FINAL.ppt [Compatibility Mode]

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    we're doing: Office of River Protection Activities funded by the American Reinvestment and Recovery Act Tank Farms Work Scope: Major Areas Tank Farm Infrastructure Upgrades Waste Feed Infrastructure Waste Feed Infrastructure Other Infrastructure Facility Upgrades Tentative scope as of 6/11/2009 <#> 2 What We're Doing Office of River Protection Activities funded by the American Reinvestment and Recovery Act Tank Farm Infrastructure Upgrades Ventilation at AP and SY Farms What: Design new

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Processes Working Group, ARM STM 2007 Radiative Processes Working Group, ARM STM 2007 CLOWD Overview CLOWD Overview CLOWD Overview CLOWD Overview Andy Vogelmann & Dave Turner Andy Vogelmann & Dave Turner Andy Vogelmann & Dave Turner Andy Vogelmann & Dave Turner Jennifer Comstock Jennifer Comstock Plus LOTS of PI Contributors Plus LOTS of PI Contributors Plus LOTS of PI Contributors Plus LOTS of PI Contributors Outline Outline 1. Introduction 1. Introduction 2. Current Activities

  16. Microsoft PowerPoint - Cimel_ARM_STM_2008_poster_final.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Cimel Sunphotometers at ACRF Sites History and Current Status Laurie Gregory, Richard Wagener, and Lynn Ma Brookhaven National Laboratory, Upton, New York More Information Cimel (CSPHOT) Instrument Page: http://www.arm.gov/instruments/instrument.php?id=csphot Aeronet http://aeronet.gsfc.nasa.gov/ ARM eXternal Data Center (XDC): http://www.xdc.arm.gov/, xdc_oper@arm.gov. ARM Google: http://google.arm.gov/ search for "Cimel OR CSPHOT OR CSPOT" ARM Cimel Sunphotometers As of August 2007,

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    T k R l S d DOE Tank Removal Study Hanford Advisory Board Tank Waste Committee Vince Panesko November 3, 2011 Concept Sketch for Tank Removal Concept Sketch for Tank Removal Page 3-3 of RPP-RPT-47167 Concept Sketch - Deep Soil Excavation Concept Sketch Deep Soil Excavation Page 3-3 of RPP-RPT-47167 Soil removal to 5 feet below tanks Soil removal to 5 feet below tanks 5 5 19,700 Ci Cs 137 5 feet below tank 25,100 Ci Cs 137 59,000 Ci Cs 137 CONCERNS CONCERNS 1. Does it make sense to spend $800

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Hanford Advisory Board Stacy Charboneau Deputy Manager November 3, 2011 Tank Farm Activities Tank Farm Activities *System Plan 6 *ARRA work is completed *Remote handling manipulator installed 222-S Hot Cell 2 *Remote handling manipulator installed at 222-S laboratory *Alternative analyses for capital projects Effluent Treatment Facility Tank Waste Retrieval Progress * MARS installed and operating in C-107 * Hard heel removal started in C-108 - Caustic dissolution began in October and scheduled

  19. Microsoft PowerPoint - FY 2011 RL Budget Roll Out Feb 1 2010_Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Congressional Budget Request U.S. Department of Energy February 1, 2010 FY 2011 Congressional Budget February 2010 Shrinking the Footprint of Active Site Cleanup Safe and Effective Cleanup that Protects the Columbia River Reduces the Active Site Footprint of Cleanup to 75 Square Miles (586 to 75) Significantly Reduces Long-Term Mortgage Costs At Completion, Shifts Emphasis and Resources to Full Scale Cleanup of the Central Plateau (75 square miles) Reduces Costs by "Right Sizing"

  20. Microsoft PowerPoint - FY11 budget rollout 2-1-10 final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Department of Energy FY 2011 Budget Overview February 1, 2010 2 Supporting the President's goals Energy "The nation that leads the clean energy economy will be the nation that leads the global economy. And America must be that nation." Innovation "We need to encourage innovation... And no area is more ripe for such innovation than energy." Security "...a clear goal: securing all vulnerable nuclear materials around the world in four years, so that they never fall into the

  1. Microsoft PowerPoint - HAB - Single-Shell Tank Closure April 27, 2016 Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Jim Alzheimer Washington State Department of Ecology Single-Shell Tank Engineer April 27, 2016 Single-Shell Tank Closure Ecology Perspective Single-Shell Tank System Closure Pieces  Tank Waste Retrieval  Closure of each SST under a component closure plan (i.e., Tier 3)  Closure of all other waste management area (WMA) components  Mitigation of vadose zone contamination  Coordination with mitigation of groundwater contamination  Coordination with other interfacing and WMA

  2. Microsoft PowerPoint - HAB 2012 Budget to Full Board Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Hanford Advisory Board 2012 Budget Discussion Paula Call Paula Call U.S. Department of Energy - Richland Operations Office Susan Leckband Susan Leckband Chair, Hanford Advisory Board November 4 2011 November 4, 2011 Special Executive Issues Committee Session * EIC met on October 11 to discuss HAB Fiscal Year (FY) 2012 budget and potential efficiencies 2012 budget and potential efficiencies * FY 2012 HAB base budget is similar to recent years * However significantly less carryover money *

  3. Microsoft PowerPoint - HAB-RAP-May 2015_Final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    River & Plateau Committee Groundwater Update Dib Goswami WA State Dept. Ecology May 12, 2015 Groundwater and Deep Vadose Zone 200 West Area: * Groundwater remediation is in place to address all existing past practice (CERCLA) and RCRA (Tank Farm) groundwater contamination * All deep vadose contamination (except CCL-4) yet to be addressed 200 East Area: * No groundwater remediation is currently in place * A treatability test to remediate Tc-99, U and nitrate is planned * All the deep vadose

  4. Microsoft PowerPoint - HAB1111-Conflict of Interest-Marla final.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Marla Marvin, RL Office of Chief Counsel Marla Marvin, RL Office of Chief Counsel Hanford Progress Update - Page 1 November 2011 RL Office of Chief Counsel RL Office of Chief Counsel Purpose of this Presentation Purpose of this Presentation Educate the Board on existing rules applicable to HAB from * HAB Operating Ground Rules http://www hanford gov/?page=449 HAB Operating Ground Rules http://www.hanford.gov/?page=449 * DOE Manual 515.1-1 on the Advisory Committee Management Program // / / / /

  5. Microsoft PowerPoint - HPC - Operations and Monitoring_Final (002) [Compatibility Mode]

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    5397 This document is approved for public release; further dissemination unlimited HPC Operations and Monitoring HPC Operations and Monitoring The Laboratory's supercomputers play a vital role in our mission of stockpile stewardship and scientific discoveries. * Our Operations Team is monitoring HPC systems 24/7 by 365. * Extensive modifications were made to customize the IT monitoring application Zenoss to fit our environment. Monitoring infrastructure built around RabbitMQ lays the foundation

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    3146 This document is approved for public release; further dissemination unlimited Resilience / Fault Injection Research ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● ● 0 10 20 30 40 50 60 70 80 32PB 64PB 96PB 128PB System Memory Capacity Uncorrected Error Rate (Relative to Cielo) ● ● ● ● ● ● 8Gbit / High FIT 8Gbit / Low FIT 16Gbit / High FIT 16Gbit / Low FIT 32Gbit / High FIT 32Gbit / Low FIT Resilience / Fault Injection Research

  7. Microsoft PowerPoint - HPC-FlexibleComputingStacks1_Final [Compatibility Mode]

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    5103 This document is approved for public release; further dissemination unlimited Flexible HPC Environments UNCLASSIFIED UNCLASSIFIED Flexible HPC Environments New computational paradigms require new tools and environments * A new class of data-analysis tools are available for scientists * These tools do not integrate well with traditional HPC resource management systems * Differing and often conflicting requirements exist * Some fields require validated environments * High energy physics *

  8. Microsoft PowerPoint - LIQUID_CLOUD_SUMMARY.final.amv.ppt [Compatibility Mode]

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Phase Subgroup Liquid Phase Subgroup B k t S f B k t S f Breakout Summary from Breakout Summary from Fall 2006 CPWG Fall 2006 CPWG Fall 2006 CPWG Fall 2006 CPWG (With Updates) (With Updates) Dave Turner and Andy Vogelmann ( p ) ( p ) Cloud Property Working Group Breakout Session 26 M h 2007 26 March 2007 Arm Science Team Meeting Monterey, California Sub Sub- -group Agenda: 9 Nov 2006 group Agenda: 9 Nov 2006 Presentations (7) Presentations (7) Wang Wang - - Refine Arctic Microwave Radiometer LWP

  9. Microsoft PowerPoint - Town_Hall_Slides_3_5_15_Final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Carlsbad Town Hall Meeting Sponsored by the U.S. Department of Energy and the City of Carlsbad, NM March 5, 2015 www.energy.gov/EM 2 Agenda * Opening Comments - Mayor Dale Janway * Update on CBFO and WIPP activities - Dana Bryson * Recovery Status - Tammy Reynolds * Radiological Contamination - Jim Blankenhorn * Audience Questions * In house * Internet * Closing Comments - Dana Bryson www.energy.gov/EM 3 Update on CBFO and WIPP Activities Dana Bryson, CBFO Deputy Manager www.energy.gov/EM 4 *

