National Library of Energy BETA

Sample records for analysis core analysis

  1. Category:Core Analysis | Open Energy Information

    Open Energy Info (EERE)

    Analysis page? For detailed information on Core Analysis as exploration techniques, click here. Category:Core Analysis Add.png Add a new Core Analysis Technique Pages in...

  2. Core Analysis | Open Energy Information

    Open Energy Info (EERE)

    Area 1992 K-Ar Dates Of Hydrothermal Clays From Core Hole Vc-2B, Valles Caldera, New Mexico And Their Relation To Alteration In A Large Hydrothermal System Core Analysis At...

  3. HTTF Core Stress Analysis

    SciTech Connect (OSTI)

    Brian D. Hawkes; Richard Schultz

    2012-07-01

    In accordance with the need to determine whether cracking of the ceramic core disks which will be constructed and used in the High Temperature Test Facility (HTTF) for heatup and cooldown experiments, a set of calculation were performed using Abaqus to investigate the thermal stresses levels and likelihood for cracking. The calculations showed that using the material properties provided for the Greencast 94F ceramic, cracking is predicted to occur. However, this modeling does not predict the size or length of the actual cracks. It is quite likely that cracks will be narrow with rough walls which would impede the flow of coolant gases entering the cracks. Based on data recorded at Oregon State University using Greencast 94F samples that were heated and cooled at prescribed rates, it was concluded that the likelihood that the cracks would be detrimental to the experimental objectives is small.

  4. Multi-core Performance Analysis

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

    core Performance Analysis HPC Computation 1 Performance Analysis * Compiler Feedback * HWPC Data * Load Balance 2 Compiler Feedback * Before optimizing code, it's critical to know what the compiler does to your code - Loop optimizations - Vectorization - Prefetching - ... * Equally important to what the compiler does is what it doesn't do, and why - Data dependencies - Misplaced branches - Unknown loop counts - ... 3 Enabling Compiler Feedback * Portland Group - Minfo=all - Mneginfo - Minfo=ccff

  5. Core Analysis At Alum Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Core Analysis At Alum Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Alum Area (DOE GTP) Exploration Activity...

  6. Overview on Hydrate Coring, Handling and Analysis

    SciTech Connect (OSTI)

    Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

    2003-06-30

    Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

  7. Core Analysis At Raft River Geothermal Area (1981) | Open Energy...

    Open Energy Info (EERE)

    search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Raft River Geothermal Area (1981) Exploration Activity Details Location Raft River...

  8. Core Analysis At Raft River Geothermal Area (1976) | Open Energy...

    Open Energy Info (EERE)

    search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Raft River Geothermal Area (1976) Exploration Activity Details Location Raft River...

  9. Core Analysis At Jemez Mountain Area (Eichelberger & Koch, 1979...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Jemez Mountain Area (Eichelberger & Koch, 1979) Exploration Activity...

  10. Geologic analysis of Devonian Shale cores

    SciTech Connect (OSTI)

    1982-02-01

    Cleveland Cliffs Iron Company was awarded a DOE contract in December 1977 for field retrieval and laboratory analysis of cores from the Devonian shales of the following eleven states: Michigan, Illinois, Indiana, Ohio, New York, Pennsylvania, West Virginia, Maryland, Kentucky, Tennessee and Virginia. The purpose of this project is to explore these areas to determine the amount of natural gas being produced from the Devonian shales. The physical properties testing of the rock specimens were performed under subcontract at Michigan Technological University (MTU). The study also included LANDSAT information, geochemical research, structural sedimentary and tectonic data. Following the introduction, and background of the project this report covers the following: field retrieval procedures; laboratory procedures; geologic analysis (by state); references and appendices. (ATT)

  11. Core Analysis At Raft River Geothermal Area (1979) | Open Energy...

    Open Energy Info (EERE)

    Raft River Geothermal Area (1979) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Raft River Geothermal Area (1979) Exploration...

  12. Core Analysis At Flint Geothermal Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Flint Geothermal Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Flint Geothermal Area (DOE GTP) Exploration...

  13. Core Analysis At Colrado Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Colrado Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Colrado Area (DOE GTP) Exploration Activity Details...

  14. Core Analysis At Mcgee Mountain Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Mcgee Mountain Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Mcgee Mountain Area (DOE GTP) Exploration Activity...

  15. Core Analysis At Geysers Area (Lambert & Epstein, 1992) | Open...

    Open Energy Info (EERE)

    (Lambert & Epstein, 1992) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Geysers Area (Lambert & Epstein, 1992) Exploration...

  16. Core Analysis At Desert Peak Area (Laney, 2005) | Open Energy...

    Open Energy Info (EERE)

    Desert Peak Area (Laney, 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Desert Peak Area (Laney, 2005) Exploration...

  17. Core Analysis At Geysers Area (Boitnott, 2003) | Open Energy...

    Open Energy Info (EERE)

    Exploration Activity Details Location Geysers Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown References Greg N. Boitnott...

  18. Core Analysis At International Geothermal Area, Indonesia (Boitnott...

    Open Energy Info (EERE)

    Location International Geothermal Area Indonesia Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown References Greg N. Boitnott...

  19. Core Analysis At Newberry Caldera Area (Carothers, Et Al., 1987...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Newberry Caldera Area (Carothers, Et Al., 1987) Exploration Activity...

  20. Core Analysis At Coso Geothermal Area (1980) | Open Energy Information

    Open Energy Info (EERE)

    Exploration Activity Details Location Coso Geothermal Area Exploration Technique Core Analysis Activity Date 1980 Usefulness not indicated DOE-funding Unknown Exploration Basis...

  1. Core Analysis At Fenton Hill HDR Geothermal Area (Brookins &...

    Open Energy Info (EERE)

    Core Analysis Activity Date - 1983 Usefulness useful DOE-funding Unknown Notes See linked abstract for a synopsis of chemical analyses and Rb-Sr age determinations for gneissic...

  2. Core Analysis At Kilauea East Rift Geothermal Area (Quane, Et...

    Open Energy Info (EERE)

    rates lavas from Kilauea's East Rift Zone. The core analysis revealed that the average rate of lava expelled from the volcano has been remarkably constant for the last 350,000...

  3. Third (March 2006) Coring and Analysis of Zero-Valent Iron Permeable Reactive Barrier, Monticello, Utah

    Broader source: Energy.gov [DOE]

    Third (March 2006) Coring and Analysis of Zero-Valent Iron Permeable Reactive Barrier, Monticello, Utah

  4. BWR containment failure analysis during degraded-core accidents

    SciTech Connect (OSTI)

    Yue, D.D.

    1982-06-06

    This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents.

  5. Analysis of MSE Cores Tuba City, Arizona, Site | Department of Energy

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

    MSE Cores Tuba City, Arizona, Site Analysis of MSE Cores Tuba City, Arizona, Site Analysis of MSE Cores Tuba City, Arizona, Site Analysis of MSE Cores Tuba City, Arizona, Site (3.46 MB) More Documents & Publications Analysis of Contaminant Rebound in Ground Water in Extraction Wells at the Tuba City, Arizona, Site Uranium-Bearing Evaporite Mineralization Influencing Plume Persistence: Literature Review and DOE-LM Site Surveys Diffusion Multilayer Sampling of Ground Water in Five Wells at the

  6. Criticality safety analysis on fissile materials in Fukushima reactor cores

    SciTech Connect (OSTI)

    Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong; Hirano, Fumio

    2013-07-01

    The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

  7. 100-KE REACTOR CORE REMOVAL PROJECT ALTERNATIVE ANALYSIS WORKSHOP REPORT

    SciTech Connect (OSTI)

    HARRINGTON RA

    2010-01-15

    On December 15-16, 2009, a 100-KE Reactor Core Removal Project Alternative Analysis Workshop was conducted at the Washington State University Consolidated Information Center, Room 214. Colburn Kennedy, Project Director, CH2M HILL Plateau Remediation Company (CHPRC) requested the workshop and Richard Harrington provided facilitation. The purpose of the session was to select the preferred Bio Shield Alternative, for integration with the Thermal Shield and Core Removal and develop the path forward to proceed with project delivery. Prior to this workshop, the S.A. Robotics (SAR) Obstruction Removal Alternatives Analysis (565-DLV-062) report was issued, for use prior to and throughout the session, to all the team members. The multidisciplinary team consisted ofrepresentatives from 100-KE Project Management, Engineering, Radcon, Nuclear Safety, Fire Protection, Crane/Rigging, SAR Project Engineering, the Department of Energy Richland Field Office, Environmental Protection Agency, Washington State Department of Ecology, Defense Nuclear Facility Safety Board, and Deactivation and Decommission subject matter experts from corporate CH2M HILL and Lucas. Appendix D contains the workshop agenda, guidelines and expectations, opening remarks, and attendance roster going into followed throughout the workshop. The team was successful in selecting the preferred alternative and developing an eight-point path forward action plan to proceed with conceptual design. Conventional Demolition was selected as the preferred alternative over two other alternatives: Diamond Wire with Options, and Harmonic Delamination with Conventional Demolition. The teams preferred alternative aligned with the SAR Obstruction Removal Alternative Analysis report conclusion. However, the team identified several Path Forward actions, in Appendix A, which upon completion will solidify and potentially enhance the Conventional Demolition alternative with multiple options and approaches to achieve project delivery

  8. Core Analysis At Silver Peak Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Silver Peak Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Silver Peak Area (DOE GTP) Exploration Activity...

  9. Core Analysis At Black Warrior Area (DOE GTP) | Open Energy Informatio...

    Open Energy Info (EERE)

    Black Warrior Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Black Warrior Area (DOE GTP) Exploration Activity...

  10. Core Analysis At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Gabbs Valley Area (DOE GTP) Exploration Activity...

  11. Core Analysis At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fish Lake Valley Area (DOE GTP) Exploration...

  12. Core Analysis At Snake River Plain Region (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Snake River Plain Region (DOE GTP) Exploration Activity Details Location...

  13. Core Analysis At Fort Bliss Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fort Bliss Area (DOE GTP) Exploration Activity Details Location Fort Bliss...

  14. ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

    SciTech Connect (OSTI)

    Reigel, M.; Cheng, W.

    2012-01-26

    The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements

  15. Core Analysis At Coso Geothermal Area (1979) | Open Energy Information

    Open Energy Info (EERE)

    useful DOE-funding Unknown Exploration Basis Compare microcracks between Coso and Raft River geothermal areas Notes Microcracks were observed in core samples from Coso. Both...

  16. Core Analysis At Raft River Geothermal Area (2011) | Open Energy...

    Open Energy Info (EERE)

    that were conducted on the core sample are presented. References Jones, C.; Moore, J.; Teplow, W.; Craig, S. (1 January 2011) GEOLOGY AND HYDROTHERMAL ALTERATION OF THE...

  17. TREAT Transient Analysis Benchmarking for the HEU Core

    SciTech Connect (OSTI)

    Kontogeorgakos, D. C.; Connaway, H. M.; Wright, A. E.

    2014-05-01

    This work was performed to support the feasibility study on the potential conversion of the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory from the use of high enriched uranium (HEU) fuel to the use of low enriched uranium (LEU) fuel. The analyses were performed by the GTRI Reactor Conversion staff at the Argonne National Laboratory (ANL). The objective of this study was to benchmark the transient calculations against temperature-limited transients performed in the final operating HEU TREAT core configuration. The MCNP code was used to evaluate steady-state neutronics behavior, and the point kinetics code TREKIN was used to determine core power and energy during transients. The first part of the benchmarking process was to calculate with MCNP all the neutronic parameters required by TREKIN to simulate the transients: the transient rod-bank worth, the prompt neutron generation lifetime, the temperature reactivity feedback as a function of total core energy, and the core-average temperature and peak temperature as a functions of total core energy. The results of these calculations were compared against measurements or against reported values as documented in the available TREAT reports. The heating of the fuel was simulated as an adiabatic process. The reported values were extracted from ANL reports, intra-laboratory memos and experiment logsheets and in some cases it was not clear if the values were based on measurements, on calculations or a combination of both. Therefore, it was decided to use the term ďreportedĒ values when referring to such data. The methods and results from the HEU core transient analyses will be used for the potential LEU core configurations to predict the converted (LEU) coreís performance.

  18. Core Analysis At Yellowstone Region (Sturchio, Et Al., 1990)...

    Open Energy Info (EERE)

    were 43 hydrothermal minerals (silica, clay and calcite) from Yellowstone drill cores Y-5, Y-6, Y-7, Y-8, Y-11, Y-12, and Y-13 (Fig. 1). References N. C. Sturchio, T. E. C....

  19. Lithium Intercalation in Core-Shell Materials-Theoretical Analysis

    SciTech Connect (OSTI)

    Suthar, B; Subramanian, VR

    2014-03-04

    Core-shell composite structures are potential candidates for Li-ion battery electrodes as they can take advantage of materials with higher energy density and materials with higher cyclability. This paper derives an analytical solution for isotropic 1-dimensional diffusion with galvanostatic boundary condition in composite slab, cylinder and sphere using separation of variables method. A general interfacial condition has been used to represent the dynamics at the interface of the composite material rendering the solution useful for wide variety of battery materials. Using the derived analytical solution for diffusion, intercalation induced stresses were estimated for spherical core-shell materials. (C) 2014 The Electrochemical Society. All rights reserved.

  20. Analysis of core uncovery time in Kuosheng station blackout transient with MELCOR

    SciTech Connect (OSTI)

    Wang, S.J.; Chien, C.S. [Inst. of Nuclear Energy Research, Lungtan (Taiwan, Province of China)

    1996-02-01

    The MELCOR code, developed by the Sandia National Laboratories, is capable of simulating severe accident phenomena of nuclear power plants. Core uncovery time is an important parameter in the probabilistic risk assessment. However, many MELCOR users do not generate the initial conditions in a station blackout (SBO) transient analysis. Thus, achieving reliable core uncovery time is difficult. The core uncovery time for the Kuosheng nuclear power plant during an SBO transient is analyzed. First, full-power steady-state conditions are generated with the application of a developed self-initialization algorithm. Then the response of the SBO transient up to core uncovery is simulated. The effects of key parameters including the initialization process and the reactor feed pump (RFP) coastdown time on the core uncovery time are analyzed. The initialization process is the most important parameter that affects the core uncovery time. Because SBO transient analysis, the correct initial conditions must be generated to achieve a reliable core uncovery time. The core uncovery time is also sensitive to the RFP coastdown time. A correct time constant is required.

  1. Thermal-stress analysis of a Fort St. Vrain core-support block under accident conditions

    SciTech Connect (OSTI)

    Carruthers, L.M.; Butler, T.A.; Anderson, C.A.

    1982-01-01

    A thermoelastic stress analysis of a graphite core support block in the Fort St. Vrain High Temperature Gas Cooled Reactor is described. The support block is subjected to thermal stresses caused by a loss of forced circulation accident of the reactor system. Two- and three-dimensional finite element models of the core support block are analyzed using the ADINAT and ADINA codes, and results are given that verify the integrity of this structural component under the given accident condition.

  2. Development of flow network analysis code for block type VHTR core by linear theory method

    SciTech Connect (OSTI)

    Lee, J. H.; Yoon, S. J.; Park, J. W.; Park, G. C.

    2012-07-01

    VHTR (Very High Temperature Reactor) is high-efficiency nuclear reactor which is capable of generating hydrogen with high temperature of coolant. PMR (Prismatic Modular Reactor) type reactor consists of hexagonal prismatic fuel blocks and reflector blocks. The flow paths in the prismatic VHTR core consist of coolant holes, bypass gaps and cross gaps. Complicated flow paths are formed in the core since the coolant holes and bypass gap are connected by the cross gap. Distributed coolant was mixed in the core through the cross gap so that the flow characteristics could not be modeled as a simple parallel pipe system. It requires lot of effort and takes very long time to analyze the core flow with CFD analysis. Hence, it is important to develop the code for VHTR core flow which can predict the core flow distribution fast and accurate. In this study, steady state flow network analysis code is developed using flow network algorithm. Developed flow network analysis code was named as FLASH code and it was validated with the experimental data and CFD simulation results. (authors)

  3. New time-line technique for station blackout core-melt analysis

    SciTech Connect (OSTI)

    Stutzke, M.A.

    1986-01-01

    Florida Power Corporation (FPC) has developed a new method for analyzing station blackout (SBO) core-melt accidents. This method, created during the recent probabilistic risk assessment (PRA) of Crystal River Unit 3 (CR-3), originated from the need to analyze the interactions among the two-train emergency feedwater (EFW) system, station batteries, and diesel generators (DGs) following a loss of off-site power (LOSP) event. SBO core-melt sequences for CR-3 are unique since the time core-melt commences depends on which DG fails last. The purpose of this paper is to outline the new method of analysis of SBO core-melt accidents at CR-3. The significance of SBO core-melt accidents to total plant risk, along with the efficacy of various methods to reduce SBO risk, are also discussed.

  4. PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle

    SciTech Connect (OSTI)

    Bi, G.; Liu, C.; Si, S.

    2012-07-01

    This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no

  5. Thermal-hydraulic analysis of advanced reactor concepts: The Gas Core Nuclear Rocket

    SciTech Connect (OSTI)

    Banjac, V.; Heger, A.S.

    1995-12-31

    The Gas Core Nuclear Rocket (GCNR), a design first proposed in the 1960s for fast round-trip missions to Mars and the outer planets, is generally considered to be the most advanced, and therefore the most complex, iteration of the fission reactor concept. The GCNR technology involves the extraction of fission energy, by means of thermal radiation, from a high-temperature plasma core to a working fluid. A specific derivative of GCNR technology is the nuclear fight bulb (NLB) rocket engine, first proposed by the then United Aircraft Research Laboratories (UARL) in the early 1960s. The potential operating parameters provided the motivation for a detailed thermal hydraulics analysis.