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    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Environmental Protection Agency Region 10 Region 10 Hanford Project Office Emerald Laija Hanford Site, 200-UP-1 Remedy Review Board Briefing March 27, 2012 Overview Overview * Background Information Background Information * Site Summary Ri k S * Risk Summary * RAOs and Remediation Goals * Description of Alternatives * Preferred Alternatives Preferred Alternatives * Stakeholder Views Background Information Background Information * 200-ZP-1 OU Record of Decision 200 ZP 1 OU Record of Decision -

  11. Microsoft PowerPoint - XDC_ARM_STM_2007_poster_final.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Ten Years of ARM External Data L. Ma, R. Wagener, L. Gregory, M. Liang, A. Tilp, A. Cialella Brookhaven National Laboratory, Upton, New York G XDC Mission The ARM External Data Center (XDC) acquires, processes, and transmits data to the ARM Archive, that are originally produced or collected by organizations through funding by other agencies or programs external to ARM. The criteria for inclusion are: * Scientifically relevant and complementary to ARM data * Not otherwise archived, or easily

  12. Microsoft PowerPoint - baeARM_5th_final1.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    comparison of arctic cirrus microphysical properties with mid-latitude and tropical cirrus features Kenny Bae 1 , Greg M. McFarquhar 1 , Gong Zhang 1 and Michael R. Poellot 2 1 University of Illinois, Urbana 2 University of North Dakota, Grand Forks Summary * Vertical profiles of crystal shapes observed in arctic cirrus consistent with 3-layer conceptual model of mid- latitude cirrus (nucleation zone of small crystals, growth zone of pristine crystals and sublimation zone with sublimating

  13. Microsoft PowerPoint - poster_08_final.ppt [Compatibility Mode]

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Kenneth Kehoe Randy Peppler Karen Sonntag Justin Monroe Terra Thompson Chris Schwarz Nathan Hiers Kenneth Kehoe, Randy Peppler, Karen Sonntag, Justin Monroe, Terra Thompson, Chris Schwarz, Nathan Hiers, Kenneth Kehoe, Randy Peppler, Karen Sonntag, Justin Monroe, Terra Thompson, Chris Schwarz, Nathan Hiers, St h M ll Ki b l R b ARM D t Q lit Offi CIMMS U i it f Okl h N OK Stephen Mullens Kimberly Rabon; ARM Data Quality Office CIMMS University of Oklahoma Norman OK Stephen Mullens, Kimberly

  14. Microsoft PowerPoint - SS2_8H_NERC_SANS_Final.ppt

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Corporate ICCP Peer Utility Modem Pool I II III IV Sensor Campus Sensors 10 SANS SCADA ... Trivial File Transfer Protocol (TFTP) RFC 783 Sun Microsystems Network File System ...

  15. Microsoft PowerPoint - 15.1130_Jeff Baker_Final Ultra-High Efficiency...

    Energy Saver

    Energy Standard - World-Class Performance at Affordable Cost * Accelerated Delivery at Lower Cost and Risk to Accelerated Delivery at Lower Cost and Risk to the Government -...

  16. Microsoft PowerPoint - Webbers Brief June 2009 Final1.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... Webbers Falls Major Rehab Webbers Falls Major Rehab Project Innovation * Use of a local bridge crane contractor in lieu of major US crane firms. Changing only necessary components. ...

  17. Microsoft PowerPoint - TrafficSafetyBriefing FINAL.pptx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    4 South and Beloit Avenue (Rattlesnake Barricade entrance off Highway 240) - Allows for safer access for the Benton County Sheriff's Office to perform safety enforcement actions...

  18. Microsoft PowerPoint - EM1_EMAB-presentation_Final (without notes...

    Office of Environmental Management (EM)

    ... Accelerator Laboratory 8 M Energy Technology Engineering Center 54 M 12 States, 17 Sites UraniumThorium 69 M Management & Oversight 50 M Infusion of Recovery Act Funds ...

  19. Microsoft PowerPoint - CCS Forum 9-8-2010 final.pptx

    Energy.gov [DOE] (indexed site)

    CCS Forum University of Charleston Charleston, West Virginia 8 September, 2010 America has abundant coal resources Coal will continue to be an important part of America's and the ...

  20. Microsoft PowerPoint - Final Presentation - Olinger.EMAB Presentation Goals 1 and 2 sjo (4)

    Office of Environmental Management (EM)

    Journey to Excellence Goal 1 and 2 Tank Waste and Lifecycle Costs Shirley J. Olinger Shirley J. Olinger Associate Principal Deputy for Associate Principal Deputy for Corporate Operations Corporate Operations Office of Environmental Management Office of Environmental Management U.S. Department of Energy U.S. Department of Energy Agenda Agenda Journey to Excellence Journey to Excellence - - Goal 1: Status Three Major Goal 1: Status Three Major Tank Waste Projects Tank Waste Projects Journey to

  1. Microsoft PowerPoint - Final Presentation - Surash.021611 EMAB Goal 6

    Office of Environmental Management (EM)

    www.em.doe.gov safety performance cleanup closure E M Environmental Management 1 Office of Environmental Management Journey to Excellence - Goal 6 J. E. Surash, P.E. Deputy Assistant Secretary Acquisition and Contract Management U.S. Department of Energy Bill Murphie Site Manager Portsmouth and Paducah Project Office U.S. Department of Energy February 24, 2011 Improve contract and project management with the objective of delivering results on time and within cost * Improve contract management

  2. Microsoft PowerPoint - NTSF 2014 180(c) WG session_final [Compatibility Mode]

    Office of Environmental Management (EM)

    Implementation of Section 180(c) of the Nuclear Waste Policy Act 180(c) Working Group Erica Bickford Office of Nuclear Energy US Department of Energy National Transportation Stakeholders Forum Bloomington, MN May 13-15, 2014 Agenda  Section 180(c) Status and Tabletop Exercise Discussion  Routing Methodology Process  Stakeholder Tool for Assessing Radioactive Transportation (START)  Wrap-up and selection of working group spokesperson for Thursday plenary 2 National Transportation

  3. Microsoft PowerPoint - NTSF 2014 180(c) WG session_final [Compatibilit...

    Office of Environmental Management (EM)

    More economical More user-oriented Easier to maintain and update ESRI ArcGIS recommended as tool development platform 26 National Transportation Stakeholders...

  4. Microsoft PowerPoint - 3rd Qtr 2011 Presentation - Final.ppt

    Office of Legacy Management (LM)

    ... surface water standard is 5.6 gL * Not detected in location 7A Detected analytes copper, lead, nickel, and zinc inadvertently analyzed for total concentration - RFLMA ...

  5. Microsoft PowerPoint - FINAL 2014 Annual Present_RFSC-June 2015...

    Office of Legacy Management (LM)

    ... After ETPTS Reconfiguration Project (continued) 19 Two former treatment cells reinforced for use as batch tanks Enclosure designed and built to house air stripper ETPTS ...

  6. Microsoft PowerPoint - Camper, ORNL-TN CAB-04-2010-final, via...

    Office of Environmental Management (EM)

    ...Assumptions * Difficult to Limit to Waste Classification * Spectrum of Possibilities * Spectrum of Possibilities * Significant Stakeholder Interest 5 Blending of LLW * ...

  7. Microsoft PowerPoint - Gandy-2016 Final DOE Project Results-October 2016.pptx

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    W. Gandy, FASM Nuclear Materials Electric Power Research Institute Davgandy@epri.com DOE Advanced Methods of Manufacturing Workshop October, 2016 Innovative Manufacturing Process for Nuclear Power Plant Components via Powder Metallurgy & Hot Isostatic Pressing Methods 2 © 2016 Electric Power Research Institute, Inc. All rights reserved. Innovative Manufacturing Process for Nuclear Power Plant Components via PM-HIP Objective: Conduct design, manufacturing, and validation studies to assess

  8. Microsoft PowerPoint - Haught Innovative Materials Grid Components FINAL 8 24 15

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    HIGH TEMPERATURE SUPERCONDUCTIVITY A HISTORY OF SUCCESS Materials Innovation for Next Generation T&D Grid Components Oak Ridge National Laboratory August 26-27, 2015 Debbie Haught Office of Electricity Delivery and Energy Reliability Many Applications That Utilize Electricity Can Benefit From Superconductivity Medical Imaging & Diagnostics Magnetoencephalography MRI Magnetocardiography Wireless Communications Filters All-Digital Receivers Scientific Research Large Hadron Collider

  9. Microsoft PowerPoint - Materials Workshop at ORNL - FINAL - refined TP

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Electricity Delivery & Energy Reliability Welcome and Overview Kerry Cheung, PhD Materials Innovation for Next Generation T&D Grid Components August 26 27, 2015 Office of Electricity Delivery and Energy Reliability The Office of Electricity Delivery and Energy Reliability (OE) drives electric grid modernization and resiliency in the energy infrastructure. OE Mission * OE leads the Department of Energy's efforts to ensure a resilient, reliable, and flexible electricity system. * OE

  10. Microsoft PowerPoint - Saudi Arabia 2-22-10 final for distribution.pptx

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Solving the Energy and Climate Challenge Together Secretary Steven Chu International Energy Forum Riyadh, Saudi Arabia 22 February 2010 King Faisal Prize Winners, 1993 The United States of America and Saudi Arabia have a long and deep relationship We are adding a new dimension to our Saudi King Abdul Aziz Al Saud and President Franklin Delano Roosevelt on the USS Quincy 65 years ago dimension to our relationship - as we move to meet shared energy and climate challenges (1) The global economy

  11. Microsoft PowerPoint - FOA Webinar - 1263 October 6 GO FINAL

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... to allow dynamic energy optimization and guide choices of ... sensing and actuation functions of components. * ... * Potential for providing a test-bed facility for ...