  6. Three-dimensional thermoelastic analysis of a Fort St. Vrain core support block

    SciTech Connect (OSTI)

    Butler, T.A.; Anderson, C.A.

    1981-09-01

    A thermoelastic stress analysis of a graphite core support block in the Fort St. Vrain High-Temperature Gas-Cooled Reactor is described. The support block is subjected to thermal stresses caused by a loss of forced circulation accident of the reactor system. Two- and three-dimensional finite element models of the core support block are analyzed using the ADINAT and ADINA codes, and results are given that verify the integrity of this structural component under the given accident condition. 10 refs., 39 figs.

  7. Development of HELIOS/CAPP code system for the analysis of block type VHTR cores

    SciTech Connect (OSTI)

    Lee, H. C.; Han, T. Y.; Jo, C. K.; Noh, J. M.

    2012-07-01

    In this paper, the HELIOS/CAPP code system developed for the analysis of block type VHTR cores is presented and verified against several VHTR core configurations. Verification results shows that HELIOS code predicts less negative MTC and RTC than McCARD code does and thus HELIOS code overestimates the multiplication factors at the states with high moderator and reflector temperature especially when the B{sub 4}C BP is loaded. In the depletion calculation for the VHTR single cell fuel element, the error of HELIOS code increases as burnup does. It is ascribed to the fact that HELIOS code treats some fission product nuclides with large resonances as non-resonant nuclides. In the 2-D core depletion calculation, a relatively large reactivity error is observed in the case with BP loading while the reactivity error in the case without BP loading is less than 300 pcm. (authors)

  8. DANDE: a linked code system for core neutronics/depletion analysis

    SciTech Connect (OSTI)

    LaBauve, R.J.; England, T.R.; George, D.C.; MacFarlane, R.E.; Wilson, W.B.

    1985-06-01

    This report describes DANDE - a modular neutronics, depletion code system for reactor analysis. It consists of nuclear data processing, core physics, and fuel depletion modules, and allows one to use diffusion and transport methods interchangeably in core neutronics calculations. This latter capability is especially important in the design of small modular cores. Additional unique features include the capability of updating the nuclear data file during a calculation; a detailed treatment of depletion, burnable poisons as well as fuel; and the ability to make geometric changes such as control rod repositioning and fuel relocation in the course of a calculation. The detailed treatment of reactor fuel burnup, fission-product creation and decay, as well as inventories of higher-order actinides is a necessity when predicting the behavior of reactor fuel under increased burn conditions. The operation of the code system is made clear in this report by following a sample problem.

  9. Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll

    SciTech Connect (OSTI)

    Robison, W.L.; Noshkin, V.E.

    1981-02-18

    Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu and /sup 241/Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island radioecology and dose assessment work.

  10. Experimental investigation and CFD analysis on cross flow in the core of PMR200

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

    Lee, Jeong -Hun; Yoon, Su -Jong; Cho, Hyoung -Kyu; Jae, Moosung; Park, Goon -Cherl

    2015-04-16

    The Prismatic Modular Reactor (PMR) is one of the major Very High Temperature Reactor (VHTR) concepts, which consists of hexagonal prismatic fuel blocks and reflector blocks made of nuclear gradegraphite. However, the shape of the graphite blocks could be easily changed by neutron damage duringthe reactor operation and the shape change can create gaps between the blocks inducing the bypass flow.In the VHTR core, two types of gaps, a vertical gap and a horizontal gap which are called bypass gap and cross gap, respectively, can be formed. The cross gap complicates the flow field in the reactor core by connectingmore¬†¬Ľ the coolant channel to the bypass gap and it could lead to a loss of effective coolant flow in the fuel blocks. Thus, a cross flow experimental facility was constructed to investigate the cross flow phenomena in the core of the VHTR and a series of experiments were carried out under varying flow rates and gap sizes. The results of the experiments were compared with CFD (Computational Fluid Dynamics) analysis results in order to verify its prediction capability for the cross flow phenomena. Fairly good agreement was seen between experimental results and CFD predictions and the local characteristics of the cross flow was discussed in detail. Based on the calculation results, pressure loss coefficient across the cross gap was evaluated, which is necessary for the thermo-fluid analysis of the VHTR core using a lumped parameter code.¬ę¬†less

  11. Experimental investigation and CFD analysis on cross flow in the core of PMR200

    SciTech Connect (OSTI)

    Lee, Jeong -Hun; Yoon, Su -Jong; Cho, Hyoung -Kyu; Jae, Moosung; Park, Goon -Cherl

    2015-04-16

    The Prismatic Modular Reactor (PMR) is one of the major Very High Temperature Reactor (VHTR) concepts, which consists of hexagonal prismatic fuel blocks and reflector blocks made of nuclear gradegraphite. However, the shape of the graphite blocks could be easily changed by neutron damage duringthe reactor operation and the shape change can create gaps between the blocks inducing the bypass flow.In the VHTR core, two types of gaps, a vertical gap and a horizontal gap which are called bypass gap and cross gap, respectively, can be formed. The cross gap complicates the flow field in the reactor core by connecting the coolant channel to the bypass gap and it could lead to a loss of effective coolant flow in the fuel blocks. Thus, a cross flow experimental facility was constructed to investigate the cross flow phenomena in the core of the VHTR and a series of experiments were carried out under varying flow rates and gap sizes. The results of the experiments were compared with CFD (Computational Fluid Dynamics) analysis results in order to verify its prediction capability for the cross flow phenomena. Fairly good agreement was seen between experimental results and CFD predictions and the local characteristics of the cross flow was discussed in detail. Based on the calculation results, pressure loss coefficient across the cross gap was evaluated, which is necessary for the thermo-fluid analysis of the VHTR core using a lumped parameter code.

  12. Analysis of core damage frequency from internal events: Peach Bottom, Unit 2

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Lambright, J.A.; Ferrell, W.L.; Cathey, N.G.; Najafi, B.; Harper, F.T.

    1986-10-01

    This document contains the internal event initiated accident sequence analyses for Peach Bottom, Unit 2; one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Peach Bottom, Unit 2, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Peach Bottom core damage frequency estimate. The mean core damage frequency at Peach Bottom was calculated to be 8.2E-6. Station blackout type accidents (loss of all ac power) were found to dominate the overall results. Anticipated Transient Without Scram accidents were also found to be non-negligible contributors. The numerical results are largely driven by common mode failure probability estimates and to some extent, human error. Because of significant data and analysis uncertainties in these two areas (important, for instance, to the most dominant scenario in this study), it is recommended that the results of the uncertainty and sensitivity analyses be considered before any actions are taken based on this analysis.

  13. Contributed Review: Nuclear magnetic resonance core analysis at 0.3 T

    SciTech Connect (OSTI)

    Mitchell, Jonathan Fordham, Edmund J.

    2014-11-15

    Nuclear magnetic resonance (NMR) provides a powerful toolbox for petrophysical characterization of reservoir core plugs and fluids in the laboratory. Previously, there has been considerable focus on low field magnet technology for well log calibration. Now there is renewed interest in the study of reservoir samples using stronger magnets to complement these standard NMR measurements. Here, the capabilities of an imaging magnet with a field strength of 0.3 T (corresponding to 12.9 MHz for proton) are reviewed in the context of reservoir core analysis. Quantitative estimates of porosity (saturation) and pore size distributions are obtained under favorable conditions (e.g., in carbonates), with the added advantage of multidimensional imaging, detection of lower gyromagnetic ratio nuclei, and short probe recovery times that make the system suitable for shale studies. Intermediate field instruments provide quantitative porosity maps of rock plugs that cannot be obtained using high field medical scanners due to the field-dependent susceptibility contrast in the porous medium. Example data are presented that highlight the potential applications of an intermediate field imaging instrument as a complement to low field instruments in core analysis and for materials science studies in general.

  14. TRACE/PARCS Core Modeling of a BWR/5 for Accident Analysis of ATWS Events

    SciTech Connect (OSTI)

    Cuadra A.; Baek J.; Cheng, L.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10

    The TRACE/PARCS computational package [1, 2] isdesigned to be applicable to the analysis of light water reactor operational transients and accidents where the coupling between the neutron kinetics (PARCS) and the thermal-hydraulics and thermal-mechanics (TRACE) is important. TRACE/PARCS has been assessed for itsapplicability to anticipated transients without scram(ATWS) [3]. The challenge, addressed in this study, is to develop a sufficiently rigorous input model that would be acceptable for use in ATWS analysis. Two types of ATWS events were of interest, a turbine trip and a closure of main steam isolation valves (MSIVs). In the first type, initiated by turbine trip, the concern is that the core will become unstable and large power oscillations will occur. In the second type,initiated by MSIV closure,, the concern is the amount of energy being placed into containment and the resulting emergency depressurization. Two separate TRACE/PARCS models of a BWR/5 were developed to analyze these ATWS events at MELLLA+ (maximum extended load line limit plus)operating conditions. One model [4] was used for analysis of ATWS events leading to instability (ATWS-I);the other [5] for ATWS events leading to emergency depressurization (ATWS-ED). Both models included a large portion of the nuclear steam supply system and controls, and a detailed core model, presented henceforth.

  15. Analysis of core damage frequency: Peach Bottom, Unit 2 internal events appendices

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L.; Sandia National Labs., Albuquerque, NM )

    1989-08-01

    This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. The mean core damage frequency is 4.5E-6 with 5% and 95% uncertainty bounds of 3.5E-7 and 1.3E-5, respectively. Station blackout type accidents (loss of all ac power) contributed about 46% of the core damage frequency with Anticipated Transient Without Scram (ATWS) accidents contributing another 42%. The numerical results are driven by loss of offsite power, transients with the power conversion system initially available operator errors, and mechanical failure to scram. 13 refs., 345 figs., 171 tabs.

  16. Design and analysis of large-core single-mode windmill single crystal sapphire optical fiber

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

    Cheng, Yujie; Hill, Cary; Liu, Bo; Yu, Zhihao; Xuan, Haifeng; Homa, Daniel; Wang, Anbo; Pickrell, Gary

    2016-06-01

    We present a large-core single-mode ‚Äúwindmill‚ÄĚ single crystal sapphire optical fiber (SCSF) design, which exhibits single-mode operation by stripping off the higher-order modes (HOMs) while maintaining the fundamental mode. The ‚Äúwindmill‚ÄĚ SCSF design was analyzed using the finite element analysis method, in which all the HOMs are leaky. The numerical simulation results show single-mode operation in the spectral range from 0.4 to 2 őľm in the windmill SCSF, with an effective core diameter as large as 14 őľm. Such fiber is expected to improve the performance of many of the current sapphire fiber optic sensor structures.

  17. Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.

    Energy Science and Technology Software Center (OSTI)

    1992-06-12

    Version 00 VPI-NECM is a nuclear engineering computer system of modules for in-core fuel management analysis. The system consists of 6 independent programs designed to calculate: (1) FARCON - neutron slowing down and epithermal group constants, (2) SLOCON - thermal neutron spectrum and group constants, (3) DISFAC - slow neutron disadvantage factors, (4) ODOG - solution of a one group neutron diffusion equation, (5) ODMUG - three group criticality problem, (6) FUELBURN - fuel burnupmore¬†¬Ľ in slow neutron fission reactors.¬ę¬†less

  18. Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling

    SciTech Connect (OSTI)

    Kneafsey, Timothy J.; Lu, Hailong; Winters, William; Boswell, Ray; Hunter, Robert; Collett, Timothy S.

    2009-09-01

    Collecting and preserving undamaged core samples containing gas hydrates from depth is difficult because of the pressure and temperature changes encountered upon retrieval. Hydrate-bearing core samples were collected at the BPXA-DOE-USGS Mount Elbert Gas Hydrate Stratigraphic Test Well in February 2007. Coring was performed while using a custom oil-based drilling mud, and the cores were retrieved by a wireline. The samples were characterized and subsampled at the surface under ambient winter arctic conditions. Samples thought to be hydrate bearing were preserved either by immersion in liquid nitrogen (LN), or by storage under methane pressure at ambient arctic conditions, and later depressurized and immersed in LN. Eleven core samples from hydrate-bearing zones were scanned using x-ray computed tomography to examine core structure and homogeneity. Features observed include radial fractures, spalling-type fractures, and reduced density near the periphery. These features were induced during sample collection, handling, and preservation. Isotopic analysis of the methane from hydrate in an initially LN-preserved core and a pressure-preserved core indicate that secondary hydrate formation occurred throughout the pressurized core, whereas none occurred in the LN-preserved core, however no hydrate was found near the periphery of the LN-preserved core. To replicate some aspects of the preservation methods, natural and laboratory-made saturated porous media samples were frozen in a variety of ways, with radial fractures observed in some LN-frozen sands, and needle-like ice crystals forming in slowly frozen clay-rich sediments. Suggestions for hydrate-bearing core preservation are presented.

  19. Coupling the core analysis program DeCART to the fuel performance application BISON

    SciTech Connect (OSTI)

    Gleicher, F. N.; Spencer, B.; Novascone, S.; Williamson, R.; Martineau, R. C. [Idaho National Laboratory, 2525 N. Fremont Avenue, Idaho Falls, ID 83415 (United States); Rose, M.; Downar, T. J.; Collins, B. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI 48105 (United States)

    2013-07-01

    The 3D neutron transport and core analysis program DeCART was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the method of characteristics) to a high fidelity fuel performance program, both of which can simulate 3D problems. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during burnup or a fast transient. BISON implicitly solves coupled thermomechanical equations for the fuel on a sub-millimeter level finite element mesh. A method was developed for mapping the fission rate density and fast neutron flux from DeCART to BISON. Multiple depletion cases were run with one-way data transfer from DeCART to BISON. The one-way data transfer of fission rate density is shown to agree with the fission rate density obtained from an internal Lassman-style model in BISON. One-way data transfer was also demonstrated in a 3D case in which azimuthal asymmetry was induced in the fission rate density profile of a fuel rod modeled in DeCART. Two-way data transfer was established by mapping the temperature distribution from BISON to DeCART. A Picard iterative algorithm was developed for the loose coupling with two-way data transfer. (authors)

  20. CORE ANALYSIS, DESIGN AND OPTIMIZATION OF A DEEP-BURN PEBBLE BED REACTOR

    SciTech Connect (OSTI)

    B. Boer; A. M. Ougouag

    2010-05-01

    Achieving a high burnup in the Deep-Burn pebble bed reactor design, while remaining within the limits for fuel temperature, power peaking and temperature reactivity feedback, is challenging. The high content of Pu and Minor Actinides in the Deep-Burn fuel significantly impacts the thermal neutron energy spectrum. This can result in power and temperature peaking in the pebble bed core in locally thermalized regions near the graphite reflectors. Furthermore, the interplay of the Pu resonances of the neutron absorption cross sections at low-lying energies can lead to a positive temperature reactivity coefficient for the graphite moderator at certain operating conditions. To investigate the aforementioned effects a code system using existing codes has been developed for neutronic, thermal-hydraulic and fuel depletion analysis of Deep-Burn pebble bed reactors. A core analysis of a Deep-Burn Pebble Bed Modular Reactor (400 MWth) design has been performed for two Deep-Burn fuel types and possible improvements of the design with regard to power peaking and temperature reactivity feedback are identified.

  1. Analysis of Fracture in Cores from the Tuff Confining Unit beneath Yucca Flat, Nevada Test Site

    SciTech Connect (OSTI)

    Lance Prothro

    2008-03-01

    The role fractures play in the movement of groundwater through zeolitic tuffs that form the tuff confining unit (TCU) beneath Yucca Flat, Nevada Test Site, is poorly known. This is an important uncertainty, because beneath most of Yucca Flat the TCU lies between the sources of radionuclide contaminants produced by historic underground nuclear testing and the regional carbonate aquifer. To gain a better understanding of the role fractures play in the movement of groundwater and radionuclides through the TCU beneath Yucca Flat, a fracture analysis focusing on hydraulic properties was performed on conventional cores from four vertical exploratory holes in Area 7 of Yucca Flat that fully penetrate the TCU. The results of this study indicate that the TCU is poorly fractured. Fracture density for all fractures is 0.27 fractures per vertical meter of core. For open fractures, or those observed to have some aperture, the density is only 0.06 fractures per vertical meter of core. Open fractures are characterized by apertures ranging from 0.1 to 10 millimeter, and averaging 1.1 millimeter. Aperture typically occurs as small isolated openings along the fracture, accounting for only 10 percent of the fracture volume, the rest being completely healed by secondary minerals. Zeolite is the most common secondary mineral occurring in 48 percent of the fractures observed.