  12. Microsoft PowerPoint - Watson Salishan 042412 final.ppt [Compatibility...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    symbols are completely grounded in the mathematical rules of the game * Human Language - Words by themselves have no meaning - Only grounded in human cognition - Words navigate,...

  13. Microsoft PowerPoint - 3Q12 Presentation_FINAL.pptx [Read-Only...

    Office of Legacy Management (LM)

    ... reduced contaminants by 90 percent * Solar Ponds Plume Treatment System Continued ... Concentration in mgL Date Sampled SPLA2 SPLB2 Questions? 22 Cell A contains recirculation ...

  14. Award DE-FG02-04ER52655 Final Technical Report: Interior Point...

    Office of Scientific and Technical Information (OSTI)

    Subject: 97 MATHEMATICS AND COMPUTING Linear programming, linear optimization, quadratic programming, quadratic optimization, entropy-based moment closure, gas dynamics Word Cloud ...

  15. Microsoft PowerPoint - Final 3Q13 presentation_01282014.pptx

    Office of Legacy Management (LM)

    ... 2013 Ecological Monitoring Summary Weed mapping Nest box surveys Prairie dog surveys Revegetation monitoring PMJM mitigation monitoring Wetland ...

  16. Microsoft PowerPoint - P&RA CoP EPA optimization Biggs final 111215

    Office of Environmental Management (EM)

    Implementing Optimization in the Superfund Program __________________________________________________ For the Interagency Performance and Risk Assessment Community of Practice (P&RA CoP) November 12, 2015 Kirby Biggs National Optimization Program Coordinator Technology Integration and Information Branch Office of Superfund Remediation and Technology Integration Washington DC 20460 biggs.kirby@epa.gov . 703-823-3081 . www.cluin.org/optimization (Cleanup Horizon: 2004 - 2033) Source:

  17. Microsoft PowerPoint - P&RA CoP EPA optimization Biggs final...

    Office of Environmental Management (EM)

    ... ARD Amanda VanEpps vanepps.amanda@epa.gov ARD Shahid Mahmud (Mining Sites) ... Mining Optimization and Technical Support * OSRTI continued its implementation of the mine ...

  18. Two dimensional point of use fuel cell : a final LDRD project report.

    SciTech Connect

    Zavadil, Kevin Robert; Hickner, Michael A.; Gross, Matthew L.

    2011-03-01

    The Proliferation Assessment (program area - Things Thin) within the Defense Systems and Assessment Investment Area desires high energy density and long-lived power sources with moderate currents (mA) that can be used as building blocks in platforms for the continuous monitoring of chemical, biological, and radiological agents. Fuel cells can be an optimum choice for a power source because of the high energy densities that are possible with liquid fuels. Additionally, power generation and fuel storage can be decoupled in a fuel cell for independent control of energy and power density for customized, application-driven power solutions. Direct methanol fuel cells (DMFC) are explored as a possible concept to develop into ultrathin or two-dimensional power sources. New developments in nanotechnology, advanced fabrication techniques, and materials science are exploited to create a planar DMFC that could be co-located with electronics in a chip format. Carbon nanotubes and pyrolyzed polymers are used as building block electrodes - porous, mechanically compliant current collectors. Directed assembly methods including surface functionalization and layer-by-layer deposition with polyelectrolytes are used to pattern, build, and add functionality to these electrodes. These same techniques are used to incorporate nanoscale selective electrocatalyst into the carbon electrodes to provide a high density of active electron transfer sites for the methanol oxidation and oxygen reduction reactions. The resulting electrodes are characterized in terms of their physical properties, electrocatalytic function, and selectivity to better understand how processing impacts their performance attributes. The basic function of a membrane electrode assembly is demonstrated for several prototype devices.

  19. Microsoft PowerPoint - Luczak_SSAB_2010 Final 042210.pptx

    Office of Environmental Management (EM)

    ... - Maintain integrity of lifecycle cost estimates a ta teg ty o ecyc e cost est ates - Assign performance measures and milestones to capital projects Categorizing EM ...

  20. Microsoft PowerPoint - Saudi Arabia 2-22-10 final for distribution...

    Energy.gov [DOE] (indexed site)

    IEA: World Energy Outlook 2009 Change in primary oil demand 2007 - 2030 15 20 25 Energy Information ... Oil Prices decisions OPEC production decisions Domestic politics ...

  1. Microsoft PowerPoint - 3rd Quarter 2009 Presentation _final.ppt

    Office of Legacy Management (LM)

    Code of Colorado Regulations 1002 38) (Regulation 31) section 31.44 I.J 6 POC GS03 ... Code of Colorado Regulations 1002 38) (Regulation 31) section 31.44 I.J 7 POC GS03 ...

  2. Microsoft Word - FINAL FOIA June 26 Share Point Request.docx

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    6, 2012 Dorothy Riehle RL/ORP Freedom of Information and Privacy Act Officer P.O. Box 550 Richland, Washington 99352 Telephone: (509) 376-6288 Facsimile: (509) 376-9704 Email: Dorothy_C_Riehle@rl.gov Dear Freedom of Information and Privacy Act Officer(s), Pursuant to the Freedom of Information Act, we are requesting on behalf of Heart of America Northwest, copies of the following public records, including email, electronic documents, and paper records: 1. All records relating to permit review

  3. Microsoft PowerPoint - ARM_STM_08_cmbe_poster_final1.ppt

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    under Contract DE-AC52-07NA27344. CRL-POST-401945 A new ARM product, the Climate Modeling Best Estimate Climate Modeling Best Estimate (CMBE) (CMBE) dataset, was created to serve...

  4. Microsoft PowerPoint - BPA Public Meeting Presentation_9.14 FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    by: * Transmission service and operational coordination enhancements. * Advanced data sharing tools implementation. September 14, 2015 BPA Public Meeting 9 NWPP MC Timeline...

  5. Microsoft PowerPoint - 16.1555_Chad Henderson_Final

    Energy.gov [DOE] (indexed site)

    g Shielded Operations Radiation Detection Materials Science & Technology Chemistry and Processing CSF BSF BSF - Systems Biology CSF - Information Analytics...

  6. Microsoft PowerPoint - UAE Masdar 2-24-10 final for distribution...

    Office of Environmental Management (EM)

    February 2010 Bell Labs solar cell - 1954 First transistor ... Biofuels including imports Petroleum supply Richard ... Index (GDPcapita, education level, health care, etc.) vs. ...

  7. Microsoft PowerPoint - Sweetnam NG Disc Slides - April 7 2010 final.ppt [Compatibility Mode]

    Gasoline and Diesel Fuel Update

    Gas: U.S. Markets in a Global Context 2010 Energy Conference U.S. Energy Information Administration Johns Hopkins University - SAIS p y April 7, 2010 - Washington, DC Natural Gas: U.S. Markets is a Global Context, April 7, 2010 Richard Newell, March 2, 2010 1 Richard Newell, SAIS, December 14, 2009 1 April 7, 2010 Washington, DC Discussion Outline * Setting the context * Demand/supply outlook for 3 regions - United States United States - OECD Europe - China * Evolution of the global gas market -

  8. POINT 2015: ENDF/B-VII.1 Final Temperature Dependent Cross Section Library

    Energy Science and Technology Software Center

    2015-06-01

    Version 00 For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 K and 2100 K, in steps of 300 K (the exception being 293.6 K, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 K is approximatelymore » 1/40 eV, so that 1 eV is approximately 12,000 K. At each temperature the cross sections are tabulated and linearly interpolable in energy.« less

  9. Microsoft PowerPoint - February 7 2013 ORP Agency Update Final

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Energy Office of River Protection Kevin W. Smith Manager Hanford Advisory Board - Agency Update Brief Background - Kevin Smith Manager of Los Alamos Site Office Acting Manager of ...

  10. Microsoft PowerPoint - Final_IIP NOPR PubWorkshop Presentation...

    Energy.gov [DOE] (indexed site)

    Interagency Pre-Application (IIP) Process Notice of Proposed Rulemaking Public Workshop Meghan Conklin, Julie Smith, and Lynn Alexander March 22, 2016 2 Agenda * Introduction * ...

  11. Final Scientific EFNUDAT Workshop

    ScienceCinema

    None

    2016-07-12

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilities  International Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden) Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis Vlachoudis Workshop Assistant: Géraldine Jean

  12. Final Progress Report

    SciTech Connect

    Josef Michl

    2011-10-31

    In this project we have established guidelines for the design on organic chromophores suitable for producing high triplet yields via singlet fission. We have proven their utility by identifying a chromophore of a structural class that had never been examined for singlet fission before, 1,3-diphenylisobenzofuran, and demonstrating in two independent ways that a thin layer of this material produces a triplet yield of 200% within experimental error. We have also designed a second chromophore of a very different type, again of a structural class that had not been examined for singlet fission before, and found that in a thin layer it produces a 70% triplet yield. Finally, we have enhanced the theoretical understanding of the quantum mechanical nature of the singlet fission process.