  2. Thermal hydraulic method for whole core design analysis of an HTGR

    SciTech Connect (OSTI)

    Huning, A. J.; Garimella, S. [George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA (United States)

    2013-07-01

    A new thermal hydraulic method and initial results are presented for core-wide steady state analysis of prismatic High Temperature Gas-Cooled Reactors (HTGR). The method allows for the complete solution of temperature and coolant mass flow distribution by solving quasi-steady energy balances for the discretized core. Assembly blocks are discretized into unit cells for which the average temperature of each unit cell is determined. Convective heat removal is coupled to the unit cell energy balances by a 1-D axial flow model. The flow model uses established correlations for friction factor and Nusselt number. Bypass flow is explicitly calculated by using an initial guess for mass flow distribution and determining the exit pressure of each flow channel. The mass flow distribution is updated until a uniform core exit pressure condition is reached. Results are obtained for the MHTGR-350 with emphasis on the change in thermal hydraulic parameters due to various steady state power profiles and bypass gap widths. Steady state temperature distribution and its variations are discussed. (authors)

  3. A Raman cell based on hollow core photonic crystal fiber for human breath analysis

    SciTech Connect (OSTI)

    Chow, Kam Kong; Zeng, Haishan; Short, Michael; Lam, Stephen; McWilliams, Annette

    2014-09-15

    Purpose: Breath analysis has a potential prospect to benefit the medical field based on its perceived advantages to become a point-of-care, easy to use, and cost-effective technology. Early studies done by mass spectrometry show that volatile organic compounds from human breath can represent certain disease states of our bodies, such as lung cancer, and revealed the potential of breath analysis. But mass spectrometry is costly and has slow-turnaround time. The authors‚Äô goal is to develop a more portable and cost effective device based on Raman spectroscopy and hollow core-photonic crystal fiber (HC-PCF) for breath analysis. Methods: Raman scattering is a photon-molecular interaction based on the kinetic modes of an analyte which offers unique fingerprint type signals that allow molecular identification. HC-PCF is a novel light guide which allows light to be confined in a hollow core and it can be filled with a gaseous sample. Raman signals generated by the gaseous sample (i.e., human breath) can be guided and collected effectively for spectral analysis. Results: A Raman-cell based on HC-PCF in the near infrared wavelength range was developed and tested in a single pass forward-scattering mode for different gaseous samples. Raman spectra were obtained successfully from reference gases (hydrogen, oxygen, carbon dioxide gases), ambient air, and a human breath sample. The calculated minimum detectable concentration of this system was ‚ąľ15 parts per million by volume, determined by measuring the carbon dioxide concentration in ambient air via the characteristic Raman peaks at 1286 and 1388 cm{sup ‚ąí1}. Conclusions: The results of this study were compared to a previous study using HC-PCF to trap industrial gases and backward-scatter 514.5 nm light from them. The authors found that the method presented in this paper has an advantage to enhance the signal-to-noise ratio (SNR). This SNR advantage, coupled with the better transmission of HC-PCF in the near-IR than in the

  4. RELAP5-3D Code Application for RBMK-1500 Reactor Core Analysis

    SciTech Connect (OSTI)

    Bubelis, Evaldas; Kaliatka, Algirdas; Uspuras, Eugenijus

    2002-07-01

    The paper presents an evaluation of RELAP5-3D code suitability to model specific transients that take place during RBMK-1500 reactor operation, where the neutronic response of the core is important. A successful best estimate RELAP5-3D model of the Ignalina NPP RBMK-1500 reactor has been developed and validated against real plant data. Certain RELAP5-3D transient calculation results were benchmarked against calculation results obtained using the Russian code STEPAN, specially designed for RBMK reactor analysis. Comparison of the results obtained, using the RELAP5-3D and STEPAN codes, showed quite good mutual coincidence of the calculation results and good agreement with real plant data. (authors)

  5. Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping

    SciTech Connect (OSTI)

    Permana, Sidik; Novitrian,; Waris, Abdul; Ismail; Suzuki, Mitsutoshi; Saito, Masaki

    2014-09-30

    Nuclear fuel breeding based on the capability of fuel conversion capability can be achieved by conversion ratio of some fertile materials into fissile materials during nuclear reaction processes such as main fissile materials of U-233, U-235, Pu-239 and Pu-241 and for fertile materials of Th-232, U-238, and Pu-240 as well as Pu-238. Minor actinide (MA) loading option which consists of neptunium, americium and curium will gives some additional contribution from converted MA into plutonium such as conversion Np-237 into Pu-238 and it's produced Pu-238 converts to Pu-239 via neutron capture. Increasing composition of Pu-238 can be used to produce fissile material of Pu-239 as additional contribution. Trans-uranium (TRU) fuel (Mixed fuel loading of MOX (U-Pu) and MA composition) and mixed oxide (MOX) fuel compositions are analyzed for comparative analysis in order to show the effect of MA to the plutonium productions in core in term of reactor criticality condition and fuel breeding capability. In the present study, neptunium (Np) nuclide is used as a representative of MAin trans-uranium (TRU) fuel composition as Np-MOX fuel type. It was loaded into the core region gives significant contribution to reduce the excess reactivity in comparing to mixed oxide (MOX) fuel and in the same time it contributes to increase nuclear fuel breeding capability of the reactor. Neptunium fuel loading scheme in FBR core region gives significant production of Pu-238 as fertile material to absorp neutrons for reducing excess reactivity and additional contribution for fuel breeding.

  6. Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2009-05-01

    The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

  7. Building waste management core indicators through Spatial Material Flow Analysis: Net recovery and transport intensity indexes

    SciTech Connect (OSTI)

    Font Vivanco, David; Puig Ventosa, Ignasi; Gabarrell Durany, Xavier

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Sustainability and proximity principles have a key role in waste management. Black-Right-Pointing-Pointer Core indicators are needed in order to quantify and evaluate them. Black-Right-Pointing-Pointer A systematic, step-by-step approach is developed in this study for their development. Black-Right-Pointing-Pointer Transport may play a significant role in terms of environmental and economic costs. Black-Right-Pointing-Pointer Policy action is required in order to advance in the consecution of these principles. - Abstract: In this paper, the material and spatial characterization of the flows within a municipal solid waste (MSW) management system are combined through a Network-Based Spatial Material Flow Analysis. Using this information, two core indicators are developed for the bio-waste fraction, the Net Recovery Index (NRI) and the Transport Intensity Index (TII), which are aimed at assessing progress towards policy-related sustainable MSW management strategies and objectives. The NRI approaches the capacity of a MSW management system for converting waste into resources through a systematic metabolic approach, whereas the TII addresses efficiency in terms of the transport requirements to manage a specific waste flow throughout the entire MSW management life cycle. Therefore, both indicators could be useful in assessing key MSW management policy strategies, such as the consecution of higher recycling levels (sustainability principle) or the minimization of transport by locating treatment facilities closer to generation sources (proximity principle). To apply this methodological approach, the bio-waste management system of the region of Catalonia (Spain) has been chosen as a case study. Results show the adequacy of both indicators for identifying those points within the system with higher capacity to compromise its environmental, economic and social performance and therefore establishing clear targets for policy

  8. Paleoclimate and Glaciological Reconstruction in Central Asia Through The Collection and Analysis of Ice Cores and Instrumental Data From the Tien Shan

    SciTech Connect (OSTI)

    Cameron P. Wake; Vladimir Aizen; Karl Kreutz

    2001-05-30

    Paleoclimate and Glaciological Reconstruction in Central Asis Through The Collection And Analysis of Ice Cores and Instrumental Data From The Tien Shan

  9. Analysis of core damage frequency due to external events at the DOE (Department of Energy) N-Reactor

    SciTech Connect (OSTI)

    Lambright, J.A.; Bohn, M.P.; Daniel, S.L. ); Baxter, J.T. ); Johnson, J.J.; Ravindra, M.K.; Hashimoto, P.O.; Mraz, M.J.; Tong, W.H.; Conoscente, J.P. ); Brosseau, D.A. )

    1990-11-01

    A complete external events probabilistic risk assessment has been performed for the N-Reactor power plant, making full use of all insights gained during the past ten years' developments in risk assessment methodologies. A detailed screening analysis was performed which showed that all external events had negligible contribution to core damage frequency except fires, seismic events, and external flooding. A limited scope analysis of the external flooding risk indicated that it is not a major risk contributor. Detailed analyses of the fire and seismic risks resulted in total (mean) core damage frequencies of 1.96E-5 and 4.60E-05 per reactor year, respectively. Detailed uncertainty analyses were performed for both fire and seismic risks. These results show that the core damage frequency profile for these events is comparable to that found for existing commercial power plants if proposed fixes are completed as part of the restart program. 108 refs., 85 figs., 80 tabs.

  10. High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor

    SciTech Connect (OSTI)

    Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

    2010-09-01

    The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450

  11. Core Analysis At Lake City Hot Springs Area (Benoit Et Al., 2005...

    Open Energy Info (EERE)

    Rock core analyses and mineral assemblage investigations References Dick Benoit, Joe Moore, Colin Goranson, David Blackwell (2005) Core Hole Drilling And Testing At The Lake...

  12. EVALUATION OF CORE PHYSICS ANALYSIS METHODS FOR CONVERSION OF THE INL ADVANCED TEST REACTOR TO LOW-ENRICHMENT FUEL

    SciTech Connect (OSTI)

    Mark DeHart; Gray S. Chang

    2012-04-01

    Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR.

  13. Paleomagnetic studies of Carboniferous and Permian in the U. K. Southern North Sea: Core orientation, paleocurrent analysis, and diagenetic application

    SciTech Connect (OSTI)

    Turner, P. ); Hartley, A.J. )

    1991-03-01

    The U.K. southern North Sea is a major gas province with production from Carboniferous and Permian reservoirs. It was a foreland basin in Carboniferous times uplifted to form a Lower Permian desert basin and subsequently deeply buried during the Mesozoic. Paleomagnetic methods have been used for burial analysis, core orientation, and paleocurrent studies. VRM is shown to be of only limited value for core orientation; problems relating to drilling effects and deflection by ChRM will be discussed. Detailed thermal demagnetization studies are most valuable. Blocking temperature spectra can be related to burial history curves, and ChRM directions isolated and compared with Carboniferous and Permian reference directions. ChRM is a valuable parameter for core orientation and thus paleocurrent studies. Examples will be shown from the Carboniferous and Lower Permian.

  14. Developing Fully Coupled Dynamical Reactor Core Isolation System Models in RELAP-7 for Extended Station Black-Out Analysis

    SciTech Connect (OSTI)

    Haihua Zhao; Ling Zou; Hongbin Zhang; David Andrs; Richard Martineau

    2014-04-01

    The reactor core isolation cooling (RCIC) system in a boiling water reactor (BWR) provides makeup water to the reactor vessel for core cooling when the main steam lines are isolated and the normal supply of water to the reactor vessel is lost. It was one of the very few safety systems still available during the Fukushima Daiichi accidents after the tsunamis hit the plants and the system successfully delayed the core meltdown for a few days for unit 2 & 3. Therefore, detailed models for RCIC system components are indispensable to understand extended station black-out accidents (SBO) for BWRs. As part of the effort to develop the new generation reactor system safety analysis code RELAP-7, major components to simulate the RCIC system have been developed. This paper describes the models for those components such as turbine, pump, and wet well. Selected individual component test simulations and a simplified SBO simulation up to but before core damage is presented. The successful implementation of the simplified RCIC and wet well models paves the way to further improve the models for safety analysis by including more detailed physical processes in the near future.

  15. Time-resolved characterization and energy balance analysis of implosion core in shock-ignition experiments at OMEGA

    SciTech Connect (OSTI)

    Florido, R. Mancini, R. C.; Nagayama, T.; Tommasini, R.; Delettrez, J. A.; Regan, S. P.

    2014-10-15

    Time-resolved temperature and density conditions in the core of shock-ignition implosions have been determined for the first time. The diagnostic method relies on the observation, with a streaked crystal spectrometer, of the signature of an Ar tracer added to the deuterium gas fill. The data analysis confirms the importance of the shell attenuation effect previously noted on time-integrated spectroscopic measurements of thick-wall targets [R. Florido et al., Phys. Rev. E 83, 066408 (2011)]. This effect must be taken into account in order to obtain reliable results. The extracted temperature and density time-histories are representative of the state of the core during the implosion deceleration and burning phases. As a consequence of the ignitor shock launched by the sharp intensity spike at the end of the laser pulse, observed average core electron temperature and mass density reach T‚ÄČ‚ąľ‚ÄČ1100‚ÄČeV and ŌĀ‚ÄČ‚ąľ‚ÄČ2‚ÄČg/cm{sup 3}; then temperature drops to T‚ÄČ‚ąľ‚ÄČ920‚ÄČeV while density rises to ŌĀ‚ÄČ‚ąľ‚ÄČ3.4‚ÄČg/cm{sup 3} about the time of peak compression. Compared to 1D hydrodynamic simulations, the experiment shows similar maximum temperatures and smaller densities. Simulations do not reproduce all observations. Differences are noted in the heating dynamics driven by the ignitor shock and the optical depth time-history of the compressed shell. Time-histories of core conditions extracted from spectroscopy show that the implosion can be interpreted as a two-stage polytropic process. Furthermore, an energy balance analysis of implosion core suggests an increase in total energy greater than what 1D hydrodynamic simulations predict. This new methodology can be implemented in other ICF experiments to look into implosion dynamics and help to understand the underlying physics.

  16. Analysis of core damage frequency: Peach Bottom, Unit 2 internal events

    SciTech Connect (OSTI)

    Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L.; Sandia National Labs., Albuquerque, NM )

    1989-08-01

    This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. 58 refs., 58 figs., 52 tabs.

  17. Quantitative EDS Analysis of Nanometer-Scale Core/Shell Pd/Rh...

    Office of Scientific and Technical Information (OSTI)

    of Nanometer-Scale CoreShell PdRh Structures. Authors: Sugar, Joshua Daniel ; Kotula, Paul Gabriel 1 ; Robinson, David ; Cappillino, Patrick + Show Author Affiliations (Sandia...

  18. KUGEL: a thermal, hydraulic, fuel performance, and gaseous fission product release code for pebble bed reactor core analysis

    SciTech Connect (OSTI)

    Shamasundar, B.I.; Fehrenbach, M.E.

    1981-05-01

    The KUGEL computer code is designed to perform thermal/hydraulic analysis and coated-fuel particle performance calculations for axisymmetric pebble bed reactor (PBR) cores. This computer code was developed as part of a Department of Energy (DOE)-funded study designed to verify the published core performance data on PBRs. The KUGEL code is designed to interface directly with the 2DB code, a two-dimensional neutron diffusion code, to obtain distributions of thermal power, fission rate, fuel burnup, and fast neutron fluence, which are needed for thermal/hydraulic and fuel performance calculations. The code is variably dimensioned so that problem size can be easily varied. An interpolation routine allows variable mesh size to be used between the 2DB output and the two-dimensional thermal/hydraulic calculations.

  19. Results of submerged sediment core sampling and analysis on Par Pond, Pond C, and L Lake: July 1995

    SciTech Connect (OSTI)

    Koch, J.W. II; Martin, F.D.; Friday, G.P.

    1996-06-01

    Sediment cores from shallow and deep water locations in Par Pond, Pond C, and L Lake were collected and analyzed in 1995 for radioactive and nonradioactive constituents. This core analysis was conducted to develop a defensible characterization of contaminants found in the sediments of Par Pond, Pond C, and L Lake. Mercury was the only nonradiological constituent with a nonestimated quantity that was detected above the U.S Environmental Protection Agency Region IV potential contaminants of concern screening criteria. It was detected at a depth of 0.3--0.6 meters (1.0--2.0 feet) at one location in L Lake. Cesium-137, promethium-146, plutonium-238, and zirconium-95 had significantly higher concentrations in Par Pond sediments than in sediments from the reference sites. Cobalt-60, cesium-137, plutonium-238, plutonium-239/240, and strontium-90 had significantly higher concentrations in L-Lake sediments than sediments from the reference sites.

  20. Comparative analysis of core drilling and rotary drilling in volcanic terrane

    SciTech Connect (OSTI)

    Flynn, T.; Trexler, D.T.; Wallace, R.H. Jr.

    1987-04-01

    Initially, the goal of this report is to compare and contrast penetration rates of rotary-mud drilling and core drilling in young volcanic terranes. It is widely recognized that areas containing an abundance of recent volcanic rocks are excellent targets for geothermal resources. Exploration programs depend heavily upon reliable subsurface information, because surface geophysical methods may be ineffective, inconclusive, or both. Past exploration drilling programs have mainly relied upon rotary-mud rigs for virtually all drilling activity. Core-drilling became popular several years ago, because it could deal effectively with two major problems encountered in young volcanic terranes: very hard, abrasive rock and extreme difficulty in controlling loss of circulation. In addition to overcoming these difficulties, core-drilling produced subsurface samples (core) that defined lithostratigraphy, structure and fractures far better than drill-chips. It seemed that the only negative aspect of core drilling was cost. The cost-per-foot may be two to three times higher than an ''initial quote'' for rotary drilling. In addition, penetration rates for comparable rock-types are often much lower for coring operations. This report also seeks to identify the extent of wireline core drilling (core-drilling using wireline retrieval) as a geothermal exploration tool. 25 refs., 21 figs., 13 tabs.

  1. Code System for the Analysis of Material Test Reactor (MTR) Cores.

    Energy Science and Technology Software Center (OSTI)

    1995-03-24

    Version 00 The RETRAC code uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behavior under transient or accident conditions. The reactor core is represented by a single equivalent unit cell composed of three regions: fuel, clad, and moderator (coolant).

  2. High Flux Isotope Reactor Core Analysis-Challenges and Recent Enhancements in Modeling and Simulation

    SciTech Connect (OSTI)

    Ilas, Germina

    2016-01-01

    A concerted effort over the past few years has focused on enhancing the core depletion models for the High Flux Isotope Reactor (HFIR) as part of a comprehensive study for designing a HFIR core that would use low-enriched uranium (LEU) fuel. A HFIR core depletion model that is based on current state-of-the-art methods and nuclear data was needed for use as a reference for the design of an LEU fuel for HFIR and to improve the basis for analyses that support HFIR s current operation with high-enriched uranium (HEU) fuel. This paper summarizes the recent improvements in modeling and simulation for HFIR core analyses, with a focus on core depletion models.

  3. Analysis of fuel options for the breakeven core configuration of the Advanced Recycling Reactor

    SciTech Connect (OSTI)

    Stauff, N.E.; Klim, T.K.; Taiwo, T.A.; Fiorina, C.; Franceschini, F.

    2013-07-01

    A trade-off study is performed to determine the impacts of various fuel forms on the core design and core physics characteristics of the sodium-cooled Toshiba- Westinghouse Advanced Recycling Reactor (ARR). The fuel forms include oxide, nitride, and metallic forms of U and Th. The ARR core configuration is redesigned with driver and blanket regions in order to achieve breakeven fissile breeding performance with the various fuel types. State-of-the-art core physics tools are used for the analyses. In addition, a quasi-static reactivity balance approach is used for a preliminary comparison of the inherent safety performances of the various fuel options. Thorium-fueled cores exhibit lower breeding ratios and require larger blankets compared to the U-fueled cores, which is detrimental to core compactness and increases reprocessing and manufacturing requirements. The Th cores also exhibit higher reactivity swings through each cycle, which penalizes reactivity control and increases the number of control rods required. On the other hand, using Th leads to drastic reductions in void and coolant expansion coefficients of reactivity, with the potential for enhancing inherent core safety. Among the U-fueled ARR cores, metallic and nitride fuels result in higher breeding ratios due to their higher heavy metal densities. On the other hand, oxide fuels provide a softer spectrum, which increases the Doppler effect and reduces the positive sodium void worth. A lower fuel temperature is obtained with the metallic and nitride fuels due to their higher thermal conductivities and compatibility with sodium bonds. This is especially beneficial from an inherent safety point of view since it facilitates the reactor cool-down during loss of power removal transients. The advantages in terms of inherent safety of nitride and metallic fuels are maintained when using Th fuel. However, there is a lower relative increase in heavy metal density and in breeding ratio going from oxide to metallic

  4. Fukushima Daiichi Unit 1 Uncertainty Analysis-Exploration of Core Melt Progression Uncertain Parameters-Volume II.

    SciTech Connect (OSTI)

    Denman, Matthew R.; Brooks, Dusty Marie

    2015-08-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysi s (UA) on the Fukushima Daiichi unit (1F1) accident progression wit h the MELCOR code. Volume I of the 1F1 UA discusses the physical modeling details and time history results of the UA. Volume II of the 1F1 UA discusses the statistical viewpoint. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). The goal of this work was to perform a focused evaluation of uncertainty in core damage progression behavior and its effect on key figures - of - merit (e.g., hydrogen production, fraction of intact fuel, vessel lower head failure) and in doing so assess the applicability of traditional sensitivity analysis techniques .

  5. Core Analysis At Blue Mountain Geothermal Area (U.S. Geological...

    Open Energy Info (EERE)

    1 and 46 samples from Deep Blue No. 2. The diameter of the core samples are 6.4 cm. Density, porosity, and rock type information was recorded. The samples contain Jurassic and...

  6. Sedimentologic analysis of cores from the upper Triassic Chinle formation and the lower permian cutler formation, Lisbon Valley, Utah. (Chapter E)

    SciTech Connect (OSTI)

    Dubiel, R.F.; Brown, J.L.

    1993-12-31

    Five uranium exploration cores from Lisbon Valley in the Paradox Basin of southeastern Utah provide examples of sedimentary structures and lithofacies from the Lower Permian Cutler Formation and the overlying Moss Back Member of the Upper Triassic Chinle Formation. These five cores record eolian and fluvial sedimentary structures and lithofacies sequences not well preserved in outcrops, they provide the basis for interpretation and comparison of depositional environments from lithofacies analysis in core and outcrop studies, and they establish the sedimentologic background for future petrographic and geochemical research on cores and outcrops from the Lisbon Valley area.

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

    SciTech Connect (OSTI)

    2014-10-01

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

  8. Performance analysis of distributed symmetric sparse matrix vector multiplication algorithm for multi-core architectures

    SciTech Connect (OSTI)

    Oryspayev, Dossay; Aktulga, Hasan Metin; Sosonkina, Masha; Maris, Pieter; Vary, James P.

    2015-07-14

    In this article, sparse matrix vector multiply (SpMVM) is an important kernel that frequently arises in high performance computing applications. Due to its low arithmetic intensity, several approaches have been proposed in literature to improve its scalability and efficiency in large scale computations. In this paper, our target systems are high end multi-core architectures and we use messaging passing interface + open multiprocessing hybrid programming model for parallelism. We analyze the performance of recently proposed implementation of the distributed symmetric SpMVM, originally developed for large sparse symmetric matrices arising in ab initio nuclear structure calculations. We also study important features of this implementation and compare with previously reported implementations that do not exploit underlying symmetry. Our SpMVM implementations leverage the hybrid paradigm to efficiently overlap expensive communications with computations. Our main comparison criterion is the "CPU core hours" metric, which is the main measure of resource usage on supercomputers. We analyze the effects of topology-aware mapping heuristic using simplified network load model. Furthermore, we have tested the different SpMVM implementations on two large clusters with 3D Torus and Dragonfly topology. Our results show that the distributed SpMVM implementation that exploits matrix symmetry and hides communication yields the best value for the "CPU core hours" metric and significantly reduces data movement overheads.

  9. Performance analysis of distributed symmetric sparse matrix vector multiplication algorithm for multi-core architectures

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

    Oryspayev, Dossay; Aktulga, Hasan Metin; Sosonkina, Masha; Maris, Pieter; Vary, James P.

    2015-07-14

    In this article, sparse matrix vector multiply (SpMVM) is an important kernel that frequently arises in high performance computing applications. Due to its low arithmetic intensity, several approaches have been proposed in literature to improve its scalability and efficiency in large scale computations. In this paper, our target systems are high end multi-core architectures and we use messaging passing interface + open multiprocessing hybrid programming model for parallelism. We analyze the performance of recently proposed implementation of the distributed symmetric SpMVM, originally developed for large sparse symmetric matrices arising in ab initio nuclear structure calculations. We also study important featuresmore¬†¬Ľ of this implementation and compare with previously reported implementations that do not exploit underlying symmetry. Our SpMVM implementations leverage the hybrid paradigm to efficiently overlap expensive communications with computations. Our main comparison criterion is the "CPU core hours" metric, which is the main measure of resource usage on supercomputers. We analyze the effects of topology-aware mapping heuristic using simplified network load model. Furthermore, we have tested the different SpMVM implementations on two large clusters with 3D Torus and Dragonfly topology. Our results show that the distributed SpMVM implementation that exploits matrix symmetry and hides communication yields the best value for the "CPU core hours" metric and significantly reduces data movement overheads.¬ę¬†less

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

    Energy Science and Technology Software Center (OSTI)

    2014-10-01

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

  11. Benchmark analysis of high temperature engineering test reactor core using McCARD code

    SciTech Connect (OSTI)

    Jeong, Chang Joon; Jo, Chang Keun; Lee, Hyun Chul; Noh, Jae Man

    2013-07-01

    A benchmark calculation has been performed for a startup core physics test of Japan's High Temperature Engineering Test Reactor (HTTR). The calculation is carried out by the McCARD code, which adopts the Monte Carlo method. The cross section library is ENDF-B/VII.0. The fuel cell is modeled by the reactivity-equivalent physical transform (RPT) method. Effective multiplication factors with different numbers of fuel columns have been analyzed. The calculation shows that the HTTR becomes critical with 19 fuel columns with an excess reactivity of 0.84% őĒk/k. The discrepancies between the measurements and Monte Carlo calculations are 2.2 and 1.4 % őĒk/k for 24 and 30 columns, respectively. The reasons for the discrepancy are thought to be the current version of cross section library and the impurity in the graphite which is represented by the boron concentration. In the future, the depletion results will be proposed for further benchmark calculations. (authors)

  12. Analysis of fractures in volcanic cores from Pahute Mesa, Nevada Test Site

    SciTech Connect (OSTI)

    Drellack, S.L. Jr.; Prothro, L.B.; Roberson, K.E.

    1997-09-01

    The Nevada Test Site (NTS), located in Nye County, southern Nevada, was the location of 828 announced underground nuclear tests, conducted between 1951 and 1992. Approximately one-third of these tests were detonated near or below the water table. An unavoidable consequence of these testing activities was introducing radionuclides into the subsurface environment, impacting groundwater. Groundwater flows beneath the NTS almost exclusively through interconnected natural fractures in carbonate and volcanic rocks. Information about these fractures is necessary to determine hydrologic parameters for future Corrective Action Unit (CAU)-specific flow and transport models which will be used to support risk assessment calculations for the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Underground Test Area (UGTA) remedial investigation. Fracture data are critical in reducing the uncertainty of the predictive capabilities of CAU-specific models because of their usefulness in generating hydraulic conductivity values and dispersion characteristics used in transport modeling. Specifically, fracture aperture and density (spacing) are needed to calculate the permeability anisotropy of the formations. Fracture mineralogy information is used qualitatively to evaluate diffusion and radionuclide retardation potential in transport modeling. All these data can best be collected through examination of core samples.

  13. Analysis of Advanced Fuel Assemblies and Core Designs for the Current and Next Generations of LWRs

    SciTech Connect (OSTI)

    Ragusa, Jean; Vierow, Karen

    2011-09-01

    The objective of the project is to design and analyze advanced fuel assemblies for use in current and future light water reactors and to assess their ability to reduce the inventory of transuranic elements, while preserving operational safety. The reprocessing of spent nuclear fuel can delay or avoid the need for a second geological repository in the US. Current light water reactor fuel assembly designs under investigation could reduce the plutonium inventory of reprocessed fuel. Nevertheless, these designs are not effective in stabilizing or reducing the inventory of minor actinides. In the course of this project, we developed and analyzed advanced fuel assembly designs with improved thermal transmutation capability regarding transuranic elements and especially minor actinides. These designs will be intended for use in thermal spectrum (e.g., current and future fleet of light water reactors in the US). We investigated various fuel types, namely high burn-up advanced mixed oxides and inert matrix fuels, in various geometrical designs that are compliant with the core internals of current and future light water reactors. Neutronic/thermal hydraulic effects were included. Transmutation efficiency and safety parameters were used to rank and down-select the various designs.

  14. Geomechanical testing of Bayou Choctaw 102B core for SPR analysis

    SciTech Connect (OSTI)

    Ingraham, Mathew Duffy; Broome, Scott Thomas; Bauer, Stephen J.; Barrow, Perry Carl; Flint, Gregory Mark

    2014-02-01

    A laboratory testing program was developed to examine the short-term mechanical and time-dependent (creep) behavior of salt from the Bayou Choctaw Salt Dome. This report documents the test methodologies, and constitutive properties inferred from tests performed. These are used to extend our understanding of the mechanical behavior of the Bayou Choctaw domal salt and provide a data set for numerical analyses. The resulting information will be used to support numerical analyses of the current state of the Bayou Choctaw Dome as it relates to its crude oil storage function as part of the US Strategic Petroleum Reserve. Core obtained from Drill Hole BC-102B was tested under creep and quasi-static constant mean stress axisymmetric compression, and constant mean stress axisymmetric extension conditions. Creep tests were performed at 100 degrees Fahrenheit, and the axisymmetric tests were performed at ambient temperatures (72-78 degrees Fahrenheit). The testing performed indicates that the dilation criterion is pressure and stress state dependent. It was found that as the mean stress increases, the shear stress required to cause dilation increases. The results for this salt are reasonably consistent with those observed for other domal salts. Also it was observed that tests performed under extensile conditions required consistently lower shear stress to cause dilation for the same mean stress, which is consistent with other domal salts. Young's moduli ranged from 3.95 x 106 to 8.51 x 106 psi with an average of 6.44 x 106 psi, with Poisson's ratios ranging from 0.10 to 0.43 with an average of 0.30. Creep testing indicates that the BC salt is intermediate in creep resistance when compared with other bedded and domal salt steady-state behavior.

  15. Paleo-Climate and Glaciological Reconstruction in Central Asia through the Collection and Analysis of Ice Cores and Instrumental Data from the Tien Shan

    SciTech Connect (OSTI)

    Vladimir Aizen; Donald Bren; Karl Kreutz; Cameron Wake

    2001-05-30

    While the majority of ice core investigations have been undertaken in the polar regions, a few ice cores recovered from carefully selected high altitude/mid-to-low latitude glaciers have also provided valuable records of climate variability in these regions. A regional array of high resolution, multi-parameter ice core records developed from temperate and tropical regions of the globe can be used to document regional climate and environmental change in the latitudes which are home to the vase majority of the Earth's human population. In addition, these records can be directly compared with ice core records available from the polar regions and can therefore expand our understanding of inter-hemispheric dynamics of past climate changes. The main objectives of our paleoclimate research in the Tien Shan mountains of middle Asia combine the development of detailed paleoenvironmental records via the physical and chemical analysis of ice cores with the analysis of modern meteorological and hydrological data. The first step in this research was the collection of ice cores from the accumulation zone of the Inylchek Glacier and the collection of meteorological data from a variety of stations throughout the Tien Shan. The research effort described in this report was part of a collaborative effort with the United State Geological Survey's (USGS) Global Environmental Research Program which began studying radionuclide deposition in mid-latitude glaciers in 1995.

  16. High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor With Results from FY-2011 Activities

    SciTech Connect (OSTI)

    Michael A. Pope

    2011-10-01

    The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450

  17. Prognostic Importance of Gleason 7 Disease Among Patients Treated With External Beam Radiation Therapy for Prostate Cancer: Results of a Detailed Biopsy Core Analysis

    SciTech Connect (OSTI)

    Spratt, Daniel E.; Zumsteg, Zach; Ghadjar, Pirus; Pangasa, Misha; Pei, Xin; Fine, Samson W.; Yamada, Yoshiya; Kollmeier, Marisa; Zelefsky, Michael J.

    2013-04-01

    Purpose: To analyze the effect of primary Gleason (pG) grade among a large cohort of Gleason 7 prostate cancer patients treated with external beam radiation therapy (EBRT). Methods and Materials: From May 1989 to January 2011, 1190 Gleason 7 patients with localized prostate cancer were treated with EBRT at a single institution. Of these patients, 613 had a Gleason 7 with a minimum of a sextant biopsy with nonfragmented cores and full biopsy core details available, including number of cores of cancer involved, percentage individual core involvement, location of disease, bilaterality, and presence of perineural invasion. Median follow-up was 6 years (range, 1-16 years). The prognostic implication for the following outcomes was analyzed: biochemical recurrence-free survival (bRFS), distant metastasis-free survival (DMFS), and prostate cancer-specific mortality (PCSM). Results: The 8-year bRFS rate for pG3 versus pG4 was 77.6% versus 61.3% (P<.0001), DMFS was 96.8% versus 84.3% (P<.0001), and PCSM was 3.7% versus 8.1% (P=.002). On multivariate analysis, pG4 predicted for significantly worse outcome in all parameters. Location of disease (apex, base, mid-gland), perineural involvement, maximum individual core involvement, and the number of Gleason 3+3, 3+4, or 4+3 cores did not predict for distant metastases. Conclusions: Primary Gleason grade 4 independently predicts for worse bRFS, DMFS, and PCSM among Gleason 7 patients. Using complete core information can allow clinicians to utilize pG grade as a prognostic factor, despite not having the full pathologic details from a prostatectomy specimen. Future staging and risk grouping should investigate the incorporation of primary Gleason grade when complete biopsy core information is used.

  18. Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1998-02-01

    This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall scraping samples from the Gunite and Associated Tanks. These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge, Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping sampler and/or a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US Environmental Protection Agency guidance, was applied to identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions of a strontium concrete diffusion model, (2) estimate the amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the wall cleaning system. This revision eliminates wall-scraping samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect sufficient material for analysis.

  19. Coupled 3D-neutronics / thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core

    SciTech Connect (OSTI)

    Sun, K.; Chenu, A.; Mikityuk, K.; Krepel, J.; Chawla, R.

    2012-07-01

    The core behaviour of a large (3600 MWth) sodium-cooled fast reactor (SFR) is investigated in this paper with the use of a coupled TRACE/PARCS model. The SFR neutron spectrum is characterized by several performance advantages, but also leads to one dominating neutronics drawback - a positive sodium void reactivity. This implies a positive reactivity effect when sodium coolant is removed from the core. In order to evaluate such feedback in terms of the dynamics, a representative unprotected loss-of-flow (ULOF) transient, i.e. flow run-down without SCRAM in which sodium boiling occurs, is analyzed. Although analysis of a single transient cannot allow general conclusions to be drawn, it does allow better understanding of the underlying physics and can lead to proposals for improving the core response during such an accident. The starting point of this study is the reference core design considered in the framework of the Collaborative Project on the European Sodium Fast Reactor (CP-ESFR). To reduce the void effect, the core has been modified by introducing an upper sodium plenum (along with a boron layer) and by reducing the core height-to-diameter ratio. For the ULOF considered, a sharp increase in core power results in melting of the fuel in the case of the reference core. In the modified core, a large dryout leads to melting of the clad. It seems that, for the hypothetical event considered, fuel failure cannot be avoided with just improvement of the neutronics design; therefore, thermal-hydraulics optimization has been considered. An innovative assembly design is proposed to prevent sodium vapour blocking the fuel channel. This results in preventing a downward propagation of the sodium boiling to the core center, thus limiting it to the upper region. Such a void map introduces a negative coolant density reactivity feedback, which dominates the total reactivity change. As a result, the power level and the fuel temperature are effectively reduced, and a large dryout

  20. Development code for sensitivity and uncertainty analysis of input on the MCNPX for neutronic calculation in PWR core

    SciTech Connect (OSTI)

    Hartini, Entin Andiwijayakusuma, Dinan

    2014-09-30

    This research was carried out on the development of code for uncertainty analysis is based on a statistical approach for assessing the uncertainty input parameters. In the butn-up calculation of fuel, uncertainty analysis performed for input parameters fuel density, coolant density and fuel temperature. This calculation is performed during irradiation using Monte Carlo N-Particle Transport. The Uncertainty method based on the probabilities density function. Development code is made in python script to do coupling with MCNPX for criticality and burn-up calculations. Simulation is done by modeling the geometry of PWR terrace, with MCNPX on the power 54 MW with fuel type UO2 pellets. The calculation is done by using the data library continuous energy cross-sections ENDF / B-VI. MCNPX requires nuclear data in ACE format. Development of interfaces for obtaining nuclear data in the form of ACE format of ENDF through special process NJOY calculation to temperature changes in a certain range.