  13. Final Scientific EFNUDAT Workshop

    ScienceCinema

    None

    2011-10-06

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilitiesInternational Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden)Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis VlachoudisWorkshop Assistant: Graldine Jean

  14. Final Scientific EFNUDAT Workshop

    ScienceCinema

    None

    2011-10-06

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilities  International Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden) Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis Vlachoudis Workshop Assistant: Géraldine Jean

  15. FINAL/ SCIENTIFIC TECHNICAL REPORT

    SciTech Connect

    McDonald, Henry; Singh, Suminderpal

    2006-08-28

    The overall objective of the Chattanooga fuel cell demonstrations project was to develop and demonstrate a prototype 5-kW grid-parallel, solid oxide fuel cell (SOFC) system that co-produces hydrogen, based on Ion Americas technology. The commercial viability of the 5kW SOFC system was tested by transporting, installing and commissioning the SOFC system at the Alternative Energy Laboratory at the University of Tennessee Chattanooga. The system also demonstrated the efficiency and the reliability of the system running on natural gas. This project successfully contributed to the achievement of DOE technology validation milestones from the Technology Validation section of the Hydrogen, Fuel Cells and Infrastructure Technologies Program Multi-Year Research, Development and Demonstration Plan. Results of the project can be found in the final technical report.

  16. IRIS Final Technical Progress Report

    SciTech Connect

    M. D. Carelli

    2003-11-03

    OAK-B135 This NERI project, originally started as the Secure Transportable Autonomous Light Water Reactor (STAR-LW) and currently known as the International Reactor Innovative and Secure (IRIS) project, had the objective of investigating a novel type of water-cooled reactor to satisfy the Generation IV goals: fuel cycle sustainability, enhanced reliability and safety, and improved economics. The research objectives over the three-year (1999-2002) program were as follows: First year: Assess various design alternatives and establish main characteristics of a point design; Second year: Perform feasibility and engineering assessment of the selected design solutions; Third year: Complete reactor design and performance evaluation, including cost assessment These objectives were fully attained and actually they served to launch IRIS as a full fledged project for eventual commercial deployment. The program did not terminate in 2002 at the end of the NERI program, and has just entered in its fifth year. This has been made possible by the IRIS project participants which have grown from the original four member, two-countries team to the current twenty members, nine countries consortium. All the consortium members work under their own funding and it is estimated that the value of their in-kind contributions over the life of the project has been of the order of $30M. Currently, approximately 100 people worldwide are involved in the project. A very important constituency of the IRIS project is the academia: 7 universities from four countries are members of the consortium and five more US universities are associated via parallel NERI programs. To date, 97 students have worked or are working on IRIS; 59 IRIS-related graduate theses have been prepared or are in preparation, and 41 of these students have already graduated with M.S. (33) or Ph.D. (8) degrees. This ''final'' report (final only as far as the NERI program is concerned) summarizes the work performed in the first four

  17. Minimal Doubling and Point Splitting

    SciTech Connect

    Creutz, M.

    2010-06-14

    Minimally-doubled chiral fermions have the unusual property of a single local field creating two fermionic species. Spreading the field over hypercubes allows construction of combinations that isolate specific modes. Combining these fields into bilinears produces meson fields of specific quantum numbers. Minimally-doubled fermion actions present the possibility of fast simulations while maintaining one exact chiral symmetry. They do, however, introduce some peculiar aspects. An explicit breaking of hyper-cubic symmetry allows additional counter-terms to appear in the renormalization. While a single field creates two different species, spreading this field over nearby sites allows isolation of specific states and the construction of physical meson operators. Finally, lattice artifacts break isospin and give two of the three pseudoscalar mesons an additional contribution to their mass. Depending on the sign of this mass splitting, one can either have a traditional Goldstone pseudoscalar meson or a parity breaking Aoki-like phase.

  18. NTSF Spring 2010 Final Agenda

    Energy.gov [DOE]

    Final Agenda for the U.S. Department of Energy's National Transportation Stakeholder Forum taking place in Chicago, Illinois.

  19. Wide-angle point-to-point x-ray imaging with almost arbitrarily...

    Office of Scientific and Technical Information (OSTI)

    Wide-angle point-to-point x-ray imaging with almost arbitrarily large angles of incidence Citation Details In-Document Search Title: Wide-angle point-to-point x-ray imaging with ...

  20. ESPC ENABLE Final Proposal Requirements

    Energy.gov [DOE]

    Document describes the final proposal requirements for consideration by an energy service company (ESCO) for an agency’s Request for Quote/Notice of Opportunity or final proposal. If selected to perform a site investment grade audit, the ESCO will be required to present the findings from the IGA and a project price to the agency in the form of a final proposal.

  1. Oak Ridge Office SharePoint( MicrosoftSHarePointServer) PIA, Information

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Resourses Management Division | Department of Energy SharePoint( MicrosoftSHarePointServer) PIA, Information Resourses Management Division Oak Ridge Office SharePoint( MicrosoftSHarePointServer) PIA, Information Resourses Management Division Oak Ridge Office SharePoint( MicrosoftSHarePointServer) PIA, Information Resourses Management Division Oak Ridge Office SharePoint( MicrosoftSHarePointServer) PIA, Information Resourses Management Division (81.87 KB) More Documents & Publications

  2. VPP Points of Contact | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Points of Contact VPP Points of Contact August 9, 2016 The VPP Points of Contact document provides a current listing of all current DOE VPP participants Points of Contact for both Federal and Contractor positions. VPP Points of Contact - August 9, 2016 (198.94 KB) More Documents & Publications 2009 Voluntary Protection Programs Participants' Association (VPPPA) Presentation: Conducting your Annual VPP Self Assessment 2009 Voluntary Protection Programs Participants' Association (VPPPA)

  3. MIST final report

    SciTech Connect

    Gloudemans, J.R. )

    1991-08-01

    The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock Wilcox Owners Group, the Electric Power Research Institute, and Babcock Wilcox. The unique features of the Babcock Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to addresss the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST program is reported in eleven volumes; Volumes 2 through 8 pertain to groups of Phase 3 tests by type, Volume 9 presents inter-group comparisons. Volume 10 provides comparisons between the RELAP5 MOD2 calculations and MIST observations, and Volume 11 (with addendum) presents the later, Phase 4 tests. This is Volume 1 of the MIST final report, a summary of the entire MIST program. Major topics include: test advisory grop (TAG) issues; facility scaling and design; test matrix; observations; comparisons of RELAP5 calculations to MIST observations; and MIST versus the TAG issues. 11 refs., 29 figs., 9 tabs.

  4. Final Report to DOE

    SciTech Connect

    Ismail Gultepe

    2012-05-15

    This final report summarizes the accomplished goals and provide a list of the publications and presentations made during the project. The goals of the project were accomplished through the various publications submitted to Journals and presentations done at the DOE and international meetings and conferences. The 8 journal articles related to the goals of this project were accepted or submitted. The 23 presentations related to goals of the project were presented at the meetings. There were some minor changes regarding to project goals because of issues encountered during the analysis of the data. For example, a total water probe sensor mounted on the Convair-580 that can be used for defining mixed phase conditions and parameterization, had some problems to estimate magnitude of total water mass, and this resulted in issues providing an accurate parameterization for cloud fraction. Variability related aerosol number concentrations and their composition for direct and indirect effects were studied and published. Results were given to explain aerosol and ice microphysical effects on climate change studies. It is suggested that developed parameterizations should consider the variability in aerosol and ice parameters over the Arctic regions.

  5. Final Technical Report

    SciTech Connect

    Velasco, Mayda

    2013-11-01

    This work is focused on the design and construction of novel beam diagnostic and instrumentation for charged particle accelerators required for the next generation of linear colliders. Our main interest is in non-invasive techniques. The Northwestern group of Velasco has been a member of the CLIC Test Facility 3 (CTF3) collaboration since 2003, and the beam instrumentation work is developed mostly at this facility1. This 4 kW electron beam facility has a 25-170 MeV electron LINAC. CTF3 performed a set of dedicated measurements to finalize the development of our RF-Pickup bunch length detectors. The RF-pickup based on mixers was fully commissioned in 2009 and the RF-pickup based on diodes was finished in time for the 2010-11 data taking. The analysis of all the data taken in by the summer of 2010 was finish in time and presented at the main conference of the year, LINAC 2010 in Japan.

  6. Final Technical Report

    SciTech Connect

    Alexander Fridman

    2005-06-01

    This DOE project DE-FC36-04GO14052 ''Plasma Pilot Plant Test for Treating VOC Emissions from Wood Products Plants'' was conducted by Drexel University in cooperation with Georgia-Pacific (G-P) and Kurchatov Institute (KI). The objective of this project was to test the Plasma Pilot Plant capabilities in wood industry. The final goal of the project was to replace the current state-of-the-art, regenerative thermal oxidation (RTO) technology by Low-Temperature Plasma Technology (LTPT) in paper and wood industry for Volatile Organic Components (VOC) destruction in High Volume Low Concentration (HVLC) vent emissions. MetPro Corporation joined the team as an industrial partner from the environmental control business and a potential leader for commercialization. Concurrent Technology Corporation (CTC) has a separate contract with DOE for this technology evaluation. They prepared questionnaires for comparison of this technology and RTO, and made this comparison. These data are presented in this report along with the description of the technology itself. Experiments with the pilot plant were performed with average plasma power up to 3.6 kW. Different design of the laboratory and pilot plant pulsed coronas, as well as different analytical methods revealed many new peculiarities of the VOC abatement process. The work reported herein describes the experimental results for the VOCs removal efficiency with respect to energy consumption, residence time, water effect and initial concentration.