  1. Modeling & Analysis

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

    Facilities, Modeling, Modeling, Modeling & Analysis, Modeling & Analysis, Renewable Energy, Research & Capabilities, Wind Energy, Wind News Virtual LIDAR Model Helps Researchers ...

  2. Performance analysis of distributed symmetric sparse matrix vector multiplication algorithm for multi-core architectures. Analysis of Distributed Sparse Symmetric Algorithm

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

    Oryspayev, Dossay; Aktulga, Hasan Metin; Sosonkina, Masha; Maris, Pieter; Vary, James P.

    2015-07-14

    Sparse matrix vector multiply (SpMVM) is an important kernel that frequently arises in high performance computing applications. Due to its low arithmetic intensity, several approaches have been proposed in literature to improve its scalability and efficiency in large scale computations. In this paper, our target systems are high end multi-core architectures and we use messaging passing interface + open multiprocessing hybrid programming model for parallelism. We analyze the performance of recently proposed implementation of the distributed symmetric SpMVM, originally developed for large sparse symmetric matrices arising in ab initio nuclear structure calculations. We also study important features of this implementationmore†Ľand compare with previously reported implementations that do not exploit underlying symmetry. Our SpMVM implementations leverage the hybrid paradigm to efficiently overlap expensive communications with computations. Our main comparison criterion is the ĎCPU core hoursí metric, which is the main measure of resource usage on supercomputers. We analyze the effects of topology-aware mapping heuristic using simplified network load model. Furthermore, we have tested the different SpMVM implementations on two large clusters with 3D Torus and Dragonfly topology. Our results show that the distributed SpMVM implementation that exploits matrix symmetry and hides communication yields the best value for the ĎCPU core hoursí metric and significantly reduces data movement overheads.ę†less

  3. Core description and analysis using X-radiography and cat-scanning: examples from Sacramento and San Joaquin basins, California

    SciTech Connect (OSTI)

    Fischer, P.J.; Setiawan, J.; Cherven, V.B.

    1986-04-01

    X-radiographs of cores from Forbes deep basin sands, the tar-saturated paralic sands of the Temblor and the Tulare fluvial sands and silts, as well as fractured siliceous units (the Monterey Formation and equivalents) reveal geologic features that are either not visible or barely discernible to the naked eye. These features include changes in grain size, grading, ripple lamination to cross-bedding, cyclic couplets in tidal sequences, bioturbation and burrowing, and fracture patterns and filling. Forbes core x-radiography from the northern Sacramento basin clearly shows a sequence of thinly bedded sand and mudstones that are microripple cross-laminated. Partial Bouma sequences (Ta-b or Tb with Ta-c) are characteristic of the thickly bedded sands below the ripple-laminated units. Cyclic sequences of mud-turbidites and finely laminated, very fine-grained sands to coarse silts characterize a sand-poor sequence that overlies a massive to indistinctly thin-bedded sand. Most of these features described above are barely discernible without x-radiography, yet all provide major input to the interpretation of the depositional environment of the Forbes Formation, as well as information regarding reservoir continuity. Tar or heavy-oil saturation of cores can be a severe problem when cores are examined. In a Tulare Formation core sequence that was x-radiographed, essentially no bedding was visible, even using UV photography. However, extensive fluvial cross-bedding throughout the core was revealed by the x-radiography. A similar, heavy oil masking problem in a Temblor Formation core near East Coalinga was also resolved by the x-ray technique. The reservoir is divided into multiple, thin, tidal couplets (4-6 in.) of oil-saturated sand separated by 1 to 3 in. thick mudstones.

  4. Tank Vapor Sampling and Analysis Data Package for Tank 241-Z-361 Sampled 09/22/1999 and 09/271999 During Sludge Core Removal

    SciTech Connect (OSTI)

    VISWANATH, R.S.

    1999-12-29

    This data package presents sampling data and analytical results from the September 22 and 27, 1999, headspace vapor sampling of Hanford Site Tank 241-2-361 during sludge core removal. The Lockheed Martin Hanford Corporation (LMHC) sampling team collected the samples and Waste Management Laboratory (WML) analyzed the samples in accordance with the requirements specified in the 241-2361 Sludge Characterization Sampling and Analysis Plan, (SAP), HNF-4371, Rev. 1, (Babcock and Wilcox Hanford Corporation, 1999). Six SUMMA{trademark} canister samples were collected on each day (1 ambient field blank and 5 tank vapor samples collected when each core segment was removed). The samples were radiologically released on September 28 and October 4, 1999, and received at the laboratory on September 29 and October 6, 1999. Target analytes were not detected at concentrations greater than their notification limits as specified in the SAP. Analytical results for the target analytes and tentatively identified compounds (TICs) are presented in Section 2.2.2 starting on page 2B-7. Three compounds identified for analysis in the SAP were analyzed as TICs. The discussion of this modification is presented in Section 2.2.1.2.

  5. CORCON-MOD3: An integrated computer model for analysis of molten core-concrete interactions. User`s manual

    SciTech Connect (OSTI)

    Bradley, D.R.; Gardner, D.R.; Brockmann, J.E.; Griffith, R.O.

    1993-10-01

    The CORCON-Mod3 computer code was developed to mechanistically model the important core-concrete interaction phenomena, including those phenomena relevant to the assessment of containment failure and radionuclide release. The code can be applied to a wide range of severe accident scenarios and reactor plants. The code represents the current state of the art for simulating core debris interactions with concrete. This document comprises the user`s manual and gives a brief description of the models and the assumptions and limitations in the code. Also discussed are the input parameters and the code output. Two sample problems are also given.

  6. Estimation of SX Farm Vadose Zone CS-137 Inventories from Geostatistical Analysis of Drywell and Soil Core Data

    SciTech Connect (OSTI)

    KNEPP, A.J.

    2000-06-02

    This report provides an estimation of the Cs-137 inventories in the soil under the SX Tank Farm based on measurements obtained from drywell and soil cores. The Cs-137 inventories are estimated separately for distinct volumes of soil associated etc.

  7. Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor

    SciTech Connect (OSTI)

    B. Boer; A. M. Ougouag

    2010-09-01

    The Deep-Burn (DB) concept focuses on the destruction of transuranic nuclides from used light water reactor fuel. These transuranic nuclides are incorporated into TRISO coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes between passes. In particular, the concept does not call for reprocessing of the fuel between passes. In principle, the DB pebble bed concept employs the same reactor designs as the presently envisioned low-enriched uranium core designs, such as the 400 MWth Pebble Bed Modular Reactor (PBMR-400). Although it has been shown in the previous Fiscal Year (2009) that a PuO2 fueled pebble bed reactor concept is viable, achieving a high fuel burnup, while remaining within safety-imposed prescribed operational limits for fuel temperature, power peaking and temperature reactivity feedback coefficients for the entire temperature range, is challenging. The presence of the isotopes 239-Pu, 240-Pu and 241-Pu that have resonances in the thermal energy range significantly modifies the neutron thermal energy spectrum as compared to a Ēstandard,Ē UO2-fueled core. Therefore, the DB pebble bed core exhibits a relatively hard neutron energy spectrum. However, regions within the pebble bed that are near the graphite reflectors experience a locally softer spectrum. This can lead to power and temperature peaking in these regions. Furthermore, a shift of the thermal energy spectrum with increasing temperature can lead to increased absorption in the resonances of the fissile Pu isotopes. This can lead to a positive temperature reactivity coefficient for the graphite moderator under certain operating conditions. The effort of this task in FY 2010 has focused on the optimization of the core to maximize the pebble discharge burnup

  8. Hydrogen Analysis

    Broader source: Energy.gov [DOE]

    Presentation on Hydrogen Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  9. Hanford 100-N Area In Situ Apatite and Phosphate Emplacement by Groundwater and Jet Injection: Geochemical and Physical Core Analysis

    SciTech Connect (OSTI)

    Szecsody, James E.; Vermeul, Vincent R.; Fruchter, Jonathan S.; Williams, Mark D.; Rockhold, Mark L.; Qafoku, Nikolla; Phillips, Jerry L.

    2010-07-01

    The purpose of this study is to evaluate emplacement of phosphate into subsurface sediments in the Hanford Site 100-N Area by two different technologies: groundwater injection of a Ca-citrate-PO4 solution and water-jet injection of sodium phosphate and/or fish-bone apatite. In situ emplacement of phosphate and apatite adsorbs, then incorporates Sr-90 into the apatite structure by substitution for calcium. Overall, both technologies (groundwater injection of Ca-citrate-PO4) and water-jet injection of sodium phosphate/fish-bone apatite) delivered sufficient phosphate to subsur¨face sediments in the 100-N Area. Over years to decades, additional Sr-90 will incorporate into the apatite precipitate. Therefore, high pressure water jetting is a viable technology to emplace phosphate or apatite in shallow subsurface sediments difficult to emplace by Ca-citrate-PO4 groundwater injections, but further analysis is needed to quantify the relevant areal extent of phosphate deposition (in the 5- to 15-ft distance from injection points) and cause of the high deposition in finer grained sediments.

  10. Analysis and comparison of CVS-ADC approaches up to third order for the calculation of core-excited states

    SciTech Connect (OSTI)

    Wenzel, Jan Holzer, Andre; Wormit, Michael; Dreuw, Andreas

    2015-06-07

    The extended second order algebraic-diagrammatic construction (ADC(2)-x) scheme for the polarization operator in combination with core-valence separation (CVS) approximation is well known to be a powerful quantum chemical method for the calculation of core-excited states and the description of X-ray absorption spectra. For the first time, the implementation and results of the third order approach CVS-ADC(3) are reported. Therefore, the CVS approximation has been applied to the ADC(3) working equations and the resulting terms have been implemented efficiently in the adcman program. By treating the őĪ and ő≤ spins separately from each other, the unrestricted variant CVS-UADC(3) for the treatment of open-shell systems has been implemented as well. The performance and accuracy of the CVS-ADC(3) method are demonstrated with respect to a set of small and middle-sized organic molecules. Therefore, the results obtained at the CVS-ADC(3) level are compared with CVS-ADC(2)-x values as well as experimental data by calculating complete basis set limits. The influence of basis sets is further investigated by employing a large set of different basis sets. Besides the accuracy of core-excitation energies and oscillator strengths, the importance of cartesian basis functions and the treatment of orbital relaxation effects are analyzed in this work as well as computational timings. It turns out that at the CVS-ADC(3) level, the results are not further improved compared to CVS-ADC(2)-x and experimental data, because the fortuitous error compensation inherent in the CVS-ADC(2)-x approach is broken. While CVS-ADC(3) overestimates the core excitation energies on average by 0.61% ¬Ī 0.31%, CVS-ADC(2)-x provides an averaged underestimation of ‚ąí0.22% ¬Ī 0.12%. Eventually, the best agreement with experiments can be achieved using the CVS-ADC(2)-x method in combination with a diffuse cartesian basis set at least at the triple-ő∂ level.

  11. BWR Vessel and Internals Project Removal and Analysis of Material Samples from Core Shroud and Top Guide at Susquehanna Unit 2

    SciTech Connect (OSTI)

    Howell, D; Haertel, T; Lindberg, J; Oliver, B; Greenwood, L

    2005-04-15

    Fast and thermal fluence were determined by a laboratory analysis of the samples. Fluence in the upper regions of the shroud (between the H1 and H2 welds) was substantially lower than that in the belt line region (near the H4 weld). Fluence in the top guide was significantly higher than fluence on the core shroud. As expected, helium concentrations were highest in regions where fluence was highest. Estimates of the initial boron concentration were similar to measurements made on materials removed from other reactors. A technical justification evaluated the acceptability of the sampling process with respect to structural consequences of material removal and to increased cracking susceptibility due to the as-left condition. It was determined that the sampling process was acceptable on both counts.

  12. Quantitative analysis of the x-ray diffraction intensities of undulated smectic phases in bent-core liquid crystals

    SciTech Connect (OSTI)

    Folcia, C. L.; Etxebarria, J.; Ortega, J.

    2007-07-15

    X-ray diffraction diagrams of undulated smectic phases in bent-core liquid crystals have been theoretically studied. The intensities of the reflections have been obtained for different layer modulations, and a general expression has been deduced for orthogonal cells in terms of the different harmonics of the distortion. The case of sinusoidal modulation is especially simple and has been studied also in oblique cells. High-quality x-ray measurements of three compounds reported in the literature have been analyzed as examples. In all cases it has been deduced that the modulation is sinusoidal and its amplitude has been easily obtained by fitting the experimental intensities. Equatorial (h0) reflections have been also considered to obtain information about the structure of defects at the maxima and minima of the undulation.

  13. NREL: Energy Analysis - Sustainability Analysis

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

    ... Life Cycle Assessment Harmonization Sustainable Biomass Resource Development and Use Renewable Energy on Contaminated Lands Technology Systems Analysis Geospatial Analysis Key ...

  14. NREL: Energy Analysis: Geospatial Analysis

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

    U.S. Renewable Energy Technical Potentials: A GIS-Based Analysis This study summarizes the ... (tools, maps, data): Dynamic Maps, GIS Data and Analysis Tools website provides ...

  15. Detailed Analysis of a Late-Phase Core-Melt Progression for the Evaluation of In-vessel Corium Retention

    SciTech Connect (OSTI)

    J. L. Rempe; R. J. Park; S. B. Kim; K. Y. Suh; F. B.Cheung

    2006-12-01

    Detailed analyses of a late-phase melt progression in the advanced power reactor (APR)1400 were completed to identify the melt and the thermal-hydraulic states of the in-vessel materials in the reactor vessel lower plenum at the time of reactor vessel failure to evaluate the candidate strategies for an in-vessel corium retention (IVR). Initiating events considered included high-pressure transients of a total loss of feed water (LOFW) and a station blackout (SBO) and low-pressure transients of a 0.0009-m2 small, 0.0093-m2 medium, and 0.0465-m2 large-break loss-of-coolant accident (LOCA) without safety injection. Best-estimate simulations for these low-probability events with conservative accident progression assumptions that lead to reactor vessel failure were performed by using the SCDAP/RELAP5/MOD3.3 computer code. The SCDAP/RELAP5/MOD3.3 results have shown that the pressurizer surge line failed before the reactor vessel failure, which results in a rapid decrease of the in-vessel pressure and a delay of the reactor vessel failure time of ~40 min in the high-pressure sequences of the total LOFW and the SBO transients. In all the sequences, ~80 to 90% of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. The maximum value of the volumetric heat source in the corium pool was estimated as 1.9 to 3.7 MW/m3. The corium temperature was ~2800 to 3400 K at the time of reactor vessel failure. The highest volumetric heat source sequence is predicted for the 0.0465-m2 large-break LOCA without safety injection in the APR1400, because this sequence leads to an early reactor vessel failure.

  16. Multi-core Performance Analysis

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

    Scaling on Petascale- class Systems Cray XE/XT Architecture, System Software, and Scientific Libraries 34 CRAY XE/XT SYSTEM ARCHITECTURE 35 DDR3 Channel DDR3 Channel DDR3 Channel DDR3 Channel DDR3 Channel DDR3 Channel DDR3 Channel DDR3 Channel 6MB L3 Cache Greyhound Greyhound Greyhound Greyhound Greyhound Greyhound 6MB L3 Cache Greyhound Greyhound Greyhound Greyhound Greyhound Greyhound 6MB L3 Cache Greyhound Greyhound Greyhound Greyhound Greyhound Greyhound 6MB L3 Cache Greyhound Greyhound

  17. Multi-core Performance Analysis

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

    Extreme Scaling on Petascale-class Systems Cray XE/XT Porting, Scaling, and Optimization 46 VECTORIZATION: LOOP ORDER MATTERS 47 55. 1 ii = 0 56. 1 2-----------< do b = abmin, abmax 57. 1 2 3---------< do j=ijmin, ijmax 58. 1 2 3 ii = ii+1 59. 1 2 3 jj = 0 60. 1 2 3 4-------< do a = abmin, abmax 61. 1 2 3 4 r8----< do i = ijmin, ijmax 62. 1 2 3 4 r8 jj = jj+1 63. 1 2 3 4 r8 f5d(a,b,i,j) = f5d(a,b,i,j) + tmat7(ii,jj) 64. 1 2 3 4 r8 f5d(b,a,i,j) = f5d(b,a,i,j) - tmat7(ii,jj) 65. 1 2 3

  18. Microalgae Analysis

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

    Microalgae Analysis March 24, 2015 Algal Feedstocks Review Mark Wigmosta Pacific Northwest National Laboratory This presentation does not contain any proprietary, confidential, or ...

  19. Modeling & Analysis

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

    News & Events, Renewable Energy, Research & Capabilities, Systems Analysis, Water Power Wave-Energy-Device Modeling: Developing A 1:17 Scaled Model Many theoretical studies show ...

  20. Environmental Analysis

    Broader source: Energy.gov [DOE]

    Environmental Analysis is used by the Program to quantify the environmental impacts of hydrogen technologies. Specifically, life cycle assessment is used to identify and evaluate the emissions,...

  1. NREL: Energy Analysis - Market Analysis

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

    Market Analysis The laboratory's market analysis helps increase the use of renewable energy (RE) and energy efficiency (EE) technologies in the marketplace by providing strategic information to stakeholders interested in rapidly changing electricity markets. Our high-quality and objective crosscutting assessments and analysis support informed decision making. Primary focuses include: Energy Technology/Program Cost, Performance, and Market Data The Office of Energy Efficiency and Renewable Energy

  2. NREL: Energy Analysis - Policy Analysis

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

    The laboratory's policy analysis evaluates policies that can advance-or provide alternatives to-renewable energy technologies in meeting national goals. Federal Policy NREL's ...

  3. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal floods during mid-loop operations. Volume 4

    SciTech Connect (OSTI)

    Kohut, P.

    1994-07-01

    The major objective of the Surry internal flood analysis was to provide an improved understanding of the core damage scenarios arising from internal flood-related events. The mean core damage frequency of the Surry plant due to internal flood events during mid-loop operations is 4.8E-06 per year, and the 5th and 95th percentiles are 2.2E-07 and 1.8E-05 per year, respectively. Some limited sensitivity calculations were performed on three plant improvement options. The most significant result involves modifications of intake-level structure on the canal, which reduced core damage frequency contribution from floods in mid-loop by about 75%.

  4. The SDAV Software Frameworks for Visualization and Analysis on...

    Office of Scientific and Technical Information (OSTI)

    Software Frameworks for Visualization and Analysis on Next-Generation Multi-Core and Many-Core Architectures. Citation Details In-Document Search Title: The SDAV Software ...

  5. Program Analysis

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

    and abate nearly 20,000 mmt of CO2 through 2050. EE portfolio analysis wNEMS+MARKAL (Frances Wood, OnLocation, and Chip Friley, BNL) Heavily leverages ANL's Autonomie Tool...

  6. Financial Analysis

    Broader source: Energy.gov [DOE]

    The first step in financing a street lighting retrofit is a detailed financial analysis. Because street lighting systems are designed to last ten or twenty years, or even longer, all aspects of first costs, ongoing expenses, and long-term savings are important. While a preliminary or first-level analysis can be used to determine such things as simple payback, rate of return, and cost of light, the results may neglect a number of important economic considerations, such as the time value of money, additional savings and expenses and their relative timing, and future energy price escalations. Hence a first-level analysis does not typically provide the end user with sufficient details to make a fully informed decision. For this reason, the Illuminating Engineering Society (IES) recommends a full life cycle cost/benefit analysis (LCCBA).

  7. Supplement Analysis

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

    Supplement Analysis to the LCLS-ll Environmental Assessment, July. 2014 U.S. DEPARTMENT OF Office of *ENERGY 1 Science SLAG Site Office SLAC National Accelerator Laboratory 2575 Sand Hill Road, MS-8A Menlo Park, CA 94025 DATE: September 15, 2015 MEMORANDUM FOR: Paul Golan, Site Manager, SLAC Site Office THROUGH: James Elmore, ISC-OR NEPA Compliance Officer, Oak Ridge Office FROM: Mitzi Heard, NEPA Coornator, SLAC Site Office SUBJECT: Supplement Analysis to SLAC LCLS-I1 Environmental Assessment.

  8. NREL: Energy Analysis - Manufacturing Analysis

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

    Recent Publications "Economic Measurements of Polysilicon for the Photovoltaic Industry: Market Competition and Manufacturing Competitiveness" IEEE Journal of Photovoltaics Supply Chain and Blade Manufacturing Considerations in the Global Wind Industry Economic Development Impact of 1,000 MW of Wind Energy in Texas Manufacturing Analysis With world-class manufacturing analysis capabilities, NREL analyzes clean energy industry trends; cost, price, and performance trends; market and

  9. Fluid Lab Analysis | Open Energy Information

    Open Energy Info (EERE)

    Over Core Stress Paleomagnetic Measurements Petrography Analysis Rock Density X-Ray Diffraction (XRD) X-Ray Fluorescence (XRF) References No exploration activities found. Print...

  10. COMPETENCY MODEL ASSESSMENT DESIGN, ADMINISTRATION, AND ANALYSIS...

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

    and organizational workforce development use via gap analysis reporting A mapping of core, general, functional, and leadership competencies to various positions (Completed ...

  11. Analysis Repository

    SciTech Connect (OSTI)

    DOE

    2012-03-16

    The Analysis Repository is a compilation of analyses and analytical models relevant to assessing hydrogen fuel and fuel cell issues. Projects in the repository relate to: hydrogen production, delivery, storage, fuel cells, and hydrogen vehicle technology; hydrogen production feedstock cost and availability; electricity production, central and distributed; energy resource estimation and forecasting.

  12. Uncertainty Analysis

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

    Analysis - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear Energy

  13. Financial Analysis

    Energy Science and Technology Software Center (OSTI)

    2010-12-31

    This tool takes into account the net cost savings, implementation costs, and operations and maintenance costs of an energy conservation measure, as well as typical project lifetime and the relating discount and escalation rates. The result is a cash flow analysis over the project lifetime with calculations for simple payback, discounted payback, net present value, and savings to investment ratio. The tool also displays the results graphically.

  14. Polyculture Analysis

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

    Polyculture Analysis 24 March 2015 Deborah Newby, Ph.D. Idaho National Laboratory This presentation does not contain any proprietary, confidential, or otherwise restricted information Algal Feedstocks DOE Bioenergy Technologies Office (BETO) 2015 Project Peer Review Hub -- Sandia National Laboratories Oak Ridge National Laboratory Pacific Northwest National Laboratory 2 | Bioenergy Technologies Office Goal Statement (Hub) Challenge: * To contribute to meeting the Renewable Fuel Standard, DOE

  15. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage

    SciTech Connect (OSTI)

    Budnitz, R.J.; Davis, P.R.; Ravindra, M.K.; Tong, W.H.

    1994-08-01

    In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven projects have examined only accidents initiated by internal plant faults---so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10{sup {minus}7}/year.

  16. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendices F-H, Volume 2, Part 4

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

    1994-06-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

  17. Hazard Analysis Database report

    SciTech Connect (OSTI)

    Niemi, B.J.

    1997-08-12

    This document describes and defines the Hazard Analysis Database for the Tank Waste Remediation System Final Safety Analysis Report.

  18. An Innovative Three-Dimensional Heterogeneous Coarse-Mesh Transport Method for Advanced and Generation IV Reactor Core Analysis and Design

    SciTech Connect (OSTI)

    Farzad Rahnema

    2009-11-12

    This project has resulted in a highly efficient method that has been shown to provide accurate solutions to a variety of 2D and 3D reactor problems. The goal of this project was to develop (1) an accurate and efficient three-dimensional whole-core neutronics method with the following features: based sollely on transport theory, does not require the use of cross-section homogenization, contains a highly accurate and self-consistent global flux reconstruction procedure, and is applicable to large, heterogeneous reactor models, and to (2) create new numerical benchmark problems for code cross-comparison.

  19. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

    1994-06-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

  20. Analysis Methodologies | Department of Energy

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

    Systems Analysis ¬Ľ Analysis Methodologies Analysis Methodologies A spectrum of analysis methodologies are used in combination to provide a sound understanding of hydrogen and fuel cell systems and developing markets, as follows: Resource Analysis Technological Feasibility and Cost Analysis Environmental Analysis Delivery Analysis Infrastructure Development and Financial Analysis Energy Market Analysis In general, each methodology builds on previous efforts to quantify the benefits, drawbacks,

  1. Reactor hot spot analysis

    SciTech Connect (OSTI)

    Vilim, R.B.

    1985-08-01

    The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

  2. Forces in bolted joints: analysis methods and test results utilized...

    Office of Scientific and Technical Information (OSTI)

    nuclear core applications (LWBR Development Program) Citation Details In-Document Search Title: Forces in bolted joints: analysis methods and test results utilized for nuclear ...

  3. Compound and Elemental Analysis At Valles Caldera - Redondo Geothermal...

    Open Energy Info (EERE)

    (including from the VC-3 core hole) to study mineral abundances using X-ray powder diffraction analysis (XRD), examine specific mineral texturemorphology using Scanning electron...

  4. Compound and Elemental Analysis At Valles Caldera - Sulphur Springs...

    Open Energy Info (EERE)

    (including from the VC-3 core hole) to study mineral abundances using X-ray powder diffraction analysis (XRD), examine specific mineral texturemorphology using Scanning electron...

  5. Neutronics Design and Fuel Cycle Analysis of a High Conversion...

    Office of Scientific and Technical Information (OSTI)

    ... core height and improve neutron economy without the risk of a positive void coefficient. ... been well assessed and benchmarked for analysis of light water reactor systems. ...

  6. Clean Energy Policy Analysis: Impact Analysis of Potential Clean...

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

    Clean Energy Policy Analysis: Impact Analysis of Potential Clean Energy Policy Options for the Hawaii Clean Energy Initiative Clean Energy Policy Analysis: Impact Analysis of ...

  7. Category:Rock Lab Analysis | Open Energy Information

    Open Energy Info (EERE)

    Rock O Over Core Stress P Paleomagnetic Measurements Petrography Analysis R Rock Density Rock Lab Analysis X X-Ray Diffraction (XRD) X-Ray Fluorescence (XRF) Retrieved from...

  8. NREL: Energy Analysis - Solar Technology Analysis

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

    Solar Technology Analysis NREL conducts analysis to support research and development done by the Solar Energy Technologies Program in three major technology areas: concentrating solar power; solar electricity, also known as photovoltaics or PV; and solar heating and lighting. For example, in the area of photovoltaics, EERE's systems modeling and analysis activity rigorously assesses the performance, reliability, installed costs, and levelized energy costs (LECs) of a wide variety of flat-plate

  9. NREL: Energy Analysis - Geothermal Technology Analysis

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

    ... Biomass Buildings Electric Infrastructure Systems Energy Sciences Geothermal Hydrogen and Fuel Cells Solar Vehicles and Fuels Research Wind Geospatial Analysis Key Activities ...

  10. NREL: Energy Analysis - Wind Technology Analysis

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

    Grid Operational Impact Analysis The wind program will address the variable, normally uncontrollable nature of wind power plant output, and the additional needs that its operation ...

  11. Core Analysis At International Geothermal Area, Philippines ...

    Open Energy Info (EERE)

    Philippines. References Patrick Laney (2005) Federal Geothermal Research Program Update - Fiscal Year 2004 Additional References Retrieved from "http:en.openei.orgw...

  12. NREL: Innovation Impact - Analysis

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

    Analysis Menu Home Home Solar Solar Wind Wind Analysis Analysis Bioenergy Bioenergy Buildings Buildings Transportation Transportation Manufacturing Manufacturing Energy Systems Integration Energy Systems Integration Analysis at NREL Close NREL complements its scientific research with high-quality, credible, and technology-neutral analysis that spans the entire energy portfolio to inform policy and investment decisions. These studies help to illuminate what is possible and provide critical

  13. K Basin Hazard Analysis

    SciTech Connect (OSTI)

    PECH, S.H.

    2000-08-23

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Final Safety Analysis Report. This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  14. K Basins Hazard Analysis

    SciTech Connect (OSTI)

    WEBB, R.H.

    1999-12-29

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Safety Analysis Report (HNF-SD-WM-SAR-062, Rev.4). This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  15. Office of Analysis

    Broader source: Energy.gov [DOE]

    The Office of Analysis provides analysis of Department of Energy (DOE)-wide performance in protecting the public, the workers and the environment while performing the missions of DOE.

  16. Systems Analysis Workshop Purpose

    Broader source: Energy.gov [DOE]

    Presentation on SAW purpose to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  17. NETL: SOFC Systems Analysis

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

    Analysis NETL possesses strong systems analysis and policy support capabilities. Systems analysis support of the SOFC Program consists of conducting various energy analyses that provide input to decisions on issues such as national plans and programs, resource use, environmental and energy security policies, technology options for R&D programs and pathways to the commercialization and deployment of SOFC power systems. Here is a partial listing of SOFC systems analysis: Techno-Economic

  18. Sensitivity and Uncertainty Analysis

    Broader source: Energy.gov [DOE]

    Summary Notes from 15 November 2007 Generic Technical Issue Discussion on Sensitivity and Uncertainty Analysis and Model Support

  19. Economic Analysis of Policy Effects Analysis Platform

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

    Economic Analysis of Policy Effects Analysis Platform March 24, 2015 Jason Hansen, PhD Idaho National Laboratory This presentation does not contain any proprietary, confidential, or otherwise restricted information DOE Bioenergy Technologies Office (BETO) 2015 Project Peer Review 4.1.2.20 2 | Bioenergy Technologies Office * The goal of this project is to 1) identify risk factors in the biofuel supply system, 2) translate risk factors to implications, and 3) identify strategies and polices to

  20. NREL: Energy Analysis - Technology Systems Analysis

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

    Technology Systems Analysis NREL's Technology Systems Analysis examines RD&D areas in terms of potential costs, benefits, risks, uncertainties, and timeframes. The following pages provide information on specific technology areas: Biomass Building Electric Infrastructure Systems Energy Sciences Geothermal Hydrogen and Fuel Cells Solar Vehicles and Fuels Research Wind Key staff analyst Summary bios of staff expertise and interests Team Lead: Margaret Mann Administrative Support: Catherine

  1. Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel...

    Office of Environmental Management (EM)

    Models and Tools: Systems Analysis of Hydrogen and Fuel Cells Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel Cells The Fuel Cell Technologies Office's systems ...

  2. The Tariff Analysis Project: A Database and Analysis Platform...

    Open Energy Info (EERE)

    Tariff Analysis Project: A Database and Analysis Platform for Electricity Tariffs Jump to: navigation, search Tool Summary LAUNCH TOOL Name: The Tariff Analysis Project: A Database...

  3. Over Core Stress | Open Energy Information

    Open Energy Info (EERE)

    Analysis- Rock Over Core Stress Paleomagnetic Measurements Petrography Analysis Rock Density X-Ray Diffraction (XRD) X-Ray Fluorescence (XRF) References Page Area Activity Start...

  4. NREL: Energy Analysis - Daniel Inman

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

    Systems and Sustainability Analysis Group in the Strategic Energy Analysis Center. ... Primary research interests Sustainability analysis Biomass Scenario Model Education and ...

  5. NREL: Energy Analysis - Alberta Carpenter

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

    Alberta Carpenter is a member of the Technology Systems and Sustainability Analysis Group ... Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C. Office ...

  6. NREL: Energy Analysis - Catherine Burke

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

    the administrative assistant for the Technology Systems and Sustainability Analysis Group. ... Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C. Office ...

  7. NREL: Energy Analysis - Jenny Heeter

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

    Market analysis Policy analysis Utility regulation and analysis Primary research interests Voluntary green power market Renewable energy certificate markets and pricing Solar ...

  8. ENHANCED UNCERTAINTY ANALYSIS FOR SRS COMPOSITE ANALYSIS

    SciTech Connect (OSTI)

    Smith, F.; Phifer, M.

    2011-06-30

    The Composite Analysis (CA) performed for the Savannah River Site (SRS) in 2009 (SRS CA 2009) included a simplified uncertainty analysis. The uncertainty analysis in the CA (Smith et al. 2009b) was limited to considering at most five sources in a separate uncertainty calculation performed for each POA. To perform the uncertainty calculations in a reasonable amount of time, the analysis was limited to using 400 realizations, 2,000 years of simulated transport time, and the time steps used for the uncertainty analysis were increased from what was used in the CA base case analysis. As part of the CA maintenance plan, the Savannah River National Laboratory (SRNL) committed to improving the CA uncertainty/sensitivity analysis. The previous uncertainty analysis was constrained by the standard GoldSim licensing which limits the user to running at most four Monte Carlo uncertainty calculations (also called realizations) simultaneously. Some of the limitations on the number of realizations that could be practically run and the simulation time steps were removed by building a cluster of three HP Proliant windows servers with a total of 36 64-bit processors and by licensing the GoldSim DP-Plus distributed processing software. This allowed running as many as 35 realizations simultaneously (one processor is reserved as a master process that controls running the realizations). These enhancements to SRNL computing capabilities made uncertainty analysis: using 1000 realizations, using the time steps employed in the base case CA calculations, with more sources, and simulating radionuclide transport for 10,000 years feasible. In addition, an importance screening analysis was performed to identify the class of stochastic variables that have the most significant impact on model uncertainty. This analysis ran the uncertainty model separately testing the response to variations in the following five sets of model parameters: (a) K{sub d} values (72 parameters for the 36 CA elements in

  9. Transmission Planning Analysis Tool

    SciTech Connect (OSTI)

    2015-06-23

    Developed to solve specific problem: Assist transmission planning for regional transfers in interconnected power systems. This work was originated in a study for the U.S. Department of State, to recommend transmission reinforcements for the Central American regional system that interconnects 6 countries. Transmission planning analysis is currently performed by engineers with domainspecific and systemspecific knowledge without a unique methodology. The software codes of this disclosure assists engineers by defining systematic analysis procedures to help identify weak points and make decisions on transmission planning of regional interconnected power systems. Transmission Planning Analysis Tool groups PSS/E results of multiple AC contingency analysis and voltage stability analysis and QV analysis of many scenarios of study and arrange them in a systematic way to aid power system planning engineers or transmission operators in effective decision¬Ā]making process or in the off¬Ā]line study environment.