  7. Tiger LDRD final report

    SciTech Connect

    Steich, D J; Brugger, S T; Kallman, J S; White, D A

    2000-02-01

    This final report describes our efforts on the Three-Dimensional Massively Parallel CEM Technologies LDRD project (97-ERD-009). Significant need exists for more advanced time domain computational electromagnetics modeling. Bookkeeping details and modifying inflexible software constitute a vast majority of the effort required to address such needs. The required effort escalates rapidly as problem complexity increases. For example, hybrid meshes requiring hybrid numerics on massively parallel platforms (MPPs). This project attempts to alleviate the above limitations by investigating flexible abstractions for these numerical algorithms on MPPs using object-oriented methods, providing a programming environment insulating physics from bookkeeping. The three major design iterations during the project, known as TIGER-I to TIGER-III, are discussed. Each version of TIGER is briefly discussed along with lessons learned during the development and implementation. An Application Programming Interface (API) of the object-oriented interface for Tiger-III is included in three appendices. The three appendices contain the Utilities, Entity-Attribute, and Mesh libraries developed during the project. The API libraries represent a snapshot of our latest attempt at insulated the physics from the bookkeeping.

  8. Final Technical Report

    SciTech Connect

    Alexander Pigarov

    2012-06-05

    This is the final report for the Research Grant DE-FG02-08ER54989 'Edge Plasma Simulations in NSTX and CTF: Synergy of Lithium Coating, Non-Diffusive Anomalous Transport and Drifts'. The UCSD group including: A.Yu. Pigarov (PI), S.I. Krasheninnikov and R.D. Smirnov, was working on modeling of the impact of lithium coatings on edge plasma parameters in NSTX with the multi-species multi-fluid code UEDGE. The work was conducted in the following main areas: (i) improvements of UEDGE model for plasma-lithium interactions, (ii) understanding the physics of low-recycling divertor regime in NSTX caused by lithium pumping, (iii) study of synergistic effects with lithium coatings and non-diffusive ballooning-like cross-field transport, (iv) simulation of experimental multi-diagnostic data on edge plasma with lithium pumping in NSTX via self-consistent modeling of D-Li-C plasma with UEDGE, and (v) working-gas balance analysis. The accomplishments in these areas are given in the corresponding subsections in Section 2. Publications and presentations made under the Grant are listed in Section 3.

  9. Title XVII Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule Title XVII Final Rule Title XVII Final Rule (107.56 KB) More Documents & Publications Final Rule (December 4, 2009) Notice of Proposed Rulemaking (August 6, 2009) Final Rule (October 23, 2007)

  10. Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility

    SciTech Connect

    Douglas M. Gerstner

    2009-05-01

    The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) conditions to support clad corrosion and related reactor material testing. Further it will accommodate power ramping tests of candidate high burn-up fuels and fuel pins/rods for the commercial BWR utilities. The BWTL will be much like the pressurized water loops already in service in 5 of the 9 “flux traps” (region of enhanced neutron flux) in the ATR. The loop coolant will be isolated from the primary coolant system so that the loop’s temperature, pressure, flow rate, and water chemistry can be independently controlled. This paper presents the proposed general design of the in-core and auxiliary BWTL systems; the preliminary results of the neutronics and thermal hydraulics analyses; and the preliminary hazard analysis for safe normal and transient BWTL and ATR operation.

  11. Binary module test. Final report

    SciTech Connect

    Schilling, J.R.; Colley, T.C.; Pundyk, J.

    1980-12-01

    The objective of this project was to design and test a binary loop module representative of and scaleable to commercial size units. The design was based on state-of-the-art heat exchanger technology, and the purpose of the tests was to confirm performance of a supercritical boiling cycle using isobutane and a mixture of isobutane and isopentane as the secondary working fluid. The module was designed as one percent of a 50 MW unit. It was installed at Magma Power's East Mesa geothermal field and tested over a period of approximately 4 months. Most of the test runs were with isobutane but some data were collected for hydrocarbon mixtures. The results of the field tests are reported. In general these results indicate reasonably good heat balances and agreement with overall heat transfer coefficients calculated by current stream analysis methods and available fluid property data; however, measured pressure drops across the heat exchangers were 20 percent higher than estimated. System operation was stable under all conditions tested.

  12. Decision Point 1 Topical Report

    SciTech Connect

    Yablonsky, Al; Barsoumian, Shant; Legere, David

    2013-05-01

    This Topical Report addresses accomplishments achieved during Phase 2a of the SkyMine® Carbon Mineralization Pilot Project. The primary objectives of this project are to design, construct, and operate a system to capture CO2 from a slipstream of flue gas from a commercial coal-fired cement kiln, convert that CO2 to products having commercial value (i.e., beneficial use), show the economic viability of the CO2 capture and conversion process, and thereby advance the technology to the point of readiness for commercial scale demonstration and proliferation. The overall process is carbon negative, resulting in mineralization of CO2 that would otherwise be released into the atmosphere. The project will also substantiate market opportunities for the technology by sales of chemicals into existing markets, and identify opportunities to improve technology performance and reduce costs at the commercial scale. The project is being conducted in two phases. The primary objectives of Phase 1 were to elaborate proven SkyMine® process chemistry to commercial pilot-scale operation and complete the preliminary design for the pilot plant to be built and operated in Phase 2, complete a NEPA evaluation, and develop a comprehensive carbon life cycle analysis. The objective of the current Phase (2a) is to complete the detailed design of the pilot plant to be built in Phase 2b.

  13. Microsoft Word - Final 1703 NOPR _supercedes Final rule_ _2_.doc

    Energy Saver

    Energy 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final (219.14 KB) More Documents & Publications FY 2012 Annual Progress Report for Energy Storage R&D Hybrid Electric Systems Revolution Now: The Future Arrives for Five Clean Energy Technologies-2015 Update

    5 Annual Report I. Basic Information Regarding Report. A. Abel Lopez, Director FOIA/Privacy Act Group, MA-74 Office of the

  14. MTX final report

    SciTech Connect

    Hooper, E.B.; Allen, S.L.; Brown, M.D.; Byers, J.A.; Casper, T.A.; Cohen, B.I.; Cohen, R.H.; Fenstermacher, M.E.; Foote, J.H.; Hoshino, K.

    1994-01-01

    The MTX experiment was proposed in 1986 to apply high frequency microwaves generated by a free-electron laser (FEL) to electron cyclotron resonance heating (ECRH) in a high field, high density tokamak. As the absorption of microwaves at the electron cyclotron resonance requires high frequencies, the opportunity of applying a free-electron laser has appeal as the device is not limited to frequencies in the microwave or long millimeter wavelength regions, in contrast to many other sources. In addition, the FEL is inherently a high power source of microwaves, which would permit single units of 10 MW or more, optimum for reactors. Finally, it was recognized early in the study of the application of the FEL based on the induction linear accelerator, that the nonlinear effects associated with the intense pulses of microwaves naturally generated would offer several unique opportunities to apply ECRH to current drive, MHD control, and other plasma effects. It was consequently decided to adapt the induction accelerator based FEL to heating and controlling the tokamak, and to conduct experiments on the associated physics. To this end, the Alcator C tokamak was moved from the Massachusetts Institute of Technology (MIT) to the Lawrence Livermore National Laboratory where it was installed in Building 431 and operated from March, 1989, until the conclusion of the experiment in October, 1992. The FEL, based on the ETA-11 accelerator and IMP wiggler was brought into operation by the LLNL Electron Beam Group and power injected into the tokamak during an experimental run in the Fall, 1989. Following an upgrade by the MTX group, a second experimental run was made lasting from the Winter, 1992 through the end of the experiment. Significant contributions to the ECRH experiments were made by the Japan Atomic Energy Research Institute (JAERI).

  15. Seismic Analysis of Morrow Point Dam

    SciTech Connect

    Noble, C R

    2002-04-01

    The main objective of this study is to perform nonlinear dynamic earthquake time history analyses on Morrow Point Dam, which is located 263 km southwest of Denver, Colorado. This project poses many significant technical challenges, one of which is to model the entire Morrow Point Dam/Foundation Rock/Reservoir system which includes accurate geology topography. In addition, the computational model must be initialized to represent the existing dead loads on the structure and the stress field caused by the dead loads. To achieve the correct dead load stress field due to gravity and hydrostatic load, the computer model must account for the manner in which the dams were constructed. Construction of a dam finite element model with the correct as-built geometry of the dam structure and simply ''turning on'' gravity in the computer model will generally lead to an incorrect initial stress field in the structure. The sequence of segmented lifts typical of dam construction has a significant impact on the static stress fields induced in the dam. In addition, the dam model must also account for the interaction between the adjacent dam segments across the dam contraction joints. As a result of these challenges, it was determined that a significant amount of code development was required in order to accurately simulate the motion of the dam structure. Modifications to the existing slide surfaces are needed to allow for appropriate modeling of the shear keys across the contraction joints. Furthermore, a model for hydrodynamic interaction was also implemented into NIKE3D and DYNA3D for fluid representation in the 3D dam system finite element model. Finally, the modeling of the 3D dam system results in a very large computational model, which makes it difficult to perform a static initialization using an implicit code. Traditionally, for these large models, the model has been initialized over a long time scale using an explicit code. However, recent advancements have made it possible

  16. Final Technical Report

    SciTech Connect

    Juan Camilo Serrano

    2011-12-16

    New and novel material and process technologies applied in wind blade designs and production are critical to increasing the competitiveness of wind power generation against traditional sources of energy. In this project, through collaboration between PPG Industries and MAG Industrial Automation Systems, the potential of using automated manufacturing for the production of fiber glass composite wind blades was evaluated from both technical and economic points of view. Further, it was demonstrated that by modifying the standard blade raw material forms through the use of cost effective pre-impregnated rovings coupled with using an automated fiber placement machine to lay up the parts, it is possible to produce state of the art composite laminates with significantly improved mechanical performance and with higher processing rates than standard blade production technology allows for today, thereby lowering the cost of energy over turbine blades made using traditional processes and materials. In conformity with the scope of work of the submitted proposal, the project team completed each task and documented and reported its findings on the appropriate quarterly report submitted to the DOE project team. The activities and this report are divided into 5 subtasks: (1) Material Investigation - Reviews traditional materials and key specifications and testing methods; (2) Manufacturing and Automation - Identifies new candidate material forms and automated layup processes; (3) Process Development - Performs trials of candidate materials and processes; (4) Predictive Analysis - Assesses impact of new material forms and automated processes on a model blade design; and (5) Feasibility Assessment - Compares traditional manufacturing processes and materials to new candidate material forms and automated processes.