  10. Transmission Planning Analysis Tool

    Energy Science and Technology Software Center (OSTI)

    2015-06-23

    Developed to solve specific problem: Assist transmission planning for regional transfers in interconnected power systems. This work was originated in a study for the U.S. Department of State, to recommend transmission reinforcements for the Central American regional system that interconnects 6 countries. Transmission planning analysis is currently performed by engineers with domainspecific and systemspecific knowledge without a unique methodology. The software codes of this disclosure assists engineers by defining systematic analysis procedures to help identifymore¬†¬Ľ weak points and make decisions on transmission planning of regional interconnected power systems. Transmission Planning Analysis Tool groups PSS/E results of multiple AC contingency analysis and voltage stability analysis and QV analysis of many scenarios of study and arrange them in a systematic way to aid power system planning engineers or transmission operators in effective decision¬Ā]making process or in the off¬Ā]line study environment.¬ę¬†less

  11. Chemical Sector Analysis | NISAC

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

    NISACChemical Sector Analysis content top Chemical Supply Chain Analysis Posted by Admin on Mar 1, 2012 in | Comments 0 comments Chemical Supply Chain Analysis NISAC has developed a range of capabilities for analyzing the consequences of disruptions to the chemical manufacturing industry. Each capability provides a different but complementary perspective on the questions of interest-questions like Given an event, will the entire chemical sector be impacted or just parts? Which chemicals, plants,

  12. Analysis of Hydrologic Properties Data

    SciTech Connect (OSTI)

    H.H. Liu; C.F. Ahlers

    2001-12-20

    The purpose of this Analysis/Model Report (AMR) is to describe the methods used to determine hydrologic properties based on the available field data from the unsaturated zone at Yucca Mountain, Nevada. This is in accordance with the AMR Development Plan (DP) for U0090 Analysis of Hydrologic Properties Data (CRWMS M and O 1999c). Fracture and matrix properties are developed by compiling and analyzing available survey data from the Exploratory Studies Facility (ESF), Cross Drift of Enhanced Characterization of Repository Block (ECRB), and/or boreholes; air injection testing data from surface boreholes and from boreholes in ESF; in-situ measurements of water potential; and data from laboratory testing of core samples.

  13. EGR Cooler Deposit Analysis

    Broader source: Energy.gov [DOE]

    Analysis of fouling and performance of exhaust gas recirculation (EGR) coolers as a function of EGR flow rate, inlet gas and coolant temperatures, soot level, and hydrocarbon concentration

  14. Sustainability & Strategic Analysis

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

    ... Technologies Office * Design cases of biofuel pathways * Environmental sustainability metrics for conversion stage * GREET analysis of full pathway to identify drivers of GHG ...

  15. Modeling and Analysis

    Broader source: Energy.gov [DOE]

    DOE modeling and analysis activities focus on reducing uncertainties and improving transparency in photovoltaics (PV) and concentrating solar power (CSP) performance modeling. The overall goal of...

  16. Performance Analysis with Vampir

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

    (frank.winkler@tu-dresden.de) Performance Analysis with Vampir Disclaimer Performance tools will not automatically make you code run faster. They help you understand, what your...

  17. System Analysis Projects

    Broader source: Energy.gov [DOE]

    Geothermal Technologies Office Systems Analysis projects include environmental, regulatory, financial initiatives and efforts that solve non-technical barriers to geothermal deployment.

  18. Automated Hazard Analysis

    Energy Science and Technology Software Center (OSTI)

    2003-06-26

    The Automated Hazard Analysis (AHA) application is a software tool used to conduct job hazard screening and analysis of tasks to be performed in Savannah River Site facilities. The AHA application provides a systematic approach to the assessment of safety and environmental hazards associated with specific tasks, and the identification of controls regulations, and other requirements needed to perform those tasks safely. AHA is to be integrated into existing Savannah River site work control andmore¬†¬Ľ job hazard analysis processes. Utilization of AHA will improve the consistency and completeness of hazard screening and analysis, and increase the effectiveness of the work planning process.¬ę¬†less

  19. Decision Analysis for EGS

    Broader source: Energy.gov [DOE]

    Project objectives: DEVELOPMENT OF ANALYSIS TOOLS TO ASSESS: Uncertainties associated with exploration for EGS; Uncertainties associated with development of EGS; Uncertainties associated with operation of EGS.

  20. Independent Statistics & Analysis

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

    October 2014 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 Quarterly Coal Distribution Report April - June 2014 This report was...

  1. Scenario Analysis Meeting

    Broader source: Energy.gov [DOE]

    Presentation by Sigmund Gronich at the 2010-2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles and Infrastructure meeting on January 31, 2007.

  2. Asset Protection Analysis Guide

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2008-08-21

    The Guide provides examples of the application of as set protection analysis to several common problems. Canceled by DOE N 251.80.

  3. Sandia Energy - Analysis

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

    Climate Change Is the Subject of a New Book Analysis, Climate, Global Climate & Energy, Monitoring, News, News & Events, Sensing, Sensing & Monitoring, Water Security Climate...

  4. Fast Analysis and Simulation Team | NISAC

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

    NISACFast Analysis and Simulation Team

  5. Geographically-Based Infrastructure Analysis

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

    January 26, 2006 Geographically-Based Infrastructure Analysis (GIA) Utilizes GIS, ... Geographically-based Infrastructure Analysis GIS Transportation Technologies & Systems ...

  6. Analysis of Hydrologic Properties Data

    SciTech Connect (OSTI)

    L. Pan

    2004-10-04

    This analysis report describes the methods used to determine hydrologic properties based on the available field data from the unsaturated zone (UZ) at Yucca Mountain, Nevada. The technical scope, content, and management of this analysis report are described in the planning document ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654], Sections 2, 4, and 8). Fracture and matrix properties are developed by analyzing available survey data from the Exploratory Studies Facility (ESF), the Enhanced Characterization of Repository Block (ECRB) Cross-Drift, and/or boreholes; air-injection testing data from surface boreholes and from boreholes in the ESF; and data from laboratory testing of core samples. In addition, the report ''Geologic Framework Model'' (GFM2000) (BSC 2004 [DIRS 170029]) also serves as a source report by providing the geological framework model of the site. This report is a revision of the model report under the same title (BSC 2003 [DIRS 161773]), which in turn superceded the analysis report under the same title. The principal purpose of this work is to provide representative uncalibrated estimates of fracture and matrix properties for use in the model report Calibrated Properties Model. The term ''uncalibrated'' is used to distinguish the properties or parameters estimated in this report from those obtained from the inversion modeling used in ''Calibrated Properties Model''. The present work also provides fracture geometry properties for generating dual-permeability grids as documented in the scientific analyses report, ''Development of Numerical Grids for UZ Flow and Transport Modeling''.

  7. Nondestrucive analysis of fuel pins

    DOE Patents [OSTI]

    Stepan, I.E.; Allard, N.P.; Suter, C.R.

    1972-11-03

    Disclosure is made of a method and a correspondingly adapted facility for the nondestructive analysis of the concentation of fuel and poison in a nuclear reactor fuel pin. The concentrations of fuel and poison in successive sections along the entire length of the fuel pin are determined by measuring the reactivity of a thermal reactor as each successive small section of the fuel pin is exposed to the neutron flux of the reactor core and comparing the measured reactivity with the reactivities measured for standard fuel pins having various known concentrations. Only a small section of the length of the fuel pin is exposed to the neutron flux at any one time while the remainder of the fuel pin is shielded from the neutron flux. In order to expose only a small section at any one time, a boron-10-lined dry traverse tube is passed through the test region within the core of a low-power thermal nuclear reactor which has a very high fuel sensitivity. A narrow window in the boron-10 lining is positioned at the core center line. The fuel pins are then systematically traversed through the tube past the narrow window such that successive small sections along the length of the fuel pin are exposed to the neutron flux which passes through the narrow window.

  8. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  9. NREL: Energy Analysis - Energy Analysis Newsletter

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

    Decision Insight and Market Impacts Newsletter Unsubscribe Please enter your email address to unsubscribe from the Decision Insight and Market Impacts Newsletter. Complete E-mail Address: Unsubscribe If you have any questions about this online subscription service, please contact us. Printable Version Energy Analysis Home Capabilities & Expertise Key Activities Models & Tools Data & Resources Publications Partnerships Staff Working with Us Related Links News Did you find what you

  10. NREL: Energy Analysis - Energy Sciences Technology Analysis

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

    Energy Sciences Technology Analysis To help meet the nation's needs for clean energy, inexpensive alternative fuels, and a healthy environment, researchers in NREL's Energy Sciences are improving our understanding of the science behind renewable energy and energy-efficient technologies. These technologies include photovoltaics (solar cells), fuels and energy systems made from biomass (plants and waste products) and hydrogen, and advanced energy storage and transmission systems. In this work, our

  11. Hazard Analysis Database Report

    SciTech Connect (OSTI)

    GAULT, G.W.

    1999-10-13

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The FSAR is part of the approved TWRS Authorization Basis (AB). This document describes, identifies, and defines the contents and structure of the TWRS FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The TWRS Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The database supports the preparation of Chapters 3,4, and 5 of the TWRS FSAR and the USQ process and consists of two major, interrelated data sets: (1) Hazard Evaluation Database--Data from the results of the hazard evaluations; and (2) Hazard Topography Database--Data from the system familiarization and hazard identification.

  12. Resource Analysis | Department of Energy

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

    Systems Analysis ¬Ľ Analysis Methodologies ¬Ľ Resource Analysis Resource Analysis Resource Analysis determines the quantity and location of resources needed to produce hydrogen. Additionally, resource analysis quantifies the cost of the resources, as a function of the amount that can be available for hydrogen production. While often associated with renewable resources, resource analysis is also suitable for fossil resources and existing production facilities. Geographic Information Systems (GIS)

  13. Energy Analysis | Department of Energy

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

    Services ¬Ľ Energy Analysis Energy Analysis Photo courtesy of Dennis Schroeder, NREL 24348 Photo courtesy of Dennis Schroeder, NREL 24348 Energy analysis informs EERE decision-making by delivering analytical products in four main areas: Data Resources, Market Intelligence, Energy Systems Analysis, and Portfolio Impacts Analysis. The Energy Analysis website is designed to help energy experts and policymakers access energy analysis resources related to renewable energy and energy efficiency. It

  14. Demand Response Analysis Tool

    Energy Science and Technology Software Center (OSTI)

    2012-03-01

    Demand Response Analysis Tool is a software developed at the Lawrence Berkeley National Laboratory. It is initially funded by Southern California Edison. Our goal in developing this tool is to provide an online, useable, with standardized methods, an analysis tool to evaluate demand and demand response performance of commercial and industrial facilities. The tool provides load variability and weather sensitivity analysis capabilities as well as development of various types of baselines. It can be usedmore¬†¬Ľ by researchers, real estate management firms, utilities, or any individuals who are interested in analyzing their demand and demand response capabilities.¬ę¬†less

  15. Demand Response Analysis Tool

    SciTech Connect (OSTI)

    2012-03-01

    Demand Response Analysis Tool is a software developed at the Lawrence Berkeley National Laboratory. It is initially funded by Southern California Edison. Our goal in developing this tool is to provide an online, useable, with standardized methods, an analysis tool to evaluate demand and demand response performance of commercial and industrial facilities. The tool provides load variability and weather sensitivity analysis capabilities as well as development of various types of baselines. It can be used by researchers, real estate management firms, utilities, or any individuals who are interested in analyzing their demand and demand response capabilities.

  16. Graphical Contingency Analysis Tool

    Energy Science and Technology Software Center (OSTI)

    2010-03-02

    GCA is a visual analytic tool for power grid contingency analysis to provide more decision support for power grid operations. GCA allows power grid operators to quickly gain situational awareness of power grid by converting large amounts of operational data to graphic domain with a color contoured map; identify system trend and foresee and discern emergencies by performing trending analysis; identify the relationships between system configurations and affected assets by conducting clustering analysis; and identifymore¬†¬Ľ the best action by interactively evaluate candidate actions.¬ę¬†less

  17. Biochemical Platform Analysis

    SciTech Connect (OSTI)

    2006-06-01

    The objective of this project is to perform analysis for the Biochemical Platform to support the on-going research in biochemical conversion of biomass that will be part of an integrated biorefinery.

  18. Energy Sector Market Analysis

    SciTech Connect (OSTI)

    Arent, D.; Benioff, R.; Mosey, G.; Bird, L.; Brown, J.; Brown, E.; Vimmerstedt, L.; Aabakken, J.; Parks, K.; Lapsa, M.; Davis, S.; Olszewski, M.; Cox, D.; McElhaney, K.; Hadley, S.; Hostick, D.; Nicholls, A.; McDonald, S.; Holloman, B.

    2006-10-01

    This paper presents the results of energy market analysis sponsored by the Department of Energy's (DOE) Weatherization and International Program (WIP) within the Office of Energy Efficiency and Renewable Energy (EERE). The analysis was conducted by a team of DOE laboratory experts from the National Renewable Energy Laboratory (NREL), Oak Ridge National Laboratory (ORNL), and Pacific Northwest National Laboratory (PNNL), with additional input from Lawrence Berkeley National Laboratory (LBNL). The analysis was structured to identify those markets and niches where government can create the biggest impact by informing management decisions in the private and public sectors. The analysis identifies those markets and niches where opportunities exist for increasing energy efficiency and renewable energy use.

  19. Fluid Inclusion Gas Analysis

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

    Dilley, Lorie

    Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

  20. Building America Analysis Spreadsheets

    Broader source: Energy.gov [DOE]

    The Building America Analysis Spreadsheets are companions to the House Simulation Protocols, and can assist with many of the calculations and look-up tables found in the report. The spreadsheets...

  1. Building energy analysis tool

    DOE Patents [OSTI]

    Brackney, Larry; Parker, Andrew; Long, Nicholas; Metzger, Ian; Dean, Jesse; Lisell, Lars

    2016-04-12

    A building energy analysis system includes a building component library configured to store a plurality of building components, a modeling tool configured to access the building component library and create a building model of a building under analysis using building spatial data and using selected building components of the plurality of building components stored in the building component library, a building analysis engine configured to operate the building model and generate a baseline energy model of the building under analysis and further configured to apply one or more energy conservation measures to the baseline energy model in order to generate one or more corresponding optimized energy models, and a recommendation tool configured to assess the one or more optimized energy models against the baseline energy model and generate recommendations for substitute building components or modifications.

  2. Fluid Inclusion Gas Analysis

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

    Dilley, Lorie

    2013-01-01

    Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

  3. Systems Analysis Sub site

    SciTech Connect (OSTI)

    EERE

    2012-03-16

    Systems analysis provides direction, focus, and support for the development and introduction of hydrogen production, storage, and end-use technologies, and provides a basis for recommendations on a balanced portfolio of activities.

  4. Supervisory Program Analysis Officer

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will be responsible for the program analysis and evaluation of all activities which fall within the purview of the Office. The incumbent directs a moderate...

  5. Systems analysis-independent analysis and verification

    SciTech Connect (OSTI)

    Badin, J.S.; DiPietro, J.P.

    1995-09-01

    The DOE Hydrogen Program is supporting research, development, and demonstration activities to overcome the barriers to the integration of hydrogen into the Nation`s energy infrastructure. Much work is required to gain acceptance of hydrogen energy system concepts and to develop them for implementation. A systems analysis database has been created that includes a formal documentation of technology characterization profiles and cost and performance information. Through a systematic and quantitative approach, system developers can understand and address important issues and thereby assure effective and timely commercial implementation. This project builds upon and expands the previously developed and tested pathway model and provides the basis for a consistent and objective analysis of all hydrogen energy concepts considered by the DOE Hydrogen Program Manager. This project can greatly accelerate the development of a system by minimizing the risk of costly design evolutions, and by stimulating discussions, feedback, and coordination of key players and allows them to assess the analysis, evaluate the trade-offs, and to address any emerging problem areas. Specific analytical studies will result in the validation of the competitive feasibility of the proposed system and identify system development needs. Systems that are investigated include hydrogen bromine electrolysis, municipal solid waste gasification, electro-farming (biomass gasifier and PEM fuel cell), wind/hydrogen hybrid system for remote sites, home electrolysis and alternate infrastructure options, renewable-based electrolysis to fuel PEM fuel cell vehicle fleet, and geothermal energy used to produce hydrogen. These systems are compared to conventional and benchmark technologies. Interim results and findings are presented. Independent analyses emphasize quality, integrity, objectivity, a long-term perspective, corporate memory, and the merging of technical, economic, operational, and programmatic expertise.