  17. Effects of Point Defects and Impurities on Kinetics in NaAlH4 | Department

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Energy Point Defects and Impurities on Kinetics in NaAlH4 Effects of Point Defects and Impurities on Kinetics in NaAlH4 A presentation showing that point defects play an important role in the kinetics of NaAlH4 including vacancies and interstitials consistent with observed effects of Ti. effects_of_point_defects.pdf (503.7 KB) More Documents & Publications Catalytic Effect of Ti for Hydrogen Cycling in NaAlH4 FTA - SunLine Transit Agency - Final Report Proceedings of the 1998 U.S. DOE

  18. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    The U.S. Environmental Protection Agency (EPA) is currently working to submit permit ... into Hanford's current permit. The EPA Consent Agreement and Final Order (CAFO) ...

  19. LIVE_NSB_final.wmv

    ScienceCinema

    None

    2016-07-12

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  20. Microsoft Word - Abengoa Final EA

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    683 FINAL ENVIRONMENTAL ASSESSMENT FOR DEPARTMENT OF ENERGY LOAN GUARANTEE TO ABENGOA SOLAR INC. FOR THE SOLANA THERMAL ELECTRIC POWER PROJECT NEAR GILA BEND, ARIZONA U.S. ...

  1. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    upcoming action and follow-up items. * Attachment 5: Tri-Party Agreement Agency Fiscal Year 2015 Work Plan- RAP-focused Topics1: Transcribed flipcharts Final Meeting...

  2. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... administrative controls, worker training, industrial hygiene procedures, occupational medicine programs and oversight 2009-present" Final Meeting Summary Page 4 Health, Safety ...

  3. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ADVISORY BOARD PUBLIC INVOLVEMENT AND COMMUNICATION COMMITTEE June 7, 2016 Richland, WA ... Final Meeting Summary Page 2 Public Involvement and Communication Committee June 7, 2016 ...

  4. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Committee September 4, 2013 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATION COMMITTEE September 4, 2013 Kennewick, WA Topics in this Meeting Summary ...

  5. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ADVISORY BOARD PUBLIC INVOLVEMENT AND COMMUNICATION COMMITTEE April 12, 2016 Richland, WA ... Final Meeting Summary Page 2 Public Involvement and Communication Committee April 12, 2016 ...

  6. EA-1637: Final Environmental Assessment

    Office of Energy Efficiency and Renewable Energy (EERE)

    10 CFR 431 Energy Conservation Program for Commerical and Industrial Equipment: Packaged Terminal Air Conditioner and Packaged Terminal Heat Pump Energy Conservation Standards; Final Rule

  7. Points of Contact and Privacy Act Advisory

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Points of Contact Points of Contact and Privacy Act Advisory If you are trying to contact an agency other than the Department of Energy, use the web address: http:...

  8. CenterPoint Comments | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    CenterPoint Comments CenterPoint Comments CenterPoint Comments on the Smart Grid RFI: Addressing Policy and Logistical Challenges CenterPoint Comments (5.21 MB) More Documents & Publications City Utilities of Springfield Missouri Comments on Smart Grid RFI: Addressing Policy and Logistical Challenges Dairyland Power Cooperative Comments on Smart Grid RFI: Addressing Policy and Logistical Challenges Comments of North American Electric Reliability Corporation (NERC) to DOE Smart Grid RFI:

  9. Beryllium Program Points of Contact - Hanford Site

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Program Points of Contact About Us Beryllium Program Beryllium Program Points of Contact Beryllium Facilities & Areas Beryllium Program Information Hanford CBDPP Committee Beryllium FAQs Beryllium Related Links Hanford Beryllium Awareness Group (BAG) Program Performance Assessments Beryllium Program Feedback Beryllium Health Advocates Primary Contractors/Employers Medical Testing and Surveillance Facilities General Resources Beryllium Program Points of Contact Email Email Page | Print Print

  10. Microsoft Word - 2014PHYSOR_Powers_FCM_final rev2.docx

    Office of Scientific and Technical Information (OSTI)

    ... could be pursued for boiling water reactor (BWR) cores. ... Analysis work can rely on sound engineering judgment in the ... Fuel for the Deep Burn Management of ...

  11. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    language, as it denotes that zero contamination should remain. R. Rather than use the words "meet drinking water standards," the advice point could state that contaminants...

  12. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... C: The notes include specific examples where there are problems with clarity. The ... The following text captures the key discussion points: C: The Hanford emergency planning ...

  13. SPR Acquisition Procedures- Final Rulemaking

    Energy.gov [DOE]

    Point of Contact:  Thomas McGarry, Director of Operatons and Readiness, Strategic Petroleum Reserve,  (202) 586-8197

  14. Final Technical Report

    SciTech Connect

    Stenzel, Reiner; Urrutia, J. Manuel

    2009-09-08

    emissions are only observed in whistler spheromaks and FRCs but not in mirrors or asymmetric configurations lacking magnetic null lines. The collisionless electron energization in a toroidal null line usually produces non-Maxwellian distributions. Off the null axis electrons gain more perpendicular than parallel energy. Distributions with T{sub {perpendicular}} > T{sub {parallel}} lead to whistler instabilities which have been observed. A whistler spheromak is a source of high-frequency whistler emissions. These are usually small amplitude whistlers propagating in a complicated background magnetic field. The waves are emitted from a moving source. High frequency whistlers propagate faster than the spheromak, thus partly move ahead of it and partly in the reverse direction. In test wave experiments wave growth opposite to the direction of the hot electron flow has been observed, confirming that Doppler-shifted cyclotron resonance instabilities account for the emission process. Propagating whistler mirrors produce no significant instabilities except when they interact with other fields which exhibit null lines. For example, a whistler mirror has been launched against a stationary FRC, resulting in strong FRC heating and whistler instabilities. In the whistler mirror configuration the antenna near-zone field produces a toroidal null line outside the coil which can also become a source for whistler emissions. Finally, nonlinear EMHD research has been extended to initially unmagnetized plasmas where a new nonlinear skin depth has been discovered. When a small-amplitude oscillating magnetic field is applied to a plasma the field penetration is governed by the skin depth, collisional or collisionless depending on frequency, collision frequency and plasma frequency. However, when the magnetic field increases the electrons become magnetized and the field penetration occurs in the whistler mode if the cyclotron frequency exceeds the oscillating frequency. This phenomenon has been

  15. Final Technical Report

    SciTech Connect

    Mattes, M. Jules

    2005-06-10

    effective than the LEE emitters, probably because of the much shorter half-life of the available {alpha}-particle emitter (less than 1 hr). Of the LEE emitters tested, {sup 67}Ga was considerably more potent than {sup 111}In, per decay, but {sup 111}In has major advantages due to the fact that better chelators are available, and the purity of the commercial radionuclide is much higher. Both were better than {sup 125}I because of their more suitable half-lives. Therefore, 111In remains the optimal LEE emitter at the current time, although it is useful to continue to consider the use of other radionuclides. In fact, we have emphasized that there are many LEE-emitting radionuclides that would be much more potent than {sup 111}In; these are not available at all, or not available carrier-free, or suitable conjugation methods have not been developed. Our results indicate that the development of such radionuclides, at the DOE reactors or at other facilities, would be likely to have substantial medical applications. In therapy, we have thus far been able to treat micrometastatic tumors (injected i.v.) and only small s.c. tumors, barely visible by eye, thin disks with a diameter of 1-2 mm. Because some of the tumors used grow slowly, we are able to obtain effective therapy as late as one month after tumor injection. While this is a limitation, perhaps due to the short tissue path-length of the LEEs, it does not mean that they are not clinically useful: many patients have microscope disease, and such tumors are probably the most difficult, and important, to treat. If we can effectively eliminate such micrometastases, there is a prospect of curing patients in whom the tumor would otherwise recur. Also, it is still possible that we could use this approach to treat larger tumor, if multiple doses are administered. It should also be pointed out that my laboratory is virtually the only one doing experiments of this type. Previous theoretical calculations had suggested that it should be

  16. Critical point analysis of phase envelope diagram

    SciTech Connect

    Soetikno, Darmadi; Siagian, Ucok W. R.; Kusdiantara, Rudy Puspita, Dila Sidarto, Kuntjoro A. Soewono, Edy; Gunawan, Agus Y.

    2014-03-24

    Phase diagram or phase envelope is a relation between temperature and pressure that shows the condition of equilibria between the different phases of chemical compounds, mixture of compounds, and solutions. Phase diagram is an important issue in chemical thermodynamics and hydrocarbon reservoir. It is very useful for process simulation, hydrocarbon reactor design, and petroleum engineering studies. It is constructed from the bubble line, dew line, and critical point. Bubble line and dew line are composed of bubble points and dew points, respectively. Bubble point is the first point at which the gas is formed when a liquid is heated. Meanwhile, dew point is the first point where the liquid is formed when the gas is cooled. Critical point is the point where all of the properties of gases and liquids are equal, such as temperature, pressure, amount of substance, and others. Critical point is very useful in fuel processing and dissolution of certain chemicals. Here in this paper, we will show the critical point analytically. Then, it will be compared with numerical calculations of Peng-Robinson equation by using Newton-Raphson method. As case studies, several hydrocarbon mixtures are simulated using by Matlab.

  17. Function point count adjustment by means of scaling touched function points

    SciTech Connect

    Bell, M.

    1997-11-01

    This report contains viewgraphs on the use of scaling touched function points to adjust function point analysis in determine the usefullness, productivity, and quality of software.

  18. Free-formed insulated concentrating solar collector. Final report

    SciTech Connect

    Goodwin, G.

    1981-01-01

    A free-formed, insulated solar concentrating-collector was designed, built, and tested. The design utilizes new concepts to achieve simplicity, low cost, high efficiency, and long service life. Three concepts were utilized to meet these goals: First, the concentrating reflector is free-formed by hand from a thin steel sheet. Second, a transparent cover is placed over the concentrator and insulation is placed on the back and ends reduce heat losses and protect the reflecting surface from attack by rain and dust. Third, a highly-reflective aluminum film, protected by bonding between two thin sheets of uv stabilized polyester, is fastened to the steel substrate by peelable adhesive. The material cost of the unit without sun seeking electronics and drive motor is about $6.75 per square foot of sun capturing area. Sun following equipment adds to the cost, however, in units of about 100 square feet sun following equipment contributes about $2.00 per square foot. Labor costs are estimated to be approximately $3.00 per square foot for a $5.00 per hour labor rate for a trained crew. On a do-it-yourself basis a 100 square foot unit would cost about $875. Tests of the prototype collector performed by a certified solar test laboratory were made and the results compared with similar tests of a commercial unit. These tests indicate that the efficiency of the prototype is higher than the commercial unit at outlet temperatures below 160/sup 0/F and comparable with the commercial unit at the boiling point of water.

  19. Boiling Water Reactor Fuel Behavior Under Reactivity-Initiated-Accident Conditions at Burnup of 41 to 45 GWd/tonne U

    SciTech Connect

    Nakamura, Takehiko; Yoshinaga, Makio; Takahashi, Masato; Okonogi, Kazunari; Ishijima, Kiyomi

    2000-02-15

    Boiling water reactor (BWR) fuel at burnup of 41 to 45 GWd/tonne U was pulse irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate fuel behavior under cold startup reactivity-initiated-accident conditions. Current Japanese BWR fuel, 8 x 8BJ type (Step I), from Fukushima-Daiichi Unit 3 was refabricated into short segments, and the test rods were promptly subjected to thermal energy from 293 to 607 J/g (70 to 145 cal/g) within {approx}20 ms. The fuel cladding was ductile enough to survive the prompt deformation due to pellet cladding mechanical interaction, while the plastic hoop strain reached 1.5% at the peak location. Transient fission gas release by the pulse irradiation varied from 3.1 to 8.2%, depending on the peak fuel enthalpy and the steady-state operation conditions.

  20. EIS-0349: EPA Notice of Availability of the Final Environmental Impact

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Statement | Department of Energy EPA Notice of Availability of the Final Environmental Impact Statement EIS-0349: EPA Notice of Availability of the Final Environmental Impact Statement BP Cherry Point Cogeneration Project, Whatcom County, Washington BP West Coast Products, LLC proposes to construct and operate a 720-megawatt, natural-gas-fired, combined-cycle cogeneration facility on land adjacent to its BP Cherry Point Refinery. This EIS assesses the existing natural and built environment,

  1. Neutronic evaluation of a non-fertile fuel for the disposition of weapons-grade plutonium in a boiling water reactor

    SciTech Connect

    Sterbentz, J.W.

    1994-10-01

    A new non-fertile, weapons-grade plutonium oxide fuel concept is developed and evaluated for deep burn applications in a boiling water reactor environment using the General Electric 8x8 Advanced Boiling Water Reactor (ABWR) fuel assembly dimensions and pitch. Detailed infinite lattice fuel burnup results and neutronic performance characteristics are given and although preliminary in nature, clearly demonstrate the fuel`s potential as an effective means to expedite the disposition of plutonium in existing light water reactors. The new non-fertile fuel concept is an all oxide composition containing plutonia, zirconia, calcia, and erbia having the following design weight percentages: 8.3; 80.4; 9.7; and 1.6. This fuel composition in an infinite fuel lattice operating at linear heat generation rates of 6.0 or 12.0 kW/ft per rod can remain critical for up to 1,200 and 600 Effective Full Power Days (EFPD), respectively, and achieve a burnup of 7.45 {times} 10{sup 20} f/cc. These burnups correspond to a 71--73% total plutonium isotope destruction and a 91--94% destruction of the {sup 239}Pu isotope for the 0--40% moderator steam void condition. Total plutonium destruction greater than 73% is possible with a fuel management scheme that allows subcritical fuel assemblies to be driven by adjacent high reactivity assemblies. The fuel exhibits very favorable neutron characteristics from beginning-of-life (BOL) to end-of-life (EOL). Prompt fuel Doppler coefficient of reactivity are negative, with values ranging between {minus}0.4 to {minus}2.0 pcm/K over the temperature range of 900 to 2,200 K. The ABWR fuel lattice remains in an undermoderated condition for both hot operational and cold startup conditions over the entire fuel burnup lifetime.

  2. An experimental study on sub-cooled flow boiling CHF of R134a at low pressure condition with atmospheric pressure (AP) plasma assisted surface modification

    SciTech Connect

    Kim, Seung Jun; Zou, Ling; Jones, Barclay G.

    2015-02-01

    In this study, sub-cooled flow boiling critical heat flux tests at low pressure were conducted in a rectangular flow channel with one uniformly heated surface, using simulant fluid R-134a as coolant. The experiments were conducted under the following conditions: (1) inlet pressure (P) of 400-800 kPa, (2) mass flux (G) of 124-248 kg/m2s, (3) inlet sub-cooling enthalpy (ΔHi) of 12~ 26 kJ/kg. Parametric trends of macroscopic system parameters (G, P, Hi) were examined by changing inlet conditions. Those trends were found to be generally consistent with previous understandings of CHF behavior at low pressure condition (i.e. reduced pressure less than 0.2). A fluid-to-fluid scaling model was utilized to convert the test data obtained with the simulant fluid (R-134a) into the prototypical fluid (water). The comparison between the converted CHF of equivalent water and CHF look-up table with same operation conditions were conducted, which showed good agreement. Furthermore, the effect of surface wettability on CHF was also investigated by applying atmospheric pressure plasma (AP-Plasma) treatment to modify the surface characteristic. With AP-Plasma treatment, the change of microscopic surface characteristic was measured in terms of static contact angle. The static contact angle was reduced from 80° on original non-treated surface to 15° on treated surface. An enhancement of 18% on CHF values under flow boiling conditions were observed on AP-Plasma treated surfaces compared to those on non-treated heating surfaces.

  3. Final ECR 2008 Report | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final ECR 2008 Report Final ECR 2008 Report Final ECR 2008 Report Environmental Conflict Resolution Third Annual Report January 2009 (224.55 KB) More Documents & Publications Environmental Conflict Resolution 2009 ECR FINAL REPORT 2010 test

  4. Microsoft PowerPoint - LANL_colloqium

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    dominate the universe in terms of number of particles ... Evidence for Oscillations: Search for -> e Alabama, ... with a final state muon enter the e background ...

  5. EIS-0481: Final Programmatic Environmental Impact Statement ...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    1: Final Programmatic Environmental Impact Statement EIS-0481: Final Programmatic Environmental Impact Statement Engineered High Energy Crop Programs Programmatic Environmental ...

  6. Hawaii Clean Energy Final PEIS

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    A 1 2 Public Notices 3 Notices about the Draft Programmatic EIS Appendix A Hawai i Clean Energy Final PEIS A-1 September 2015 DOE/EIS-0459 The following Notice of Availability appeared in the Federal Register on April 18, 2014. Appendix A Hawai i Clean Energy Final PEIS A-2 September 2015 DOE/EIS-0459 Appendix A Hawai i Clean Energy Final PEIS A-3 September 2015 DOE/EIS-0459 DOE-Hawaii placed the following advertisement in The Garden Island on May 5 and 9, 2014. Appendix A Hawai i Clean Energy

  7. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    June 18, 2015 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD HEALTH, SAFETY, AND ENVIRONMENTAL PROTECTION COMMITTEE June 18, 2015 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Tank Farm Vapors Advice Response ............................................................................................................ 1 Effectiveness of

  8. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    March 15, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE March 15, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Environmental Restoration and Disposal Facility Vertical Expansion ......................................................... 2 Committee Business

  9. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    April 26, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE April 26, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Update on Plutonium Finishing Plant ........................................................................................................... 1 Leadership Workshop Preparation, FY 2017

  10. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    August 9, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE August 9, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 PFP Milestone Change .................................................................................................................................. 2 100 D/H Proposed Plan

  11. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    August 10, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE August 10, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Vapors Monitoring Detection Update (Joint w/HSEP) ................................................................................. 2 Tank

  12. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    4, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE October 4, 2016 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 2 PFP Update ................................................................................................................................................... 2 Groundwater Year-End Update

  13. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    October 5, 2016 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE October 5, 2016 Richland, WA Topics in this Meeting Summary Hanford Site Tour (Joint w/HSEP) ............................................................................................................... 2 Opening ......................................................................................................................................................... 2 Tank Farm Update

  14. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Dennis Faulk, U.S. Environmental Protection Agency (EPA), added that the auguring would ... Area will be remediated by March 2016. EPA and Ecology are working to conduct final ...