  6. NREL: Energy Analysis - Staff

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

    Staff National Renewable Energy Laboratory (NREL) analysts have capabilities that span a wide range of renewable energy technologies. This site will help you learn more about the crosscutting analysis capabilities, energy-modeling background, and technology expertise of analysts in our Strategic Energy Analysis Center (SEAC). Strategic Planning and Direction Center Director: David Mooney Business Development: Debbie Brodt-Giles Integrated Energy System Model: Mark Ruth Synthesis and Integration:

  7. Techno-Economic Analysis

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

    Economic Analysis: Water splitting technologies and metrics Brian James Cassidy Houchins Daniel DeSantis Advanced Water Splitting Materials Workshop Stanford University 4/14/2016 Strategic Analysis Inc. Arlington VA Overview * Overview of H2A * Past H2A techno-economic analyses of water splitting technologies - High Temperature Solid Oxide Electrolysis Cell (SOEC) - Photoelectrochemical (PEC) - Solar Thermochemical Hydrogen (STCH) * System and Component Metrics - Tiered technology metrics *

  8. Decision Analysis for EGS

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

    Decision Analysis for EGS Herbert H. Einstein Massachusetts Institute of Technology April 22, 2013 This presentation does not contain any proprietary confidential, or otherwise restricted information. Insert photo of your choice MIT 2 | US DOE Geothermal Office eere.energy.gov DECISION ANALYSIS FOR EGS Relevance/Impact of Research OBJECTIVES CHALLENGE - How to develop EGS projects that are affected by many unknown and variable factors. Uncertainties, particularly those related to the subsurface,

  9. NREL Sustainability Analysis

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

    Date: March 25, 2015 Technology Area: Sustainability PIs: Daniel Inman and Garvin Heath Organization: National Renewable Energy Laboratory This presentation does not contain any proprietary, confidential, or otherwise restricted information. NREL Sustainability Analysis WBS 4.2.1.30 2 Goal - Air Emissions from Bioenergy Systems NREL's sustainability analysis program aims to better understand air emissions from the biofuel supply chain, applicable air regulations and implications for cost,

  10. Performance Measurement Analysis System

    Energy Science and Technology Software Center (OSTI)

    1989-06-01

    The PMAS4.0 (Performance Measurement Analysis System) is a user-oriented system designed to track the cost and schedule performance of Department of Energy (DOE) major projects (MPs) and major system acquisitions (MSAs) reporting under DOE Order 5700.4A, Project Management System. PMAS4.0 provides for the analysis of performance measurement data produced from management control systems complying with the Federal Government''s Cost and Schedule Control Systems Criteria.

  11. DOE Retro Analysis Plan

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

    Retro Analysis Plan August 2, 2011 Page 1 August 2, 2011 Daniel Cohen, Esq. Office of General Counsel U.S. Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Re: Preliminary Plan for Retrospective Analysis Dear Mr. Cohen: These comments are submitted by the Air-Conditioning, Heating, and Refrigeration Institute (AHRI) in response to the U.S. Department of Energy's (DOE) notice appearing in the July 11, 2011 Federal Register requesting comments on the Preliminary Plan for

  12. Analysis | Department of Energy

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

    Analysis Analysis The Bioenergy Technologies Office uses a wide range of analytical tools, data, and methodologies to support decision making, guide research, and demonstrate progress toward goals. The wide variety of available biomass feedstocks, conversion technologies, and integration strategies offer a broad range of feasible biofuels scenarios, so the Office focuses its analytical activities on the biofuels research and development (R&D) pathways that offer the best potential for

  13. ESF BLAST DESIGN ANALYSIS

    SciTech Connect (OSTI)

    E.F. fitch

    1995-03-13

    The purpose and objective of this design analysis are to develop controls considered necessary and sufficient to implement the requirements for the controlled drilling and blasting excavation of operations support alcoves and test support alcoves in the Exploratory Studies Facility (ESF). The conclusions reached in this analysis will flow down into a construction specification ensuring controlled drilling and blasting excavation will be performed within the bounds established here.

  14. Strategic Analysis and Modeling

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

    NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. Strategic Analysis and Modeling Mary J. Biddy, Ling Tao, Eric Tan, Yimin Zhang National Renewable Energy Laboratory March 24, 2015 Analysis and Sustainability Peer Review 2015 DOE Bioenergy Technologies Office (BETO) Project Peer Review 2 Goal Statement * Develop tools and perform analyses to address key questions in support of

  15. Interactive Comparative Analysis

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

    Comparative Analysis Interactive Comparative Analysis We can learn the correlations between sensors and modalities that differentiate activities (or operating modes) by using transfer learning. Our new approach to data fusion and signature discovery has a number of advantages and applications: * Finding correlations that differentiate datasets requires less data than finding correlations that explain datasets. * The differences between datasets are smaller in number, and often easier to

  16. Program Evaluation: Criteria, Logistics, Cost, and Analysis | Department of

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

    Energy Criteria, Logistics, Cost, and Analysis Program Evaluation: Criteria, Logistics, Cost, and Analysis There are a few criteria that are often recommended and used by the DOE, OMB, NAS, and others. Although programs may choose to define additional criteria, at a minimum all EERE programs are expected to use the following three criteria (referred to as "core criteria"). The three core criteria are the following: Quality, Productivity, and Accomplishments. Quality, as used here,

  17. Statistical Hot Channel Analysis for the NBSR

    SciTech Connect (OSTI)

    Cuadra A.; Baek J.

    2014-05-27

    A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.

  18. Sandia Energy - PV Modeling & Analysis

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

    PV Modeling & Analysis Home Stationary Power Energy Conversion Efficiency Solar Energy Photovoltaics PV Modeling & Analysis PV Modeling & AnalysisTara Camacho-Lopez2015-05-11T20:03...

  19. Systems Analysis | Department of Energy

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

    About the Geothermal Technologies Office ¬Ľ Systems Analysis Systems Analysis What is the Systems Analysis program? The Systems Analysis program in the Geothermal Technologies Office focuses primarily on: Environmental issues Policy, regulatory, and financing Economic Analysis and validation Data and Tools that support geothermal exploration and development As a key part of the Systems Analysis portfolio, a two-year, comprehensive Vision Study for geothermal energy development is underway to

  20. NREL: Energy Analysis - Key Activities

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

    Key Activities NREL conducts a broad range of energy analysis in support of the laboratory's programs and initiatives, DOE's Office of Energy Efficiency and Renewable Energy (EERE), technology transfer, and the greater energy analysis community. NREL's recent analysis activities include: Analysis of Project Finance Electric Sector Integration Energy-Water Nexus Life Cycle Assessment Harmonization Manufacturing Analysis Resource Assessment Printable Version Energy Analysis Home Capabilities &

  1. NREL: Energy Analysis - David Harrison

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

    Harrison David Harrison is a member of the Data Analysis and Visualization Group in the Strategic Energy Analysis Center. Software Engineer On staff since 2009 Phone number:...

  2. NREL: Energy Analysis - Lori Bird

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

    Market analysis Policy analysis Primary research interests Renewable energy and carbon markets Renewable energy policy Interplay of emissions and renewables policies Education and ...

  3. NREL: Energy Analysis - Eric Lantz

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

    Economic development impacts analysis State and federal policy analysis Primary research interests Policy applications for expanding renewable energy markets Evaluating economic ...

  4. NREL: Energy Analysis - Daniel Getman

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

    Daniel Getman Photo of Daniel Getman. Daniel Getman is a member of the Data Analysis and Visualization Group in the Strategic Energy Analysis Center. Geospatial Data Science Team...

  5. NREL: Energy Analysis - Dylan Hettinger

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

    Dylan Hettinger is a member of the Data Analysis and Visualization Group in the Strategic Energy Analysis Center. GIS Programmer Analyst On staff since 2010 Phone number: ...

  6. NREL: Energy Analysis - Michael Gleason

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

    Michael Gleason is a member of the Data Analysis and Visualization Group in the Strategic Energy Analysis Center. Scientist III - GIS On staff since April 2014 Phone number: ...

  7. NREL: Energy Analysis - David Mooney

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

    technologies and industry Design and cost analysis of concentrating solar power system ... Data Analysis and Visualization Group Energy Forecasting and Modeling Group Market and ...

  8. NREL: Energy Analysis - David Hurlbut

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

    and econometrics Optimization modeling Cost-benefit analysis Primary research interests Economic ... Data Analysis and Visualization Group Energy Forecasting and Modeling Group Market ...

  9. NREL: Energy Analysis - Maureen Hand

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

    Wind technology development risk analysis Wind turbine cost and scaling model development ... Data Analysis and Visualization Group Energy Forecasting and Modeling Group ...

  10. NREL: Energy Analysis - Parthiv Kurup

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

    Group in the Strategic Energy Analysis Center. CSP Cost Analyst and Engineer On staff since ... Data Analysis and Visualization Group Energy Forecasting and Modeling Group ...

  11. NREL: Energy Analysis - Tyler Stehly

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

    Energy economic models Wind energy systems Cost of energy analysis Project cost estimation ... Data Analysis and Visualization Group Energy Forecasting and Modeling Group ...

  12. NREL: Energy Analysis - Ahmad Mayyas

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

    in the Strategic Energy Analysis Center. Clean Energy Manufacturing and Cost Analyst On staff since April, ... Data Analysis and Visualization Group Energy Forecasting and ...

  13. NREL: Energy Analysis - Liz Torres

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

    and Visualization Group Energy Forecasting and Modeling Group Market and Policy Impact Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C....

  14. NREL: Energy Analysis - Heidi Pawlowski

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

    and Visualization Group Energy Forecasting and Modeling Group Market and Policy Impact Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C....

  15. NREL: Energy Analysis - Melissa Hudman

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

    and Visualization Group Energy Forecasting and Modeling Group Market and Policy Impact Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C....

  16. NREL: Energy Analysis - Michael Bahl

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

    and Visualization Group Energy Forecasting and Modeling Group Market and Policy Impact Analysis Group Technology Systems and Sustainability Analysis Group Washington D.C....

  17. Advanced engineering analysis

    SciTech Connect (OSTI)

    Freeman, W.R.

    1992-11-01

    The Advanced Engineering Analysis project is being used to improve the breadth of engineering analysis types, the particular phenomena which may be simulated, and also increase the accuracy and usability of the results of both new and current types of simulations and analyses. This is an interim report covering several topics under this project. Information on two new implementations of failure criteria for metal forming, the implementation of coupled fluid flow/heat transfer analysis capabilities, the integration of experimental shock and vibration test data with analyses, a correction to a contact solution problem with a 3-D parabolic brick finite element, and the development and implementation of a file translator to link IDEAS to DYNA3D is provided in this report.

  18. Proximate analysis of coal

    SciTech Connect (OSTI)

    Donahue, C.J.; Rais, E.A.

    2009-02-15

    This lab experiment illustrates the use of thermogravimetric analysis (TGA) to perform proximate analysis on a series of coal samples of different rank. Peat and coke are also examined. A total of four exercises are described. These are dry exercises as students interpret previously recorded scans. The weight percent moisture, volatile matter, fixed carbon, and ash content are determined for each sample and comparisons are made. Proximate analysis is performed on a coal sample from a local electric utility. From the weight percent sulfur found in the coal (determined by a separate procedure the Eschka method) and the ash content, students calculate the quantity of sulfur dioxide emissions and ash produced annually by a large coal-fired electric power plant.

  19. Foundations of VISAR analysis.

    SciTech Connect (OSTI)

    Dolan, Daniel H.

    2006-06-01

    The Velocity Interferometer System for Any Reflector (VISAR) is a widely used diagnostic at Sandia National Laboratories. Although the operating principles of the VISAR are well established, recently deployed systems (such as the fast push-pull and air delay VISAR) require more careful consideration, and many common assumptions about VISAR are coming into question. This report presents a comprehensive review of VISAR analysis to address these issues. Detailed treatment of several interferometer configurations is given to identify important aspects of the operation and characterization of VISAR systems. The calculation of velocity from interferometer measurements is also described. The goal is to derive the standard VISAR analysis relationships, indicate when these relationships are valid, and provide alternative methods when the standard analysis fails.

  20. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, Hugh R.; Meltzer, Michael P.

    1996-01-01

    The portable Contamination Analysis Unit (CAU) measures trace quantifies of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surface by measuring residual hazardous surface contamination, such as tritium and trace organics It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings.

  1. Contamination analysis unit

    DOE Patents [OSTI]

    Gregg, H.R.; Meltzer, M.P.

    1996-05-28

    The portable Contamination Analysis Unit (CAU) measures trace quantities of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surfaces by measuring residual hazardous surface contamination, such as tritium and trace organics. It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings. 1 fig.

  2. SAS4A/SASSYS-1: Fast Reactor Safety Analysis Code | Argonne National...

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

    The original code development was for sodium-cooled fast reactors, and sodium boiling can be modeled. However, basic core thermal-hydraulics and systems analysis features are ...

  3. Cost analysis guidelines

    SciTech Connect (OSTI)

    Strait, R.S.

    1996-01-10

    The first phase of the Depleted Uranium Hexafluoride Management Program (Program)--management strategy selection--consists of several program elements: Technology Assessment, Engineering Analysis, Cost Analysis, and preparation of an Environmental Impact Statement (EIS). Cost Analysis will estimate the life-cycle costs associated with each of the long-term management strategy alternatives for depleted uranium hexafluoride (UF6). The scope of Cost Analysis will include all major expenditures, from the planning and design stages through decontamination and decommissioning. The costs will be estimated at a scoping or preconceptual design level and are intended to assist decision makers in comparing alternatives for further consideration. They will not be absolute costs or bid-document costs. The purpose of the Cost Analysis Guidelines is to establish a consistent approach to analyzing of cost alternatives for managing Department of Energy`s (DOE`s) stocks of depleted uranium hexafluoride (DUF6). The component modules that make up the DUF6 management program differ substantially in operational maintenance, process-options, requirements for R and D, equipment, facilities, regulatory compliance, (O and M), and operations risk. To facilitate a consistent and equitable comparison of costs, the guidelines offer common definitions, assumptions or basis, and limitations integrated with a standard approach to the analysis. Further, the goal is to evaluate total net life-cycle costs and display them in a way that gives DOE the capability to evaluate a variety of overall DUF6 management strategies, including commercial potential. The cost estimates reflect the preconceptual level of the designs. They will be appropriate for distinguishing among management strategies.

  4. Germanium-76 Sample Analysis

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Engelhard, Mark H.; Zhu, Zihua

    2011-04-01

    The MAJORANA DEMONSTRATOR is a large array of ultra-low background high-purity germanium detectors, enriched in 76Ge, designed to search for zero-neutrino double-beta decay (0???). The DEMONSTRATOR will utilize 76Ge from Russia, and the first one gram sample was received from the supplier for analysis on April 24, 2011. The Environmental Molecular Sciences facility, a DOE user facility at PNNL, was used to make the required isotopic and chemical purity measurements that are essential to the quality assurance for the MAJORANA DEMONSTRATOR. The results of this first analysis are reported here.

  5. Environmental analysis support

    SciTech Connect (OSTI)

    Miller, R.L.

    1996-06-01

    Activities in environmental analysis support included assistance to the Morgantown and Pittsburgh Energy Technology Centers (METC and PETC) in reviewing and preparing documents required by the National Environmental Policy Act (NEPA) for projects selected for the Clean Coal Technology (CCT) Program. An important activity was the preparation for METC of a final Environmental Assessment (EA) for the proposed Externally Fired Combined Cycle (EFCC) Project in Warren, Pennsylvania. In addition, a post-project environmental analysis was prepared for PETC to evaluate the Demonstration of Advanced Combustion Techniques for a Tangentially-Fired Boiler in Lynn Haven, Florida.

  6. Retrofit Financial Analysis Tool

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Street and Parking Facility Lighting Retrofit Financial Analysis Tool was developed by a partnership of the DOE Municipal Solid-State Street Lighting Consortium, the Clinton Climate Initiative (CCI)/C40, and the Federal Energy Management Program (FEMP), for the financial analysis of retrofitting street and parking facility lighting with more efficient alternatives. Property owners, city and other government agencies, utilities, and energy efficiency organizations can use this tool to compute annualized energy and energy-cost savings, maintenance savings, greenhouse gas reductions, net present value, and simple payback associated with potential lighting upgrades.

  7. Finite Element Analysis Code

    Energy Science and Technology Software Center (OSTI)

    2005-06-26

    Exotxt is an analysis code that reads finite element results data stored in an exodusII file and generates a file in a structured text format. The text file can be edited or modified via a number of text formatting tools. Exotxt is used by analysis to translate data from the binary exodusII format into a structured text format which can then be edited or modified and then either translated back to exodusII format or tomore¬†¬Ľ another format.¬ę¬†less

  8. NREL: Energy Analysis - Jobs and Economic Competitiveness

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

    and Policy Impacts Analysis Workforce Development Competitive Advantage Competitve ... Energy Analysis Home Capabilities & Expertise Key Activities Analysis of Project Finance ...

  9. Handsfree Surface Analysis

    Energy Science and Technology Software Center (OSTI)

    2006-11-01

    The HANDSFREE SURFACE ANALYSIS software code enables unattended analysis of surfaces by desorption electrospray (DESI) and liquid-junction surface sampling probe (SSP) mass spectrometry. The software allows automated lane scanning, imaging (e.g. lane rastering), spot and array sampling, and array scanning methods by controlling the movement of the sample attached to a computer-controlled stage. The software is able to collect, visualize and analyze mass spectrometry data real-time for surface analysis purposes by interacting with mass spectrometrymore¬†¬Ľ instrumentation software. The software also enables data post processing for imaging and other analytical purposes. The software also contains image analysis approaches to control the sampling capillary-to-surface distance when used with DESI, and for automated formation and real-time reoptimization of the sampling probe-to-surface liquid microjunction when used with SSP. Control of these distances is essential to automated, hands-free operation of a DESI or SSP mass spectrometry system.¬ę¬†less

  10. Geothermal Play Fairway Analysis

    Broader source: Energy.gov [DOE]

    The concept of play fairway analysis was developed in the petroleum industry in response to a need to rapidly and accurately identify new areas that have the greatest potential for adding significant new reserves to a company‚Äôs portfolio and ‚ÄėSell‚Äô the need to invest in further exploration of those areas to company management and/or investors.