  15. Final Report: Axion "Roadmap" Workshop

    SciTech Connect

    Rosenberg, Leslie J

    2013-03-19

    Final report for "Vistas in Axion Physics: A Roadmap for Theoretical and Experimental Axion Physics through 2025", which was held at the University of Washington, INT, from April 23 - 26, 2012.

  16. CenterPoint Energy New Homes Program

    Energy.gov [DOE]

    Note: This program is only available to electric customers in CenterPoint Energy's service territory (greater Houston area, Texas). 

  17. Point of Compliance | Department of Energy

    Office of Environmental Management (EM)

    Generic Technical Issue Discussion on Point of Compliance More Documents & Publications Long-Term Grout Performance Concentration Averaging Sensitivity and Uncertainty Analysis...

  18. End Point Implementation Examples | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    PDF icon End Point Implementation Examples More Documents & Publications Post-Deactivation Surveillance and Maintenance Planning Project Management Plan Examples 1 - 80 ...

  19. New York Nuclear Profile - Indian Point

    Energy Information Administration (EIA) (indexed site)

    Indian Point" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" ...

  20. Building Green in Greensburg: Prairie Pointe Townhomes

    Energy.gov [DOE]

    This poster highlights energy efficiency, renewable energy, and sustainable features of the high-performing Prairie Pointe Townhomes in Greensburg, Kansas.

  1. West Point Utility System | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Utility System Jump to: navigation, search Name: West Point Utility System Place: Iowa Phone Number: (319) 837-6313 Website: www.westpointiowa.comwp-utili Facebook: https:...

  2. GreatPoint Energy | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: GreatPoint Energy Address: 222 Third Street Place: Cambridge, Massachusetts Zip: 02142 Region: Greater Boston Area Sector: Biomass Product:...

  3. Point380 LLC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Zip: 80302 Sector: Carbon Product: Point380 provides carbon consulting and resource management solutions to a broad range of clients seeking energy related risk analysis and...

  4. Wolf Point Substation, Roosevelt County, Montana

    SciTech Connect

    Not Available

    1991-05-01

    The Western Area Power Administration (Western), an agency of the United States Department of Energy, is proposing to construct the 115-kV Wolf Point Substation near Wolf Point in Roosevelt County, Montana (Figure 1). As part of the construction project, Western's existing Wolf Point Substation would be taken out of service. The existing 115-kV Wolf Point Substation is located approximately 3 miles west of Wolf Point, Montana (Figure 2). The substation was constructed in 1949. The existing Wolf Point Substation serves as a Switching Station'' for the 115-kV transmission in the region. The need for substation improvements is based on operational and reliability issues. For this environmental assessment (EA), the environmental review of the proposed project took into account the removal of the old Wolf Point Substation, rerouting of the five Western lines and four lines from the Cooperatives and Montana-Dakota Utilities Company, and the new road into the proposed substation. Reference to the new proposed Wolf Point Substation in the EA includes these facilities as well as the old substation site. The environmental review looked at the impacts to all resource areas in the Wolf Point area. 7 refs., 6 figs.

  5. Starting Points | National Nuclear Security Administration |...

    National Nuclear Security Administration (NNSA)

    Starting Points Kansas City Plant Related Web Pages Summary Kansas City Plant Home Page Kansas City Plant Contracts DOE Directives NNSA Policy System Kansas City Field Office ...

  6. VPP Points of Contact web version 07092015

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Updated 792015 VPP POINTS OF CONTACT Organization DOE POC Contractor DOE Federal POC Advanced Technologies and Laboratories International, Inc. (ATL)222-S Laboratory Analytical ...

  7. A RECIPE FOR LINEAR COLLIDER FINAL FOCUS SYSTEM DESIGN

    SciTech Connect

    Seryi, Andrei

    2003-05-27

    The design of Final Focus systems for linear colliders is challenging because of the large demagnifications needed to produce nanometer-sized beams at the interaction point. Simple first- and second-order matrix matching have proven insufficient for this task, and minimization of third- and higher-order aberrations is essential. An appropriate strategy is required for the latter to be successful. A recipe for Final Focus design, and a set of computational tools used to implement this approach, are described herein. An example of the use of this procedure is given.

  8. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... and closure efforts, and the residual waste that remains inside of emptied tanks. ... points: There are 149 single-shell tanks (SST) at the Hanford Site, the oldest of ...

  9. Final Meeting Summary Page 1

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    ... so DOE-ORP may face some trade- offs when determining where the budget should be spent. ... The first step is to obtain justification from DOE-Headquarters, at which point the ...

  10. Three-point spherical mirror mount

    DOEpatents

    Cutburth, R.W.

    1984-01-23

    A three-point spherical mirror mount for use with lasers is disclosed. The improved mirror mount is adapted to provide a pivot ring having an outer surface with at least three spaced apart mating points to engage an inner spherical surface of a support housing.

  11. Order 3331-A: Dominion Cove Point LNG, LP - Dk. No. 11-128-LNG |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy 331-A: Dominion Cove Point LNG, LP - Dk. No. 11-128-LNG Order 3331-A: Dominion Cove Point LNG, LP - Dk. No. 11-128-LNG FINAL ORDER AND OPINION GRANTING LONG-TERM MULTI-CONTRACT AUTHORIZATION TO EXPORT LIQUEFIED NATURAL GAS BY VESSEL FROM THE DOMINION COVE POINT LNG TERMINAL IN CALVERT COUNTY, MARYLAND TO NON-FREE TRADE AGREEMENT NATIONS Based on a review of the complete record and for the reasons set forth below, DOE/FE has concluded that the opponents of the Dominion

  12. Microsoft PowerPoint - 08 Lawrence 2010 DOE PM Workshop_EO

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    13514_03-01-10_presentation | Department of Energy 8 Lawrence 2010 DOE PM Workshop_EO 13514_03-01-10_presentation Microsoft PowerPoint - 08 Lawrence 2010 DOE PM Workshop_EO 13514_03-01-10_presentation Microsoft PowerPoint - 08 Lawrence 2010 DOE PM Workshop_EO 13514_03-01-10_presentation (1.69 MB) More Documents & Publications OVERVIEW OF EXECUTIVE ORDER 13XXX Federal Leadership in Environmental, Energy and Economic Performance Microsoft PowerPoint - 05 Okonski final Project Management

  13. Final 2011 Supplement Analysis of the 2005 Final SWEIS | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Final 2011 Supplement Analysis of the 2005 Final SWEIS Final 2011 Supplement Analysis of the 2005 Final Site-wide Environmental Impact Statement for Continued Operation of LLNL The below final SUPPLEMENT ANALYSIS is available for public viewing. Final 2011 SUPPLEMENT ANALYSIS of the 2005 Final Site-wide Environmental Impact Statement for Continued Operation of Lawrence Livermore National Laboratory Below are links to the final comments response and final

  14. Microsoft PowerPoint - DOE O 413 3B Brief v9 with key points...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Example BCP Template Microsoft PowerPoint - DOE O 413 3B Brief v9 with key points in notes Read-Only CD-2, Approve Performance Baseline External Independent Review (EIR) Standard ...

  15. Anderson Acceleration for Fixed-Point Iterations

    SciTech Connect

    Walker, Homer F.

    2015-08-31

    The purpose of this grant was to support research on acceleration methods for fixed-point iterations, with applications to computational frameworks and simulation problems that are of interest to DOE.

  16. City of Boulder- Green Points Building Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Boulder Green Points Building Program is a mandatory residential green building program that requires a builder or homeowner to include a minimum amount of sustainable building components bas...

  17. Analysis of Crossover Points for MVLT Superclass

    Energy Saver

    of Cross-Over Points for Grain-Oriented Electrical Steel and Amorphous Ribbon for the MVLT ... transformers with M-3 grain-oriented electrical steel core designs crosses the low-cost ...

  18. LMJ Points Plus v2.6

    Energy Science and Technology Software Center

    2013-01-15

    Short summary of the software's functionality: • built-in scan feature to acquire optical image of the surface to be analyzed • click-and-point selection of points of interest on the surface • supporting standalone autosampler/HPLC/MS operation: creating independent batch files after points of interests are selected for LEAPShell (autosampler control software from Leap Technologies) and Analyst® (mass spectrometry (MS) software from AB Sciex) • supporting integrated autosampler/HPLC/MS operation: creating one batch file for all instruments controlledmore » by Analyst® (mass spectrometry software from AB Sciex) after points of interests are selected •creating heatmaps of analytes of interests from collected MS files in a hand-off fashion« less

  19. CenterPoint Energy's Energy Wise Program

    Energy.gov [DOE]

    CenterPoint Energy's Energy Wise program provides take-home kits containing efficiency devices with classroom and in-home education techniques with the aim to inspire families to adopt new resource...

  20. CenterPoint Energy Sustainable Schools Program

    Energy.gov [DOE]

    The Sustainable Schools Program focuses on energy savings through behavioral and operational improvements, and may be used along with CenterPoint Energy’s SCORE and Load Management programs. It...